Text

2009-01-Draft Admin JPM
	ML091060249
Person / Time
Site:	Columbia
Issue date:	03/20/2009
From:	Garchow S; NRC Region 4
To:	; Energy Northwest
References
	50-397/09-301
	Download: ML091060249 (121)
	v • d • e

<<0 fill1111 Ai ikl PROGRAM TITLE COURSE TITLE LESSON TITLE LESSON LENGTH Lesson Plan PQD JPM PQD Code Exam PQD Code DIVISION TITLE DEPARTMENT PREPARED BY REVISED BY Code TECHNICAL REVIEW INSTRUCTIONAL RE APPROVED BY VIEW BY BY QENERGY

~t NORTHWEST INSTRUCTIONAL COVER SHEET LICENSED OPERATOR INITIAL TRAINING ADMIN JOB PERFORMANCE MEASURE DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

MAXIMUM STUDENTS

.5 HRS I

INSTRUCTIONAL MATERIALS INCLUDED Rev. No.

Simulator Guide PQD Code Rev. No.

LOO01587 Rev. No. 1 Rev. No.

Nuclear Training Operations Training Ron Hayden DATE 5/11/06 Ron Hayden DATE 10/6/08 DATE DATE DATE Operations Training Manager Verify materials current lAW SWP-TQS-Ol prior to use.

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPMSETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Make a copy of the current pull sheet from the simulator. Determine where Minimum ECP is and indicate it on copy of pull sheet by placing an '*1' next to the step and at the bottom of the column indicate that a *1 is

'Minimum ECP'. Ensure it is AFTER step indicated in initial conditions.

Have a copy of PPM 3.1.2 startup flowchart available for reference.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-OI56; SRO-0118 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 3.1.2 Rev. 68 Location: Simulator/Plant/Table Top NUREG 1123 Ref: 2.1.7 4.4 / 4.7 Performance Method: Perform L0001587 Rev. 1 Page 1 of 6

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

JPM CHECKLIST PROCEDURE VALIDATION:

Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

A plant startup is in progress. PPM 3.1.2 has been completed as follows: Step Lll has been completed, waiting at step Ll2 ; Step P I has not yet been completed; Step Q I0 has been completed and step Qll is in progress.

You are the RO pulling control rods and you note the following indications:

Time 0953

Coolant Temp 205°F

Control rod 10-47

Control rod position 18

Neutron level 8,000 CPS and rising

Period 145 seconds and stable

.You have been pulling control rods steadily since starting Group I of the Pull Sheet.

Control rod motion stopped approximately I minute ago.

INITIATING CUE:

Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your next action.

When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.

LOOO 1587 Rev. I Page 2 of 6

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

Items are Critical Steps Comments Element RECORD START TIME:

Standard Sat/Unsat If SRO position is being evaluated If RO position is being evaluated Using given information, determines that the reactor is critical or will be critical before the minimum ECP has been reached.

Directs RO to (stop control rod withdrawal and to) drive control rods in the reverse order until all control rods are fully inserted.

Using given information, determines that the reactor is critical or will be critical before the minimum ECP has been reached.

Notifies the CRS that he has stopped control rod withdrawal due to reactor being critical prior to the minimum allowable ECP.

S / U

S / U

Termination Criteria: Student completes the attached answer sheet and hands it to the examiner.

RECORD TERMINATION TIME:

Transfer to "Results of JPM" page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

L0001587 Rev. 1 Page 3 of 6

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

RESULTS OF JPM:

Examinee (Please Print):

Evaluator (Please Print):

Task Standard: SRO Candidate: To pass the JPM the candidate must indicate that direction is to be gi yen to the RO to drive control rods in the reverse order until all control rods are fully inserted.

RO Candidate: To pass the JPM the candidate must indicate that control rod withdrawal must be stopped and the CRS must be notifi'ed that the reactor is critical prior to the indicated minimum allowable ECP.

I Overall Evaluation I

Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 15 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

LOOOl587 Rev. I Page 4 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

A plant startup is in progress. PPM 3.1.2 has been completed as follows:

Step L11 has been conlpleted; Step PI has not yet been completed; Step Q9 has been completed and step Q lOis in progress.

The following indications are observed:

0953

Time

Coolant Temp 205 0 F

Control rod 10-47

Control rod position 18

Neutron level 8,000 CPS and rising

Period 145 seconds and stable Control rods have been steadily pulled since starting Group 1 of the Pull Sheet. Control rod motion stopped approximately 1 minute ago.

Cue:

Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your next action.

When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.

Page 5 of 6

JPM ANSWER SHEET NEXT ACTION TO BE TAKEN:

Page 6 of 6

CGS PULL SHEET COVER PAGE SEQUENCE FILE NAMED A2C19SU2.SEQ SEQUENCE TYPE A2 TOTAL NUMBER OF GROUPS 41 TOTAL NUMBER OP STEPS 488 PULL SHEET CHECK SUM 0016551495 SNE review:

DATE:

Y--1d4 5tJ~

ve;kcclrg DATE: 7~

SECOND ~eView: !-~ =~

/f/bX OPS reV1ew: S~---,Q...L~-I_~5-~

DATE:

~

Date / Time of startuP~~~~~~~~~L-~~~~~l?~l)~

Critical Data:

Recirc Suction Temperature Date / Time RWM Sequence Step Control Rod Position Period at Critical Data Rod Pattern at Critical attached (Screen dump or Printout )

Completed Pullsheets to be filed under PPM 9.3.9, DIC 1814.2 NOTICE: IF YOUR INITIALS APPEAR ON ANY PAGE OF THIS PULL SHEET, PLEASE SIGN AND INITIAL ON THE FOLLOWING PAGE Pull Sheet Check Sum

0016551495 poxaRPLax Pull Sheet Print Menu

CGS POLL SHEET COVER PAGE SEQUENCE FILE NAMED A2C19SU2.SEQ Initials iL Pull Sheet Chee~ sum

0016551.95 POWI1PL&X Pull Sh.et Print Menu

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 1 of 41 Insert l~t.

0 withdraw l~t ***

KUaber of step. on this page

1)

Control rod pattern at TOP of page

l.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Control rod pattern at BOTTOM of page

l.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 00 00 00 00 00 00 00 00 00 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 00 00 00 00 00 00 00 00 00 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Pull Sb**t Cb.c~ Sum

0016551"5 POWSRPLax Pull Sheet Print Menu

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 1 of 41 WITHDRAWAL CONTROL RODS FROM THE TOP TO THE BOTTOM OF THE PAGE

.. Cont.

Neutron Performed Verified Withdraw Plux by by Couple

Response

//1 Star RWK BPWS (Initial) (Initial)

Rod No.

Prom (2)

Here 1

1 To Chec~ (1)

Group-Step Group 00 48 26 -

31 1

Jlil 00 48 1

2 1

42 -

39 Al 00 42 -

23 48 1

4 1

3 1

00 48 1 -

5 34 -

31 1

00 48 18 - 39 1

/I 48 18 -

23 00 1

6 1

//{

/L 34 -

47 00 48 1

8 1

7 1

00 50 -

31 48 1

9 1

y 1

26 - 15 00 48 48 10 - 31 00 1 - 10 1

Iii tl.

/!..

1 -

11 1

26 -

47 00 48 y

/I 00 1 - 12 1

34 -

15 48 Iii

/f tfl..

(1) Continuous Withdraw Couple Check required when pulled to.8 T.S. S.R 3.1.3.5 (2) Neutron Plux Response (Y or N) only required prior to criticality

{P-10.SSO}

Pull Sheet Check Sum

001655~.95 POWBRPLIX Pull Sheet Print Menu Reactivity MaDager Review

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 2 of 41 In.er~ lia1~.

0 Wi~hdraw li.u~ **,

HUmber of.~ep. on thi. page

12 Control rod pattern at TOP of page

2.

02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 59 00 00 00 00 00 00 00 59 55 00 00 00 00 00 00 00 00 00 55 51 00 00 00 00 00 00 00 00 00 00 00 51 47 00 00 00 00 00 00 00 00 00 00 00 47 43 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 43 39 00 00 00 00 00 00 00 00 00 00 00 00 00 39 35 00 00 00 00 00

,00 00 00 00 00 00 00 00 00 00 35 31 00 00 00 00 00 00 00 00 00 00 00 31 27 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 27 23 00 00 00 00 00 00 00 00 00 00 00 00 00 23 19 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 19 15 00 00 00 00 00 00 00 00 00 00 00 15 11 00 00 00 00 00 00 00 00 00 00 00 11 07 00 00 00 00 00 00 00 00 00 07 03 00 00 00 00 00 00 00 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Control rod pattern at BOTTOM of page

2.

02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 59 00 00 00 00 00 00 00 59 55 00 00 00 00 00 00 00 55 51 00 00 00 00 00 00 00 00 00 00 00 51 47 00 00 00 00 00 00 00 00 00 47 43 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 43 39 00 00 00 00 00 00 00 00 00 00 00 39 35 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 35 31 00 00 00 00 00 00 00 00 00 00 00 31 27 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 27 23 00 00 00 00 00 00 00 00 00 00 00 23 19 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 19 15 00 00 00 00 00 00 00 00 00 15 11 00 00 00 00 00 00 00 00 00 00 00 11 07 00 00 00 00 00 00 00 07 03 00 00 00 00 00 00 00 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Pull Shee~ Check Sum

0016551"5 P~RPklX Pull She.~ PriD~ Manu

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 2 of 41 WITHDRAWAL CONTROL RODS FROM THE TOP TO THE (1) continuous Withdraw Coupla Chack required whan pulled to '8 (2) Neutron Plux Response (y or N) only required prior to criticality BPWS Group 1

1 1

1 From 00 00 00 00 00 00 00 00 00 00 00 00 To 48 48 48 48 48 48 48 48 48 48 48 48 Performed by (Init~l)

If RWK Group-Step Rod No.

Verified by (Initial)

BOTTOM OF THE PAGE

.. Cont.

Withdraw Couple Check~l)

'IL T.S. S.R 3.1.3.5

{P-10'550}

Full Out Light I{

/L Neutron Flux

Response

(2) y v

'v y

y y

Star Here 2

2

2 2

2

1 2

3 4

5 6

7 8

9 10 11 l:a 42 58 18 02 58 42 02 18 50 50 10 10 55 23 07 39 39 07 23 55 47 15 15 47 P~RPLax Pull Sheet Print Kanu Reactivity Manager Review

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 3 of 41 Inaart limdt.

0 Withdrew limit

1.

NUmbar of atapa on thi. pega.

Control rod pattern at TOP of page

3.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 00 00 00 00 00 00 00 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 00 00 00 00 00 00 00 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Control rod pattern at BOTTOM of page

3.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 14 00 00 00 00 00 14 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 14 00 00 00 00 00 14 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Pull Sheat Chack Sua

0016551.95 POWERPLEX Pull Sheet Print Manu

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 3 of 41 WITHDRAWAL CONTROL RODS FROM THE TOP TO THE BOTTOM OF THE PAGE j Cont.

Neutron Performed Verified Withdraw P'ull Flux RWM BPWS by by Couple Out R**ponse Group-Step Group Rod No.

From To (Initial) (Initial) Check (1)

Light (2) 3 -

1 2

18 - 47 00 101 3 -

2 2

42 - 47 00 14 3 -

3 2

18 - 15 00 14 3 -

4 2

42 - 15 00 14 Star Here

~

-fl (1) Continuoua Withdraw Couple Check required when pulled to.8 T.S. S.R 3.1.3.5

(.) Neutron P1ux Reapoaae (Y or N) oaly required prior to criticality

{P-IO.550}

~/

Pull Sheet Check Sum

0016551"5 POWKRP~X Pull Sheet Print Xenu Reactivity Xanager Review

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 4 of 41 In.ert l~t

1.

Withdraw limit *

~O NUmber of.tep. on thi. page.

Control rod pattern at TOP*of page

4.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 14 00 00 00 00 00 14 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 14 00 00 00 00 00 14 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Control rod pattern at BOTTOM of page

4.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 20 00 00 00 00 00 20 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 20 00 00 00 00 00 20 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Pull Sheet Check Sum

0016551.95 POWERP~X Pull Sheet Print Menu

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 4 of 41 WITHDRAWAL CONTROL RODS FROM THE TOP TO THE BOTTOM OF THE PAGE RWM Group-Step BPWS Group Rod No.

Prom To Performed by (Initial)

Verified by (Initial) ft Cont.

Withdraw Couple Check (1)

Full Out Light Neutron Flux

Response

(2) 4 -

1 2

18 - 47 14 20 4 -

2 2

42 -

47 14 20 4 -

3 2

18 - 15 14 20 4 -

4 2

42 - 15 14 20 Star Here (1) Continuou. Withdraw Couple Check required when pUllad to 48 T.S. S.R 3.1.3.5 (2) Nautron rlux Ra.pon.e (y or H) only required prior to criticality

{P-104550}

Pull Sheet Check Sum

0016551~'5 POWWRPLII Pull Sheet Print Menu Raactivity Xanager Revi..

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19S02.SEQ Page 5 of 41 In.ert lUait *

~O Withdraw limit *

~6 Number of atepa CD thia page.

4 Control rod pattern at TOP of page

5.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 20 00 00 00 00 00 20 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 20 00 00 00 00 00 20 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Control rod pattern at BOTTOM of page

5.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 26 00 00 00 00 00 26 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 26 00 00 00 00 00 26 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Pull Sheet Check Sum

0016551495 POWKRPL&X Pull Sheet Print Menu

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 5 of 41 WITHDRAWAL CONTROL RODS FROM THB TOP TO THE BOTTOM OF THE PAGE RWH Group-Step BPWS Group Rod No.

From To Performed by (Initial)

Verified by (Initial)

.. Cont.

Withdraw Couple Check (1)

Pull OUt Light Neutron Flux

Response

(2) 5 -

1 2

18 -

47 20 26 5 -

2 2

42 -

47 20 26 5 -

3 2

18 - 15 20 26 5 -

4 2

42 - 15 20 26 Star Here (1) Continuou. Withdraw Couple Check required when pulled to ~8 T.S. S.R 3.1.3.5

(~) Neutron Flux ae.pon.e (T or N) only required prior to criticality

{P-1045S0}

Full Sheet Check Sum

0016551~'5 Pow.RPLAX Pull Sheet Print Menu aeactivity lCa.aager Revi

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 6 of 41 In.art limit

26 Withdra" limit ***

xu.bar of.tap. on thi. paga.

Control rod pattern at TOP of page

6.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 26 00 00 00 00 00 26 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 26 00 00 00 00 00 26 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Control rod pattern at BOTTOM of page

6.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 00 00 00 00 00 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 00 00 00 00 00 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Pull Sheat Chaek Sua

0016551.'5 POWJlIlPLlIJ: Pull Shaat Print Manu

CONTROL ROO WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 6 of 41 WITHDRAWAL CONTROL RODS FROM THE TOP TO THE BOTTOM OF THE PAGE RWM Group-Step BPWS Group Rod No.

From To Performed by (Initial)

Verified by (Initial)

.. Cont.

Withdraw Coupl.

Check (1)

Full Out Light Neutron Flux R**poa**

(2) 6 -

1 2

18 - 47 26 48 6 -

2 2

42 -

47 26 48 6 -

3 2

18 - 15 26 48 6 -

4 2

42 - 15 26 48 Star Here (1) Continuoua Withdraw Couple ~eck required wben pulled to t8 T.S. S.R 3.1.3.5

(~l Neutron Flux Reaponae (y or N) only required prior to criticality

{P-104550}

Pull Sbeet Cbeck Bum -

0016551495 POWBRPL_X Pull Sbeet Print Menu R.activity Manager Review

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 7 of 41 In.ert limit.

0 Withdra.. liait

30 HUmber of.tep. on thi. page.

4 Control rod pattern at TOP of page

7.

02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 59 00 00 00 00 00 00 00 59 55 00 00 00 00 00 00 00 55 51 00 00 00 00 00 00 00 00 00 00 00 51 47 00 00 00 00 00 00 00 47 43 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 43 39 00 00 00 00 00 00 00 00 00 00 00 39 35 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 35 31 00 00 00 00 00 00 00 00 00 00 00 31 27 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 27 23 00 00 00 00 00 00 00 00 00 00 00 23 19 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 19 15 00 00 00 00 00 00 00 15 11 00 00 00 00 00 00 00 00 00 00 00 11 07 00 00 00 00 00 00 00 07 03 00 00 00 00 00 00 00 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Control rod pattern at BOTTOM of page

7.

02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 59 00 00 00 00 00 00 00 59 55 00 00 00 00 00 00 00 55 51 00 00 00 00 00 00 00 00 00 00 00 51 47 00 00 00 00 00 00 00 47 43 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 43 39 00 20 00 00 00 00 00 00 00 20 00 39 35 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 35 31 00 00 00 00 00 00 00 00 00 00 00 31 27 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 27 23 00 20 00 00 00 00 00 00 00 20 00 23 19 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 19 15 00 00 00 00 00 00 00 15 11 00 00 00 00 00 00 00 00 00 00 00 11 07 00 00 00 00 00 00 00 07 03 00 00 00 00 00 00 00 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Pull Sheet Check Sum

OO16SS1t9S PO"'RP~X Pull Sheet Print Xenu

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 7 of 41 WITHDRAWAL CONTROL RODS FROM THE TOP TO THB BOTTOM OF THE PAGE RWM Group-Step BPWS Group Rod No.

Prom To Performed by (Initial)

Verified by (Initial)

, Cont.

Withdraw Coupl.

Check (1)

Pull Out Light Neutron Flux Respons.

(2) 7 -

1 2

10 - 23 00 20 7 -

l

l 50 - 39 00 20 7 -

3

l 10 - 39 00

l0 7 -

4 2

50 -

23 00

l0 Star Here

~

(1) CODtinuou. Withdraw Couple Check require4 when pulle4 to t8 T.S. s.a 3.1.3.5 (J) Neutron 'lux ae.pon.e (Y or N) only require4 prior to criticality

{P-10tSSO}

Pull Sheet Check sum

0016~~14'5 POWlRPLBX Pull Sheet Print Menu Reactivity Manager aeview

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2. SEQ Page 8 of 41 In.art l~t

20 Withdraw l~t

U NUabar of.tap. on thi. paga.

4 Control rod pattern at TOP of page

8.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 20 00 00 20 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 00 00 00 00 00 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 00 00 00 00 00 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 20 00 00 20 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Control rod pattern at BOTTOM of page

8.

59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 00 00 00 00 00 06 00 00 00 00 00 00 00 00 00 10 00 00 00 00 00 00 14 00 00 00 00 00 00 00 00 00 00 00 00 00 18 00 00 00 00 00 00 00 00 00 22 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 26 00 00 00 00 00 00 00 00 00 00 00 00 30 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 34 00 00 00 00 00 00 00 00 00 00 00 00 38 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 42 00 00 00 00 00 00 00 00 00 46 00 00 00 00 00 00 00 00 00 00 00 00 00 50 00 00 00 00 00 00 54 00 00 00 00 00 00 00 00 00 58 00 00 00 00 00 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Pull Sh**t Check Sum

OO~655~495 POWBRPLBZ Pull Shaat Print Menu

CONTROL ROD WITHDRAWAL ORDER SHEET Sequence :

A2 A2C19SU2.SEQ Page 8 of 41 WITHDRAWAL CONTROL RODS FROM THE TOP TO THE BOTTOM OF THE PAGE RWM Group-Step BPWS Group Rod No.

Prom To Performed by (Initial)

Verified by (Initial)

Cont.

Withdraw Couple Check (1)

Full OUt Light Neutron Flux ResponBe (2) 8 -

1 2

10 -

23 20 48 8 -

2 2

50 - 39 20 48 8 -

3 2

10 - 39 20 48 8 -

4 2

50 -

23 20 48 Star Here (1) Continuou. Withdraw Couple Check require4 when pulle4 to 48 T.S. S.R 3.1.3.5

(~) Neutron P1ux.e.poe.e (Y or.) only require4 prior to criticality

{P-104550}

PUll Sheet Check Sum

0016551495 POWKRPLKX Pull Sheet Print Menu Reectivity Maneger.eview

I I _. ENABLED ~~~~~~iat~~~i~~;;' 'i~ cl~a~" _..

I 09 C8I1C91~

IWITHDRAW the 1st control rod as directed by the rod withdrawal sequence sheet to Ihe target position PPM9.3.9).

010 I~ the 1st control rod is withdrawn to ii's target position. ~ PERFORM the following:

OSP-RWM-C401 OSP-RSCS-C401 S11 014

1. STOP control rod withdrawal and notify the CRS.

r I

2. The CRS should direct Ihe CRO to drive control rods in the reverse order until all controls rods are 1-J fully inserted.

3. POC approval is required to proceed with further rod withdrawal.

1-I

4. Consider the applicability of T.S. 3.1.2.

I I

IC24J 015 I MAINTAIN reactor period GT 60 seconds.

016 017 VERIFY SRMIIRM overlap as follows:

a. VERIFY the SRM detectors are fully inserted

b. VERIFY at least 3 operable IRMs per trip system are on scale and increasing

c. VERIFY at least 3 operable SRMs read LT 3x1 DES q)S IC101@]

0191 ADVANCE the IRM range change switches 10 maintain an indication of 8 to 24 on the lower scale and 25 10 75

fin J4~AAAJ-V\\;

2

+

-C')ENERGY

~;!A'~ NORTHWEST

"-=-""

INSTRUCTIONAL COVER SHEET PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE - ADMIN LESSON TITLE RRC-P-IB DELTA T CAVITATION ALARM VERIFICATION (Time Critical)

MAXIMUM STUDENTS LESSON LENGTH

.5 HRS 1

INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LOOO1629 Rev. No.

0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current lAW SWP-TQS-Ol prior to use

lVIINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPMSETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Have a copy of the following:

4.602.A6.3-7 Alann Response (3 Pages total)

JPM Instructions:

Veri fy the current revisions of the procedure against the lPM. If the procedure revisions are di fferent than listed in the JPM, ensure the lPM is still technically correct. If the lPM is not technically correct, the lPM should be revised.

The evaluator document results on the "Results of lPM" page.

Tools/Equipment: None Safety Items: None Task Number: RO-1171 Validation Time: 7 minutes Prerequisite Training: N/A Time Critical: YES - 10 Minutes PPM

Reference:

4.602.A6.3-7 Rev. 16 Location: CLASSROOM OR SIMULATOR NUREG 1123 Ref: 2.1.25 (2.8/3.1)

Performance Method: PERFORM L0001629 Rev. 0 Page 1 of5

JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating in MODE 1 with the following information given: RRC-P-l A and RRC-P-IB are operating at 60 Hz. Annunciator 4.602.A6.3-7 has annunciated.

Per the ARP, the delta-T indication and counter on the FANUC and ASD Diagnostic display has been displayed and indicates the delta-Tis LT 10.7°F and the counter is counting down. B RRC Suction Temperature as indicated on RRC-TR-650 point 2 is 540°F and Steam Dome pressure as indicated on MS-PI-9 is 1020 psig.

INITIATING CUE:

You have been directed to perform the remainder of the ARP and indicate on the attached sheet what action you would take. When done, hand the completed sheet to the examiner. This is a TIME CRITICAL JPM and your time starts NOW.

Items are Critical Steps Comments Element RECORD START TIME (Time starts when completed reading initiating cue):

Refers to ARP and notes step 1 and 2 are completed.

Calculates B RRC suction temperature which is given: RRC-TR-650 point 2 is reading 540°F Calculates Steam Dome pressure saturation temperature by taking the pressure reading on MS-PI-9 which is given as being 1020 psig, referring to Attachment 1 to ARP and finding the saturation temperature.

Saturation temperature for 1020 psig is 549°F per Attachment 1 ofARP.

Calculates the Delta-T by subtracting 540 0 P from 549°P and coming up with a 9°F Delta-T.

Determines the alarm is a VALID alarm.

Refers to ARP Automatic Actions, 10 minutes after annunciation, both RRC pumps will run back to 15 Hz. Student circles choice #2 on attached sheet.

Termination Criteria: Student completes JPM, circles answer and hands completed sheet to the exam proctor.

RECORD TERMINATION TIME:

Transfer the following information to the "Results of JPM" page: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

L0001629 Rev. 0 Page 2 of5

RESULTS OF JPM:

DETERMINE VALIDITY OF DELTA T CAVITATION LIMIT ANNUNCIATOR Examinee (Please Print):

Evaluator (Please Print):

Task Standard: Circles Choice #2 on attached sheet.

Overall Evaluation Exam Code SAT / UNSAT (Circle Onc)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time I

I 7 Minutes / 10 Minutes I I

COlVIMENTS:

Evaluator's Signature:

Date:

L0001629 Rev. 0 Page 3 of5

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating in MODE 1 with the following information gIven:

RRC-P-IA and RRC-P-IB are operating at 60 Hz.

Annunciator 4.602.A6.3-7 has annunciated

~ blM d'*/fl..~

~~

Per the ARP, the delta-T indication and counter~n the PANUC ~~

ASD Diagnostic display.

~1he delta-T is LT lO.7°P and the counter is counting down.

B RRC Suction Temperature as indicated on RRC-TR-650 point 2 is 540 0 P Steam Dome pressure as indicated on MS-PI-9 is 1020 psig Cue:

You have been directed to perform the remainder of the ARP and indicate on the attached sheet what action you would take.

When done, hand the completed sheet to the examiner.

This is a TIME CRITICAL JPM and your time starts NOW.

Loaa1629 Rev. a Page 4 of 5

THIS ISA TIME CRITICALJPM Circle the choice of actions that you would take:

1. Calculations indicate the low Delta-T IS NOT VALID. I would place the Delta-T Cavitation Limit Bypass switch to "BYPASS" on H13 P634.

2. Calculations indicate the low Delta-T IS VALID. I would lower power per PPM 3.2.4 until both RRC pumps frequency is 15 Hz.

When completed, hand this sheet to the examiner.

L0001629 Rev. 0 Page 5 of 5

3-7 LOOP B DELTA T CAVITATION LIMIT 3-7 WINDOW SOURCE AUTOMATIC ACTIONS LOOPB DELTA T CAVITATION LIMIT RRC-RLY-K8B (LT 1O.rF)

(GT 18 Hz) 10 minutes after annunciation:

If GT 15 Hz, both RRC pumps ramp to 15 Hz.

RRC-M/A-676A & B transfer to manual.

RRC pump speed limited to 15 Hz NOTE: This is an expected alarm if reactor is shut down or during early stages of startup, if pump speed is GT 18 Hz.

NOTE: The plant lifetime limit for actual jet pump cavitation is 15 minutes in each RRC loop.

3.

Display the delta-T indication and counter on the FANUC & ASD Diagnostic display (RRC-VD-R673, H13-P602) by pressing "CONTROL STATION" on the ASD main menu.

4.

Verify that delta-Tis LT 10.rF with the counter counting down.

NOTE: Use Attachment 1, and/or steam tables to determine saturation temperature from steam dome pressure.

NOTE: The low delta-T signal is valid if the loop B calculated delta-T is LT 10.rF.

5.

Calculate delta-T by comparing B RRC suction temperature (RRC-TR-650 point 2 or TDAS X31O) to Steam Dome pressure saturation temperature (MS-PI-9) to determine if the low delta-T indication is valid.

NOTE: The delta-T counter will continue to count down after the ~ T Cavitation Limit Bypass switch has been taken to "BYPASS".

6.

IF the delta-T signal is not valid, THEN place the ~ T Cavitation Limit Bypass switch to "BYPASS" (Key 19)( H13-P634).

Otherwise, N/A.

(CONTINUED ON NEXT PAGE)

PROCEDURE NUMBER REVISION PAGE 4.602.A6 16 28 of 54

7.

IF the delta-T signal is valid, THEN perform the following: Otherwise, N/A.

a. IF the cause of the low delta-T is a Reactor Feed Pump trip AND resultant RRC pump run back, THEN check that the low delta-T clears in LE 3 minutes. Otherwise, N/A.

b. IF a valid low delta-T condition remains for GT 3 minutes, THEN lower power per PPM 3.2.4 until both RRC pumps frequency is 15 Hz.

Otherwise, N/A.

c. Check that the running RRC pumps have run back to 15 Hz after 10 minutes have elapsed.

d. Ensure RRC-MIA-676A & B has transferred to manual.

8.

IF entry conditions have been met, THEN enter ABN-CORE. Otherwise, NIA.

9.

Ensure RPV level stabilizes at set point.

10. Log the duration of low delta-T condition in the Control Room Log.

11. Evaluate the event per SWP-CAP-Ol, Attachment 8.2 "CR Initiation Guidance".

12. Have the STA perform a PPCRS/TDAS total save for the period from 5 minutes before the low delta-T condition started until 5 minutes after the low delta-T condition cleared.

(CONTINUED ON NEXT PAGE)

REFERENCES:

EWD-49E-0051 EWD-3E-0089 PROCEDURE NUMBER REVISION PAGE 4.602.A6 16 29 of 54

PRESSURE TEMPERATURE CONVERSION TABLE OF of of of PSIG PSIG PSIG PSIG II 1050 552 700 505 375 442 202 388 1040 551 690 504 370 440 199 387 1030 550 680 502 365 439 196 386 1020 549 670 500 360 438 193 384 1010 547 660 499 355 437 190 383 1000 546 650 497 350 435 187 382 990 545 640 495 345 434 184 381 980 544 630 494 340 432 181 380 970 543 620 492 335 431 178 379 960 541 610 490 330 430 175 377 950 540 600 489 325 429 172 376 940 539 590 487 320 427 169 374 930 538 580 485 315 426 166 373 920 536 570 483 310 424 163 372 910 535 560 481 305 423 160 371 900 534 550 479 300 421 157 369 890 532 540 477 295 420 154 368 880 531 530 476 290 418 151 366 870 530 520 474 285 417 148 365 860 528 510 472 280 415 145 363 850 527 500 470 275 414 142 362 840 526 490 468 270 412 139 360 830 524 480 466 265 411 136 359 820 523 470 463 260 409 133 357 810 522 460 461 255 407 130 356 800 520 450 459 250 406 127 354 790 519 440 457 245 404 124 352 780 517 430 455 240 402 121 350 770 516 420 452 235 400 118 349 760 514 410 450 230 399 115 347 750 513 400 448 225 397 112 345 740 511 395 447 220 395 109 343 730 510 390 445 215 393 106 341 720 508 385 444 210 391 103 340 710 507 380 443 205 389 100 338 NOTE: To determine the saturation temperature, record pressure as read from the instrument and record the temperature from this table, corresponding to the nearest pressure. Use standard rounding techniques. DO NOT INTERPOLATE.

PROCEDURE NUMBER 4.602.A6 REVISION 16 PAGE 30 of 54

PROGRAM TITLE COURSE TITLE LESSON TITLE INSTRUCTIONAL COVER SHEET LICENSED OPERATOR INITIAL TRAINING ADMIN JOB PERFORMANCE MEASURE DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-IA (ADMIN)

MAXIMUM STUDENTS LE ON LENGTH

.5 HRS INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Simulator Guide PQD Code JPM PQD Code Exam PQD Code L0001644 Rev. No. --

Rev. No. --

Rev. No. 0 --

Rev. No.

DIVISION TITLE DEPARTMENT PREPARED BY R.EVISED BY Nuclear Training Operations Training Ron Hayden DATE I0/6/08 DATE TECHNICAL REVIEW BY INSTRUCTIONAL REVIEW BY APPROVED BY Operations Training Manager DATE DATE DATE Verify materials current lAW SWP-TQS-Ol prior to use.

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-IA MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPMSETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Have the following drawings ready for candidate to reference:

M-526 Sheet 1 E-503 Sheet 7 and Sheet 12 EWD-38E-OO 1 EWD-38E-021 JPM Instructions:

Verify Current Procedure against lPM and ensure procedure critical steps match ifprocedure is different revision than listed in lPM. If critical steps have changed, the lPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of lPM" page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-1181 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

PPM 1.3.64; SWP-OPS-3; M-526-1; E-503-7 Location: Simulator / Classroom E-503-12; EWD-38E-OOl; EWD-38E-021 NUREG 1123 Ref: 2.2.13 4.1/4.3 Performance Method: Perform LOOO 1644 Rev. 0 Page 1 of 6

DETERMINE CLEARANCE REQillREMENTS FOR FPC-P-IA JPM CHECKLIST PROCEDURE VALIDATION:

Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating at full power. It is a Division 1 work week. Maintenance wants to replace the pump casing on FPC-P-IA.

INITIATING CUE:

You have been directed to determine the clearance order boundary component, required component position, and component tagging requirement necessary to perform work on FPC-P-IA.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME:

I I

I Identifies boundary and valve position required to isolate FPC-P-IA Determines tagging requirements Identifies FPC-P-I A Vent and Drain valves References M-526-1 and determines the following valves should be closed to isolate FPC-P-l A:

FPC-V-II4

FPC-V-II5A

FPC-V-II6A

FPC-V-ISIA Determines the following valves should be danger tagged:

FPC-V-II4

FPC-V-115A

FPC-V-II6A

FPC-V-ISIA Refers to M-526-I Detail 3 and determines vent and drain valves for FPC-P-IA:

FPC-V-IS?A (Vent)

FPC-V-I50A (Drain)

S IU

S IU

S / U

LOOO 1644 Rev. 0 Page 2 of 6

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-IA

Items are Critical Steps Standard Sat/Unsat Element Comments Determines that either FPC-V-187A requirements Detennines tagging S I U

tagged OR FPC-V-150A should be danger References E-503 sheet 12 and position required to isolate Identifies breaker and S I U

FPC-P-l A electrically detennines breaker 9B on MC-7B-B should be open for FPC-P-lA Determines MC-7B-B breaker 9B requirements Determines tagging should be danger tagged S IU

Identifies breaker and References E-503 sheet 7 and position required for FPC-determines breaker 1C on MC-7B-A S IU

should be open for FPC-V-18l A V-18lA Determines MC-7B-A breaker 1C requirements Detennines tagging S IU

should be danger tagged I

References EWD-38E-00I for FPC-requirements for FPC-P-Identifies Control Switch S/U P-lA and determines switch should I

be tagged in AUTO or AUTO after STOP position.

lA Detennines control switch for FPC-requirements Determines tagging S I U P-l A should be BLUE tagged References EWD-38E-02l for FPC-requirements for FPC-P-Identifies Control Switch S IU lA V-18l A and determines switch should be tagged in the NORM or NORM after CLOSE position Determines tagging Determines control switch for FPC-requirements S IU P-l A should be BLUE tagged Termination Criteria: Student completes the attached answer sheet and hands it to the examiner.

RECORD TERMINATION TIME:

Transfer to "Results of JPM" page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

1.0001644 Rev. 0 Page 3 of 6

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-IA ANSWER KEY:

COMPONENT FPC-V-114 FPC-V-115A FPC-V-II6A REQUIRED POSITION Closed Closed Closed TAGGING REQUIREMENT (TYPE OF TAG)

Danger Danger Danger Breaker 9B for FPC-P-I A on MC-7B-B Breaker 1C for FPC-V-I81 A on MC-7B-A Open Open Danger Danger FPC-V-I50A and / or FPC-V-I87A Open Danger I

LOOO 1644 Rev. 0 Page 4 of 6

DETERMINE CLEARANCE REQUIREMENTS FOR FPC-P-IA RESULTS OF JPM:

Examinee (Please Print):

Evaluator (Please Print):

Task Standard: Student correctly identifies the components, component position, and tagging requirements to mechanically and electrically isolate FPC-P-IA.

Exam Code Overall Evaluation SAT / UNSAT (Circle One)

Verified Procedure #fRev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 15 Minutes INA COMMENTS:

Evaluator's Signature:

Date:

L0001644 Rev. 0 Page 5 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating at full power.

It is a Division 1 work week.

Maintenance wants to replace the pump casing vent valve on FPC-P-IA.

Cue:

You have been directed to determine the clearance order boundary component, required component position, and component tagging requirement necessary to perform work on FPC-P-IA.

Page 5 of 6

JPM ANSWER SHEET The following is required to perform work on FPC-P-l A:

TAGGING REQUIRED REQUIREMENT COMPONENT POSITION (TYPE OF TAG)

When completed, hand this sheet to the examiner.

Page 6 of 6

() Itd.¥U /:'"

~£f OENERGY.

l_~~,lU NORTHWEST

~

INSTRUCTIONAL COVER SHEET INITIAL LICENSED OPERATOR TRAINING PROGRAM TITLE COURSE TITLE LESSON TITLE LESSON LENGTH

.5 HRS Lesson Plan PQD Code Simulator Guide PQD Code lPM PQD Code Exam PQD Code DIVISION TITLE DEPARTMENT PREPARED BY REVISED BY TECHNICAL REVIEW BY INSTRUCTIONAL REVIEW BY APPROVED BY 0

5/29/08 lOB PERFORMANCE MEASURE - ADMIN DETERMINE MINIMUM AND MAXIMUM STAY TIMES MAXIMUM STUDENTS I

INSTRUCTIONAL MATERIALS INCLUDED Rev. No.

Rev. No.

LOOO1632 Rev. No.

Nuclear Training Operations Training Ron Hayden Rev. No.

DATE DATE DATE DATE DATE Operations Training Manager Verify materials current lAW SWP-TQS-O 1 prior to use

MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPMSETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Each student should have access to a calculator.

Have a copy of the RWP for student.

JPM Instructions:

Verify the current revisions of the procedure against the lPM. If the procedure revisions are different than listed in the lPM, ensure the lPM is still technically correct. If the lPM is not technically correct, the lPM should be revised.

The evaluator document results on the "Results of lPM" page.

Tools/Equipment: Calculator Safety Items: None Task Number: RO-0022 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

N / A Location: CLASSROOM NUREG 1123 Ref: 2.3.2 (2.5 / 2.9)

Performance Method: PERFORM L0001632 Rev. 0 Page 1 of5

JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating in MODE 1 at full power. You have been selected to work with maintenance personnel on a valve located in contaminated zone in the North East comer of Reactor Building 422' by the R5 sump. Your accumulated dose for the year is 1800 mrem.

INITIATING CUE:

Using the high and low values associated with the radiation field you will be working in, answer the questions on the attached sheet. When completed, hand the sheet to the examiner.

Items are Critical Steps Comments Element RECORD START TIME:

Refers to RWP and determines the valve is in a High Radiation area.

High rad area radiation levels are 100 mremlhr to 1000 mremlhr Administrati~e dose limit at Columbia is 2 Rem (2000 mrem) 2000 - 1800 = 200 mrem to dose admin limit Question #1 - The minimum time to get 200 mrem in a 1000 mrem area is 1/5th of an hour which is 12 minutes. Start time is 0800, therefore you could exceed your admin dose limit at 0812 (accept 8010 to 8015)

Question #2 The maximum time to get 200 mrem (at 100 mremlhr) would be 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Start time is 0800 therefore the maximum stay time is until 1000 (accept 0955 to 1005).

Termination Criteria: Student answers questions and hands completed sheet to the examiner.

RECORD TERMINATION TIME:

Transfer the following information to the "Results of JPM" page: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

L0001632 Rev. a Page 2 of 5

RESULTS OF JPM:

DETERMINE MINIMUM AND MAXIMUM STAY TIMES Examinee (Please Print):

Evaluator (Please Print):

Task Standard: Fills in blanks on attached sheet indicating that 1012 is the earliest time and 1200 is the latest time.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 10 Minutes / N / A COMMENTS:

Evaluator's Signature:

Date:

L0001632 Rev. 0 Page 3 of5

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating in MODE 1 at full power.

You have been selected to work with maintenance personnel on a valve located in the contamination zone in the North East comer of Reactor Building 422' by the R5 sump.

Your accumulated dose for the year is 1800 mrem.

Cue:

Using the high and low values associated with the radiation field you will be working in, answer the two questions on the attached sheet.

When completed, hand the sheet to the examiner.

L0001632 Rev. 0 Page 4 of5

Use the HIGH and LOW values associated with the radiation field you will be working in to answer the following questions:

If the job starts at 0800....

1....what time represents the earliest time that you could exceed Columbia's administrative dose limit?

2....what tinle represents the latest time that you could stay in the area and still not exceed Columbia's administrative dose limit?

When completed, hand this sheet to the examiner.

L0001632 Rev. 0 Page 5 of5

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating in MODE 1 at full power.

You have been selected to work with maintenance personnel on a valve located in the contamination zone in the North East comer of Reactor Building 422' by the R5 sump.

Your accumulated dose for the year is 1800 mrem.

Cue:

Using the high and low values associated with the radiation field you will be working in, answer the two questions on the attached sheet.

When completed, hand the sheet to the examiner.

LOOO 1632 Rev. 0 Page 4 of5

Use the HIGH and LOW values associated with the radiation field you will be working in to answer the following questions:

If the job starts at 0800....

1....what time represents the earliest time that you could exceed Colunlbia's adnlinistrative dose limit?

2.... what time represents the latest time that you could stay in the area and still not exceed Columbia's administrative dose limit?

When completed, hand this sheet to the examiner.

L0001632 Rev. a Page 5 of 5

'1533.1 COLUMBIA GENERATING STATION HEALTH PHYSICS SURVEY MAP AND RECORD

'NrlENERGY 15332

;y NORTHWEST Peopl** V'-Ion' SoIu1:I.,....

Lorntlon RX 422' 1441' South Side RVVP 30001767 Job VVeeklv ROlrtine Survey Inst.lSeriaINo.

PjUL I QUI Jj?

Counter/Serial No.

L J ({ (t 1 ;-'9 DOSE RATES IN mremlhr G.oMhIIA UNLESS NOTED l

RX 422 South Side I-L

.',01 A 10 RHR "B" Pump RfTt.

-M FDfI-v~rn ~

1014

~D"-V-2

'814

>>))),)JgI - N lOllll Dof.4!

.....gl\\u*

3 3

4

'-'-e

'50120

.~ e, 2

\\~

34 2

4 I

'I"!

7 I.

I B

I 9,4 I

RX 5

I

",:,:,:~,~-.itf Status Boan::l Updated

~es ~/A IIIII SOPs Verified ~l,ooo dpmlloocm' lKJYes QIl/A I IIII Posted Radiological Boundaries Verified Correct roves O'I/A

-N

-L Rx Building Truo< BoilY B

I 441 South Side t.-

V{e((((<<~

SUlvey No.

5744 Survev Date 11129107 Survey Tirn e 0400

~o POV\\er 100%

Surveyor A. J Arroyos I RevieVl.ef CONT AMINATION SURVEY RE SUL TS All disc smea, resu~s are less than 1,000 dpmllOOan'l3vand less than 1,000 dpml PA-l AS I3v except as not ed.

No.

Location Acti~ty 2

Drip Tray 2K 3

Lip of Drip Tray 2K

'\\

"\\,

"\\.

"\\,

\\.,.....

'\\

"'\\

'\\ '.\\

Air Sample Resu~"

N/A Hzl njedion Rate (scnn) 10 Dose Received for Survey: 3 mrem Comments:

Fbor dralu all... 11'; dpm.pa-LAS.

Ver~d Gattie OOP aid UJltgg::lb:! afl:... 11;; ~m~a-lAS.V~rtnr.!'<I$llJhgg~a: ateJ tplllg, are It IJOrlOlgO[J'Il f.Allpo::thgl arotlcJ Co.tam 1131!d Art3s. <1DDD~m~a AIOnt r.ns. <1m Itm/U II leu I01!d.

Area Not Surveyed e> Very High Radiation Area High Radiation ftrea 6 Radiologically C ontroled ftrea,llJrborne Radioadiv~y Area fJI Denotes Floor Drain Contaminated Area e High-High Radiation Area 0 Radiation ftrea

@> Radioactive Materials Nea R# SUm p Location

I Silo I'J";~,

~

ENERGY

~iJ NO'RTHWEST

--=

INSTRUCTIONAL COVER SHEET PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE lOB PERFORMANCE MEASURE - SRO ADMIN LESSON TITLE DETERMINATION OF SHIFT STAFFING AND OVERTIME RESTRlCTIONS LESSON LENGTH

.5 HRS Lesson Plan PQD Code Simulator Guide PQD Code lPM PQD Code Exam PQD Code MAXIMUM STUDENTS I

INSTRUCTIONAL MATERIALS INCLUDED LOOO1643 Rev. No.

Rev. No.

0 DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/2/08 REVISED BY DATE TECHNICAL REVIEW BY DATE fNSTRUCTIONAL REVIEW BY DATE APPROVED BY Operations Training Manager DATE Verify materials current lAW SWP-TQS-O1 prior to use

MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPMSETUP Simulator Ies; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

JPM Instructions:

Verify the current revisions of each drawing against the lPM. If the drawings are a different revision than listed in the lPM, ensure the lPM is still technically correct. If the lPM is not teclmically correct, the lPM should be revised.

The evaluator document results on the "Results of lPM" page.

Tools/Equipment: None Safety Items: None Task Number: SRO-0002 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 1.3.27 Rev. 27 Location: CLASSROOM OR SIMULATOR NUREG 1123 Ref: 2.1.5 (3.9)

Performance Method: PERFORM L0001643 Rev. 0 Page 1 of7

JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the IPM, verify that the critical task steps are the same. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating in MODE 1 and has been on line for 100 days. One of the required on-shift Reactor Operators for the upcoming 0700-1900 shift has called in sick. You have been assigned to find a replacement Reactor Operator.

INITIATING CUE:

Given the days and number of hours per day previously worked, determine if any of the following three Reactor Operators could be called into work on the upcoming day shift (0700 1900 on October 21 st) without prior authorization. On the answer sheet provided, circle your choice for the three operators. When done, hand the completed sheet to the examiner.

Items are Critical Steps Comments II Element Standard SatiUnsat RECORD START TIME:

Evaluates work history ofRO#1 Determines that RO#1 has against hours worked restrictions:

worked 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months on October An individual shall not be 20th and would exceed 24 permitted to work more than:

hours in any 48-hour period requirement if called into work Third bullet: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period Evaluates work history ofRO#2 Determines that RO#2 has against hours worked restrictions:

worked 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in the An individual shall not be previous 6 days (October 14 permitted to work more than:

thru October 20th ) and would Fourth bullet: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 168-hour (seven day) period 168-hour period requirement if called into work Evaluates work history ofRO#3 Determines that RO#3 would against hours worked restrictions:

not exceed any of the hours An individual shall not be worked restrictions if called permitted to work more than:

into work 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 168-hour period S / U

S / U

S /u

L0001643 Rev. 0 Page 2 of7

Termination Criteria: Student circles either Can or Cannot be called into work for the three Reactor Operators and hands completed sheet to the exam proctor.

RECORD TERMINATION TIME:

Transfer the following information to the "Results of JPM" page: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

L0001643 Rev. 0 Page 3 of7

RESULTS OF JPM:

DETERMINATION OF SHIFT STAFFING AND OVERTIME RESTRICTIONS Examinee (Please Print):

Evaluator (Please Print):

Task Standard: Circles "CAN NOT be called into work" for RO#l and RO#2 and "CAN be called into work" for RO#3.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 10 Minutes / NA COMMENTS:

Evaluator's Signature:

Date:

L0001643 Rev. 0 Page 4 of7

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating in MODE 1 and has been on line for 100 days.

One of the required on-shift Reactor Operators for the upcoming 0700 1900 shift has called in sick.

You have been assigned to find a replacement Reactor Operator.

Cue:

Given the days and number of hours per day previously worked., determine if any of the following three Reactor Operators could be called into work on the upcoming day shift (0700 - 1900 on October 21st) without prior authorization.

On the answer sheet provided., circle your choice for the three operators.

When done., hand the completed sheet to the examiner.

LOOOl643 Rev. 0 Page50f7

Work history for Reactor Operator #1:

October 14 October 15 October 16 October 17 October 18 October 19 October 20 Worked 0700 - 2200 OFF Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 OFF Worked 0700 - 2200 Work history for Reactor Operator #2:

October 14 October 15 October 16 October 17 October 18 October 19 October 20 OFF Worked 0700 - 1500 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Work history for Reactor Operator #3:

October 14 October 15 October 16 October 17 October 18 October 19 October 20 Worked 0700 - 2200 Worked 0700 - 1500 Worked 0700 - 1900 OFF Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 L0001643 Rev. 0 Page 60f7

ANSWER SHEET Circle your choice:

Reactor Operator #1:

CAN BE CALLED INTO WORK OR CAN NOT BE CALLED INTO WORK Reactor Operator #2:

CAN BE CALLED INTO WORK OR CAN NOT BE CALLED INTO WORK Reactor Operator #3:

CAN BE CALLED INTO WORK OR CAN NOT BE CALLED INTO WORK When completed, hand this sheet to the examiner.

L0001643 Rev. 0 Page 7 of7

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating in MODE 1 and has been on line for 100 days.

One of the required on-shift Reactor Operators for the upcoming 0700 1900 shift has called in sick.

You have been assigned to find a replacement Reactor Operator.

Cue:

Given the days and number of hours per day previously worked, determine if any of the following three Reactor Operators could be called into work on the upcoming day shift (0700 -

1900 on October 21st) without prior authorization.

On the answer sheet provided, circle your choice for the three Reactor Operators.

When done, hand the completed sheet to the examiner.

LOOO 1643 Rev. 0 Page 5 of7

Work history for Reactor Operator # 1:

October 14 October 15 October 16 October 17 October 18 October 19 October 20 Worked 0700 - 2200 OFF Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 OFF Worked 0700 - 2200 Work history for Reactor Operator #2:

October 14 October 15 October 16 October 17 October 18 October 19 October 20 OFF Worked 0700 - 1500 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Work history for Reactor Operator #3:

October 14 October 15 October 16 October 17 October 18 October 19 October 20 Worked 0700 - 2200 Worked 0700 - 1500 Worked 0700 - 1900 OFF Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 L0001643 Rev. 0 Page 6 of7

ANSWER SHEET Circle your choice:

Reactor Operator #1:

CAN BE CALLED INTO WORK OR CAN NOT BE CALLED INTO WORK Reactor Operator #2:

CAN BE CALLED INTO WORK OR CAN NOT BE CALLED INTO WORK Reactor Operator #3:

CAN BE CALLED INTO WORK OR CAN NOT BE CALLED INTO WORK When completed, hand this sheet to the examiner.

LOOOl643 Rev. 0 Page7of7

ENERGY NORTHWEST People' Vision* Solutions COLUMBIA GENERATING STATION PLANT PROCEDURES MANUAL NUMBER Approver:

1.3.27 Sponsor:

MG Pratt VOLUME NAME ADMINISTRATIVE PROCEDURES s eTlaN CONDUCT OF OPERATIONS TITLE EXCESSIVE HOURS WORKED CONTROL DIC 1308.1 INFORMATION USE 56 CURRENT REVISION DATE DPBrown for SL Belcher QPR: MB Blake 12/20/06 I

I PROCEDURE 1.3.27 UMBER REVISION 27 PAGE 1 of 10 I

TABLE OF CONTENTS 1.0 PURPOSE..................................................... 3 2.0 RESPONSIBILITIES 3

2.1 Plant General Manager or Designee................................ 3 2.2 Manager/Supervisor/Leader 3

2.3 Each Employee 3

2.4 Energy Northwest Technical Representative 3

2.5 Contractor Supervision 3

3.0 PROCEDURE 4

3.1 Hours Worked Restrictions 4

3.2 Deviation to Hours Worked Restrictions 5

3.3 Authorization to Exceed Hours Worked Restriction 6

3.4 Review of Individual Hours Worked 6

3.5 Employee Tracking of Hours Worked 6

4.0 DOCUMENTATION 7

5.0 DEFINITIONS 7

6.0 REFERENCES

................................................. 8 7.0 ATTACHMENTS 8

7.1 Request for Deviation of Hours Worked Restrictions..................... 9 7.2 Work Hour Limit Applicability 10 PROCEDURE NUMBER 1.3.27 REVISION 27 PAGE 2 of 10

1.0 PURPOSE This procedure establishes limitations and controls for work hours for all station Columbia Generating Station personnel and contractors who perform safety related functions.

{R-4804}, {R-8858}

2.0 RESPONSIBILITIES 2.1 Plant General Manager or Designee Authorizes deviations to the working hour restrictions for workers, as defined in.2, who perform safety related functions.

{R-4739}

2.2 Supervisor/Manager

{P-32063}

2.2.1 Review individual schedules to ensure that excessive hours have not been assigned/worked.

2.2.2 Ensure that personnel reporting to them comply with the hours worked restrictions contained in this procedure.

2.2.3 Recommends approval for deviation to the working hour restrictions for workers, as defined in Attachment 7.2, who perform safety related functions.

{R-4739}

2.3 Each Employee

{P-32063, P-157232}

Each employee has the responsibility to ensure their hours worked comply with the terms and limitations of this procedure.

2.4 Energy Northwest Technical Representative 2.4.1 Monitor contractor personnel hours worked for compliance with the restrictions contained in this procedure.

2.4.2 Ensure communication of monitoring responsibilities occurs if contractor personnel transfer from one organization/individual to another.

2.5 Contractor Supervision Monitor contractor personnel hours worked for compliance with the restrictions contained in this procedure.

PROCEDURE 1.3.27 MBER REVlSION 27 PAGE 3 of 10

3.0 PROCEDURE 3.1 Hours Worked Restrictions OTE: Overtime is not routinely scheduled to compensate for an inadequate number of personnel to safely operate and maintain the plant. However, extended periods of shutdown for refueling, major maintenance, major plant modifications, unforeseen problems, or offsite business or work activity may require substantial amounts of overtime to be used.

Limit the use of overtime to perform work to the following maximum work hours:

3.1.1 An individual shall not be permitted to work more than:

NOTE: All of the following are exclusive of shift turnover time:

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 168-hour (seven day) period 3.1.2 A break of at least eight continuous hours shall be allowed between scheduled work periods, including shift turnover time.

3.1.3 Except during extended shutdown periods, consider the use of excessive work hours on an individual basis and not for the entire staff on a shift.

NOTE: The following step is not applicable during extended periods of shutdown, for refueling, major maintenance, or major plant modifications.

{R-4737}

3.1.4 An individual should not work more than (14) consecutive days without having (2) days off.

{R-4737}

3.1.5 If a licensed Reactor Operator or Senior Reactor Operator has been working more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months at assignments other than the Control Room, he/she shall have a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months break before reassignment to the Control Room.

{R-4742}

PROCED RE 1.3.27 UMBER REVISION 27 PAGE 4 of 10

3.1.6 A Reactor Operator should not be required to work in excess of eight continuous hours at the control board. During a shift, the Reactor Operator should be periodically relieved by another Reactor Operator on shift.

{R-4801, R-6364}

3.1.7 Shift turnover time should not exceed one hour. Turnover time is not included as part of hours worked restriction and should not normally cause a shift worker to exceed a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift by more than one (1) hour, inclusive of on coming and off-going shift turnover.

{P-1l8035}

3.1.8 When a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift individual, filling a minimum shift staffing position, does not report to work on time, the on-duty shift individual should report the fact to the Shift Manager. The individual has a maximum of one hour (maximum turnover time) to be properly relieved. The Shift Manager will determine how to fill the vacancy.

3.2 Deviation to Hours Worked Restrictions NOTE: The Supervisor/Manager is responsible for identifying the authorized work duration and the time/date for the completion of the work.

Supervisor/Manager/Designee requests PRIOR authorization for deviation of the hours worked restrictions herein by completing the Request for Deviation of Hours Worked Restrictions (Attachment 7.1). Adequate justification includes the reasons why the individual is the only person who can do the work and the work is vital.

3.2.1 Justification should include the job is an emergency necessary to support the safe and efficient operation of the plant and time is not available to obtain another individual and the individual is necessary for job continuity to minimize mistakes or the individual possesses critical job skills necessary for the completion of the task.

PROCEDURE NUMBER REVlSIO PAGE 1.3.27 27 I

5 of 10

5 ENERGY NORTHWEST INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON T1TLE DETERMINE IF MODE CHANGE IS ALLOWED (ADMIN)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Simulator Guide PQD Code JPM PQD Code Exam PQD Code L0001639 Rev. No. --

Rev. No. --

Rev. No. 0 --

Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/23/08 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTJONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current lAW SWP-TQS-Ol prior to use.

DETERMINE IF MODE CHANGE IS ALLOWED MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPMSETUP Simulator ICs; Malfunctions; Triggers; Overrides:

ADMIN JPM, NO SETUP NEEDED Special Setup Instructions:

Need a copy of PPM 3.1.2 Startup Flow Chart; Need a copy of current Technical Specifications Volume.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0116 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

TS and PPM 3.1.2 Location: ANY NUREG 1123 Ref: 2.4.40 2.3 /4.0 Performance Method: PERFORM L0001639 Rev. 0 Page 1 of6

DETERMINE IF MODE CHANGE IS ALLOWED JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is operating in MODE 4. A startup is underway following a short maintenance outage. The following conditions exist:

SRMs have normal indications and recorder speed is at 1,000 mm/hr

All IRM indications are normal on Range 1 except IRM-A which has an upscale trip and is bypassed and recorder speed is at 1,000 mm/hr

The Minimum and Maximum ECPs have been entered on the Control Rod Sequence Pull Sheet in the Control Room

A complete set of PPM 3.1.10 readings have been taken

OSP-INST-HI0ls have been completed and satisfied to enter MODE 2

The Barrier Impairment Log has no MODE change limiting conditions

The Surveillance in Progress Log shows no MODE change limiting conditions

The LCO/INOPIRFO Log shows no limiting conditions for a MODE change

HPCS-P-2 is out of service for motor oil replacement

All surveillances are completed and up to date

There are 3 inoperable control rods that are disarmed at position 00

A panel walk down has been completed

Offgas system warmup is in progress per SOP-OG-START

All ECCS systems are in a standby lineup

RRC-P-IA and RRC-P-IB arc operating at 15 hz.

Containment was de-inerted

A risk assessment has been completed for the following Out Of Service equipment:

o Remote Shutdown Panel Power Transfer Switch associated with MS RV-4A, MS-RV-4B, and MS-RV-4C o

Lower Drywell Spray Outboard Isolation Valve, RHR-V-16B INITIATING CUE:

A mode change to MODE 2 is planned. Determine if the change to MODE 2 is allowed.

Notify the Shift Manager (examiner) of your determination and justifications by filling out your justification on the attachment provided.

L0001639 Rev. a Page 2 of6

DETERMINE IF MODE CHANGE IS ALLOWED

Items are Critical Steps Standard Element Sat/Unsat Comments RECORD START TIME:

Notes HPCS-P-2 being OOS inops Review PPM 3.1.2, Startup the HPCS DG.

S /U

flow chart Reviews Tech Spec 3.8.1 and Review PPM 3.1.2, Startup detennines that LCO B is applicable flow chart which requires HPCS DG to be restored to operable status in 72 S /u

hours.

Notes that HPCS DG is required to be operable in MODE 2 and that TS 3.0Ab is not applicable to DGs.

Detennines that a Mode change is NOT allowed and fills out this reason on attachment provided.

Termination Criteria: Student hands filled out attachment to examiner.

RECORD TERMINATION TIME:

Transfer to "Results of JPM" page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked lJp procedure and remaining JPM pages may be discarded.

L0001639 Rev. 0 Page 3 of6

DETERMINE IF MODE CHANGE IS ALLOWED RESULTS OF JPM:

Examinee (Please Print):

Evaluator (Please Print):

Task Standard: Attachment is filled out indicating that a mode change is NOT allowed because HPCS-P-2 is out of service.

\\

Overall Evaluation I

Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev.

Validation/Critical JPM Completion II 10 Minutes / NA I

I COMMENTS:

Evaluator's Signature:

Date:

L0001639 Rev. 0 Page 4 0[6

STUDENT JPM INFORMATION CARD Initial Conditions: Columbia is operating in MODE 4. A startup is underway following a short maintenance outage. The following conditions exist:

SRMs have normal indications and recorder speed is at 1,000 mm/hr

All IRM indications are normal on Range 1 except IRM-A which has an upscale trip and is bypassed and recorder speed is at 1,000 mm/hr

The Minimum and Maximum ECPs have been entered on the Control Rod Sequence Pull Sheet in the Control Room

A complete set of PPM 3.1.10 readings have been taken

OSP-INST-Hl 01 s have been completed and satisfied to enter MODE 2

The Barrier Impairment Log has no MODE change limiting conditions

The Surveillance in Progress Log shows no MODE change limiting conditions

The LCOIINOP/RFO Log shows no limiting conditions for a MODE change

HPCS-P-2 is out of service for motor oil replacement

All surveillances are completed and up to date

There are 3 inoperable control rods that are at position 00

A panel walk down has been completed

Offgas system warmup is in progress per SOP-OG-START

All ECCS systems are in a standby lineup

RRC-P-IAandRRC-P-IBareoperatingat 15hz.

Containment was de-inerted

A risk assessment has been completed for the following Out Of Service equipment:

o Remote Shutdown Panel Power Transfer Switch associated with MS-RV-4A, MS-RV-4B, and MS-RV-4C o

Lower Drywell Spray Outboard Isolation Valve, RHR-V-16B Cue:

A mode change to MODE 2 is planned.

Determine if the change to MODE 2 is allowed.

Notify the Shift Manager (examiner) of your determination by filling in your justification on the attachment provided.

L0001639 Rev. a Page 5 of6

MODE CHANGE IS ALLOWED:

MODE CHANGE IS NOT ALLOWED:

L0001639 Rev. 0 Page 6 of6

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031 VERIFY the SNE is available to monitor the approach to criticality S31 PERFORM!

& verify criticality occurs between the Minimum Allowable ECP Limit and th~ Maximum AliowabJe ECP Limit.

r 04 1VERIFY at least 3 SRM's are operable.

I I

S6

[IDJ S7 I VERIFY O~

05 1COMPLETE the Reactivity Control Brief I

I Flow Mism,

IRAISE SRM & IRM recorder to 1,000 mm/hr, see basis 06 J

S8 RIFY for instructions.

I I

I 011 VERIFY the CRS/Shift Manager have been informed of

....,----II ffi[J the Estimated Critical Position (ECP).

S1 IOPEN the ~

021 Within 15 minutes PRIOR to control rod withdrawal for the purpose of achieving criticality, VERIFY RCS Pressure and S2 liE ventilatin!

I Temperature are within limits per OSP-RCS-C101.

r-I-----II VERIFYpri ventilated p

@]@]

[@]!

IN30]

DID I

PRIOR to 4l rPERFORM READINESS REVIEW per Note N30.

07 I

I I

RHRN*

I I

~

rPLACE the Mode Switch in the START/HOT STBY position.

08 I

I~

I' S10 VERIFY R~

a. Verify positi~

b. Verify ENA8 I

~

1 VERIFY OSP-RRC-D701 (Jet Pump Op & RRC Loop Flow Mismatch) Section 7.4 has been performed.

+

VERIFY the following are closed:

RHR-V-23 I I

RCIC-V-13 I I

I START a mechanical vacuum pump per SOP-AR-START.

@TI

@]

IVERIFY the vacuum breakers AR-V-3A,B,C are open. I I

QE]

.... ~

PRIOR to 48 psig, THEN VERIFY the following are closed:

RHR-V-8 I

I RHR-V-9 I

I I

ILINE UP the SS-EV-1A per PPM SOP-SS-START.

§RM the Offgas System per SOP-OG-START.

I I

.... ~

VERIFY RHR-V-9 is disabled by performing the following:

a. Verify RHR-DISC-V/9 is locked in the OFF position (RPS BRoom C213, RW 467).

b. Verify H13-P602.A5-1.8, RHR-V-9 POWER ENABLED annunciator alarm is clear.

I I

I B1 I PERFORM the Offgas System power supply and valve line up per

[@

SOP-OG-START.

i S1 I OPEN the MSIVs per PPM SOP-MSIV-OPS.

B2 I PERFORM the Air Removal and SJAE System line up per S2 liE ventilating Containment to support DW entry, It::l..EN SOP-AR-START.

I I

VERIFY prior to entering Mode 2 only the DW is being ventilated per SOP-CONT-VENT.

I B3 I,VERIFY MS-V-146 is open.

I I

IN30 I S31 PERFORM READINESS REVIEW per Note N30 I

I SECURE Shutdown Cooling per SOP-RHR-SDC.

.':1 I

~

V,ERIFY RHR is in a normal standby lineup per SOP-RHR-STBY.

I

~

VERIFY both RRC pumps are running at 15 Hz per SOP-RRC-START.

I I

~

L1 IVERIFY condensate temperature GT89°F PRIOR to sina as feedwater source for the RPV (COND-TI-804..

@]

L2 IVERIFY long cycle cleanup isolated per SOP-COND-OPS.

L5 IESTABLISH RPV water level at +36 inches.

I L6 Willill RPV water level is at +36 inches, Ib..e.n VERIFY:

a. RFW Level 8 trips reset.

I

b. HPCS Level 8 trip reset.

I

c. RCIC-RLY-K68 is de-energized (dropped out)

'I at H13-P621.

I L7 I VERIFY HPCS is in a standby line-up per I SOP-HPCS-STBY.

~

L3 'ESTABLISH a Feedwater flowpath and MAINTAIN RPV water level with RFW-L1C-620 in MANUAL per SOP-RFW-FCV-QC.

i

@I]I C12 1 ADJUST RWCU reject flow as necessary to maintain RPV level at setooint.

I I

I

AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTE S 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a.

Two qualified circuits between the offsite transmission network and the onsite Class IE AC Electric Power Distribution System; and

b.

Three diesel generators COGs).

APPLICABI LTTY:

MODES 1. 2. and 3.

-- - -- -- -- - -- -- --- --- --- ----- OTE - -- - -- -- -- - -- -- -- - --- -- ----

Division 3 AC electrical power sources are not required to be OPERABLE when High Pressure Core Spray System is inoperable.

ACTIONS

-- -- --- - --- - -- -- -- -- - -- --- -NOTE- -- --- - - -- -- --- - - -- - -- -- - -- - -- --- ---

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACT 0 COMPLETION TIME A.

One offsite circuit inoperable.

A.1 Perform SR 3.8.1.1 for OPERABLE offsite ci rcui t.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter (continued)

Columbia Generating Station 3.8.1-1 Amendment No. 149,169 187

3.8.1 AC Sources - Ope rat ing ACT IONS CONDiTION REQU IREO ACTI ON COMPLETION TIME A.

(continued)

A.2 Declare required feature(s) with no offs ite power available inoperable when the redundant required feature(s) are inoperable.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery of no offsite power to one division concurrent with inoperability of redundant required feature(s)

AND A.3 Restore offsite circuit to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND 6 days from discovery of failure to meet LCO when not associated with Required Action B.4.2.2 AND 17 days from discovery of failure to meet I LCO B.

One required DG inoperable.

B.1 Perform SR 3.8.1.1 for OPERABLE offsite circuit(s).

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND (continued)

Columbia Generating Station 3.8.1-2 Amendment No. 149.169 197

3.8.1 AC Sources - Operat i ng ACTIONS B.

CONDITION (continued)

B.2 8.3.1 8.3.2 8.4.1 REQUIRED ACTION Declare required fea ure( s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable.

Determine OPERABLE DG(s) are not inoperable due to common cause failure.

Perform SR 3.8.1.2 or OPERABLE DG(s).

Restore required DG to OPERABLE status.

COMPLETION TIME 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Conditi on B concurrent Ivi th inoperability of redundant required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours if not performed within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 72 hours from discovery of an inoperable DG 6 days from discovery of failure to meet LCO (continued)

Columbia Generating Station 3.8.1-3 Amendment No. 205 149,169,195,197

3.8.1 AC Sources - Operat ing ACTIONS CONDITION REQUI REO ACTION COMPLETI ON TIME B.

(continued)

B.4.2.1 Establish risk management actions for the alternate AC sources.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.4.2.2 Restore required DG to OPERABLE status.

14 days 17 days from discovery of failure to meet LCO C.

Two offsite circuits inoperable.

C.l Declare required feature(s) inoperable when the redundant required feature(s) are inoperable.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery of Cond ition C concurrent with i noperabi 1ity of redundant required feature(s)

C.2 Restore one offsite circuit to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

Columbia Generating Station 3.8.1-4 Amendment No. 149,169 197

3.8.1 AC Sources-Operating ACTIONS D.

CO DITION One offsi te circuit inoperable.

AND One required DG inoperable.

REQUIRED ACTION

NOTE------------

Enter applicable Conditions and Required Actions of LCO 3.8.7, "Distribution Systems - Operati ng," when Condition 0 is entered with no AC power source to any division.

0.1 Restore offsite circuit to OPERABLE status.

I COMPLETION 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TIME 0.2 Restore required DG to OPERABLE status.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E.

Two required DGs inoperable.

E.1 Restore one required DG to OPERABLE status.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 24 hours if Division 3 OG is inoperable F.

Required Action and Associated Completion Time of Condition A, B, C. D, or E not met.

F.1 AND F.2 Be Be in MODE in MODE

3.

4.

12 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months hours G.

Th AC ee or more required sources inoperable.

G.1 Enter LCO 3.0.3.

Immediately Columbia Generating Station 3.8.1-5 Amendment No. 149,169 197

PROGRAM TITLE COURSE TITLE LESSON TITLE LESSON LENGTH

.5 HRS Lesson Plan PQD Code Simulator Guide PQD Code JPM PQD Code Exam PQD Code DIVISION TITLE DEPARTMENT PREPARED BY REVISED BY TECHNICAL REVIEW BY INSTRUCTIONAL REVIEW BY APPROVED BY C ~ENERGY

'AJ NORTHWEST

~

INSTRUCTIONAL COVER SHEET LICENSED OPERATOR INITIAL TRAINING JOB PERFORMANCE MEASURE - ADMIN DETERMINATION IF MOVEMENT OF HEAVY LOAD OVER SPENT FUEL POOL CAN OCCUR MAXIMUM STUDENTS 1

INSTRUCTIONAL MATERIALS INCLUDED LOOO1630 Nuclear Training Operations Training Ron Hayden Rev. No.

Rev. No.

Rev. No. 0 Rev. No.

DATE 5/27/08 DATE DATE DATE DATE Operations Training Manager Verify materials current lAW SWP-TQS-Ol prior to use.

DETERMINE IF LOAD CAN BE MOVED OVER SPENT FUEL POOL MINOR REVISION RECORD MInor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Have a copy of the following for each student:

PPM 1.3.40 pages 1-7 and attachment 7.5 LCS 1.9.2 including graph JPM Instructions:

Verify the current revisions of each drawing against the JPM. If the drawings are a different revision than listed in the lPM, ensure the lPM is still technically correct. If the JPM is not technically correct, the lPM should be revised.

The evaluator document results on the "Results of lPM" page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0059; SRO-0096 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 1.3.40 Rev. 18 Location: CLASSROOM OR SIMULATOR LCS 1.9.2 Rev. 44 NUREG 1123 Ref: 2.2.26 2.5/3.7 Performance Method: PERFORM LOOOl630 Rev. 0 Page 1 of 6

DETERMINE IF LOAD CAN BE MOVED OVER SPENT FUEL POOL JPM CHECKLIST PROCEDURE VALIDATION:

Procedure copies for evaluator and student, if procedure revision is different from that listed on lPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL CONDITIONS:

Columbia is shutdown for a refueling outage with the following plant parameters given:

Fuel shuille has been completed with core verification taking place The Spent Fuel Pool has been verified to be subcritical for GT 24 Hrs The following equipment is OOS:

RHR-P-2C HPCS System including the HPCS-DG RRA-RIS-3 Reactor Building In-Plant Air Particulate Monitor REA-RIS-609AIB & CID Reactor Building Exhaust Plenum RMS PRM-RE-IA, IB & lC Reactor Building Low, Intennediate, and High Range Stack Monitor TRA-RIS-l Turbine Building In-Plant Air Particulate Monitor INITIATING The Refueling Floor Supervisor has just requested pennission for a load of 1190 lbs to CUE:

be carried 5 foot over the Spent Fuel Pool.

On the next page, indicate your intention of allowing the move over the Spent Fuel Pool by initialing where indicated OR indicate your intention of disallowing the move over the Spent Fuel Pool and your associated reason.

When done, hand the completed sheet to the examiner.

LOOO 1630 Rev. 0 Page 2 of6

DETERMINE IF LOAD CAN BE MOVED OVER SPENT FUEL POOL

Items are Critical Steps Comments Element Standard SatiUnsat RECORD START TIME:

Refers to PPM 1.3.40 Attachment 7.5 and determines:

1 is answered yes - the requirement is satisfied (SPF is subcritical for GT 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months - given in S/U initial conditions)

2 is answered yes - the load meets height and weight restrictions ofLCS 1.9.2 S/U 1190 lbs at a height of 5 f1. puts you in the

'permitted' area of graph

3 is answered NO as there are no operational instruments to monitor an offsite release S I U

Termination Criteria: Student hands the examiner the completed attached sheet.

RECORD TERMINATION TIME:

Transfer to "Results of JPM" page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

LOOO 1630 Rev. 0 Page 3 of6

DETERMINE IF LOAD CAN BE MOVED OVER SPENT FUEL POOL RESULTS OF JPM:

Examinee (Please Print):

Evaluator (Please Print):

Task Standard: Candidate indicates that the move of 1190 lbs 5 ft. over the spent fuel pool is NOT allowed due to answering question #3 of PPM 1.3.40 attachment 7.5 as the requirement is NOT satisfied.

Overall Evaluation

[

Exam Code I

SAT / UNSAT (Circle One)

I I

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 15 Minutes I N I A COMMENTS:

Evaluator's Signature:

Date:

LOOO J630 Rev. 0 Page 4 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is shutdown for a refueling outage with the following plant parameters given:

Fuel shume has been completed with core verification taking place The Spent Fuel Pool has been verified to be subcritical for GT 24 Hrs The following equipment is OOS:

RHR-P-2C HPCS System including the HPCS-DG RRA-RIS-3 Reactor Building In-Plant Air Particulate Monitor REA-RIS-609NB & C/D Reactor Building Exhaust Plenum RMS PRM-RE-I A, IB & IC Reactor Building Low, Intennediate, and High Range Stack Monitor TRA-RIS-l Turbine Building In-Plant Air Particulate Monitor Cue:

The Refueling Floor Supervisor has just requested permission for a load of 1190 lbs to be carried 5 foot over the Spent Fuel Pool.

On the next page, indicate your intention of allowing the move over the Spent Fuel Pool by initialing where indicated OR indicate your intention of disallowing the move over the Spent Fuel Pool and your associated reason.

When done, hand the completed sheet to the examiner.

LOOOl630 Rev. 0 Page 5 of 6

YES - I would give pennission for the 1190 Ib load to be moved 5 foot over the Spent Fuel Pool as requested by the Refueling Floor Supervisor.

Initials NO - I would NOT give pennission for the 1190 Ib load to be moved 5 foot over the Spent Fuel Pool as requested by the Refueling Floor Supervisor for the following reason:

L0001630 Rev. 0 Page 6 of 6

1111111111111111111111111111111111111111

1.3.40*

DIC 1750 ENERGY REFERENCE NORTHWEST USE People* Vision* Solutions COLUMBIA GENERATING STATION l;SE l'l'RRENT REVISION PLANT PROCEDURES MANUAL NUMBER DATE Approver:

DP Brown for SL Belcher 1.3.40 Sponsor:

MG Pratt QPR: MG Pratt 03/14/07 VOLUME NAME ADMINISTRATIVE PROCEDURES SECTION CONDUCT OF OPERATIONS TITLE OUTAGE MODE CHANGE, REFUELING ACTIVITY READINESS, AND ISFSI ACTIVITY READINESS EVALUATION PROCEDURE NUMBER REVISION PAGE 1.3.40 18 1 of 35

TABLE OF CONTENTS 1.0 PURPOSE..................................................... 3

2.0 REFERENCES

................................................. 3 3.0 PREREQUISITES............................................... 4 4.0 PRECAUTIONS AND LIMITATIONS.................................. 4 5.0 PROCEDURE 5

5. I Mode Changes.............................................. 5 5.2 Refueling Activities 7

5.3 ISFSI Activies

................................... 7 6.0 DOCUMENTATION............................................. 8 7.0 ATTACHMENTS

, 8 7.1 Mode Change Notification Form

..................... 9 7.2 Technical Specification Section Summary 10 7.3 Mode Change and Outage Related Requirements 12 7.4 Single Control Rod Scramming and Control Rod Stroke Timing (Modes 4, 5) 32 7.5 Moving Loads Over/In the Spent Fuel Pool Requirements 34 7.6 ISFSI Fuel Handling Requirements 35 PROCEDURE NUMBER 1.3.40 REVISION 18 PAGE 2 of 35

1.0 PURPOSE This procedure provides:

Instructions for Mode change from Mode 4 to Mode 5, or Mode 5 to Mode 4, to ensure that all concerned departments are prepared for the Mode change and thus avoid conflicts with Technical Specifications.

{C-3246}

Technical Specification requirements for refueling activities that may include core alterations, irradiated fuel handling in secondary containment and control rod removal.

These activities do not always require a Mode change.

Technical Specification requirements for ISFSI activities for irradiated fuel handling in secondary containment. These activities do not require a Mode change.

This procedure is not meant to replace plant Technical Specifications or ISFSI Technical Specifications.

2.0 REFERENCES

2.1 LER 86-005, Missed Surveillance for Mode Change

{C-3246}

2.2 GI2-04-100, Prohibit Entry Into Mode 4 From Mode 5 Using Provisions of LCO 3.0.4

{C-12234}

2.3 FSAR 9.1.2.1.1.2.d

{R-5883}

2.4 SWP-RXE-Ol, Reactivity Management Program (OER 8600902A)

{P-104550}

2.5 PER 296-0519-06, Adverse Trends of PERs

{P-133491}

2.6 Plant Technical Specifications 2.7 ISFSI Technical Specifications PROCEDURE NUMBER REVISION PAGE 1.3.40 18 3 of 35

3.0 PREREQUISITES 3.1 For Mode changes, the plant is should be in a stable Mode such that all departments have time to comply with Technical Specifications prior to a planned Mode or condition change.

3.2 For Mode changes, a cognizant person from each department is on site with signature authority to approve a Mode change for their department. This is normally the department manager or his designee.

4.0 PRECAUTIONS AND LIMITATIONS 4.1 Failure to comply with this procedure could lead to a violation of Technical Specifications.

4.2 A Mode change is not to be made until all concerned departments have formally indicated their readiness.

4.3 This procedure is primarily focused toward the Technical Specification requirements to enact a condition change. Additional requirements are specified in each applicable PPM. The attachments are requirements to satisfy Technical Specifications. There are no # signs identifying each individual criterion.

PROCEDURE NUMBER REVISION PAGE 1.3.40 18 4 of 35

5.0 PROCEDURE

5. I Mode Changes NOTE: Technical Specification 3.0.4 does apply for Mode change from 4 to 5 and 5 to 4. The Mode change may be made without the applicable system(s) operable, provided a risk assessment has been performed per PPM 1.5.14, with the exception of RHR SDC, which must be operable when transitioning from Mode 5 to 4.

{C-12234}

5.1.1 The PRE-PLANNED Mode change notification is initiated by the Operations department, per plant operating requirements.

NOTE: The Shift Manager determines which Mode/Condition changes require Department Manager review.

5.1.2 Appropriate departments should be informed of intended Mode/Condition change.

NOTE: The computerized surveillance printouts are a good source (but not the only source) to verify compliance with Technical Specifications when changing modes. As a minimum, the TS Section listed on Attachment 7.2 should be reviewed.

5.1.3 Each Department Manager is to verify compliance to Technical Specifications prior to the Mode/Condition change by reporting to the Outage Manager or Operations Manager for forced outages and signing the space on Attachment 7.1.

5.1.4 The CRS/SM should perform search of LCOIINOP/RFO log on "Mode CHANGE ALLOWED = NO".

{P-133491}

NOTE: Attachment 7.3 should be used as a guideline. It is not required to be retained. A Crystal Report, located at "adhoc\\operations\\ 1-3-40 Surv Complt & Late Date for Outage-Rltd Rqmts Attach", has been made that lists all the surveillances in PPM 1.3.40, Attachment 7.3, including their Last Date completed and Late Dates.

5.1.5 The CRS/SM should review Attachment 7.3 for the desired Mode change.

PROCEDURE NUMBER REVISION PAGE 1.3.40 18 5 of 35

5. I.6 The Outage Manager ensures that all departments are ready for Mode change. When all departments are ready for Mode change the Outage Manager reports to the Shift Manager the station's readiness for Mode change. The Shift Manager should ascertain that all concerned departments have agreed to the planned Mode/Configuration.

5.1.7 The Shift Manager should sign the notification form indicating its completeness.

5.1.8 The Shift Manager can then change Plant operating Mode/Configuration as required by Plant conditions.

PROCEDURE NUMBER REVISION PAGE 1.3.40 18 6 of 35

5.2 Refueling Activities NOTE: Attachment 7.3 should be used as a guideline and is not required to be retained. A Crystal Report, located at "adhoc\\operations\\ 1-3-40 Surv Complt & Late Date for Outage-Rltd Rqmts Attach", has been made that lists all the surveillances in PPM 1.3.40, Attachment 7.3, including their Last Date completed and Late Dates.

5.2.1 Complete Attachment 7.3. N/A those blocks that are not applicable.

5.2.2 Ensure the specific requirements for the refueling activity to be performed are met prior to commencement of that activity.

5.2.3 Perform a search of the LCO/INOP/RFO log for "Mode = Other".

Verify the search results allow refueling activities.

5.2.4.3 should be completed for initial irradiated fuel handling during refuel outage, and anytime refuel operations have stopped for an extended period of time (typically GE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

5.2.5 When performing control rod withdrawal for Control Rod Scram Timing or Control Rod Stroke Timing, refer to Attachment 7.4 for specific requirements.

5.2.6 When moving any loads over or in the Spent Fuel Pool, refer to.5 for specific requirements.

{P-158625}

5.3 ISFSI Activities NOTE: Attachment 7.6 should be used as a guideline and is not required to be retained. A Crystal Report, located at "adhoc\\operations\\ 1-3-40 Surv Complt & Late Date For ISFSI Rqmts Attach Attachment 7.6", has been made that lists the surveillances in PPM 1.3.40, Attachment 7.6, including their Last Date completed and Late Dates.

5.3.1 Complete Attachment 7.6. N/A those blocks that are not applicable.

5.3.2 Ensure the specific requirements for the irradiated fuel handling activity are met prior to commencement of that activity.

5.3.3 Perform a search of the LCO/INOP/RFO Jog for "Mode = Other".

Verify the search results allow ISFSI activities.

5.3.4.6 should be completed prior to commencing to load each ISFSI MPC.

PROCEDURE NUMBER REVISION PAGE 1.3.40 18 7 of 35

MOVING LOADS OVER/IN THE SPENT FUEL POOL REQUIREMENTS Specific Requirement Applicability Requirement Satisfied Yes/No Date Satisfy the following conditions:

1.

Irradiated fuel in the Spent Fuel Pool has been subcritical for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (cooling, decay time).

During movement of loads over fuel assemblies stored in the Spent Fuel Pool.

And

2.

Loads meet height and weight restrictions of LCS 1.9.2.

And

3.

Sufficient Reactor Building ventilation and instrumentation (or alternate sampling methods) are functional to monitor an offsite release..5 PROCEDURE NUMBER REVISION PAGE 1.3.40 18 34 of 35

Crane Travel 1.9.2 1.9 REFUELING OPERATIONS 1.9.2 Crane Travel RFO 1.9.2

a.

Crane travel with loads, other than the cavity in-vessel service platform (CISP), over the spent fuel storage pool racks shall be within the limits of Figure 1.9.2-1.

b.

Crane travel with the CISP over the spent fuel storage pool racks shall be within the limits of SR 1.9.2.2 and SR 1.9.2.3.

APPLICA BILI TY :

With irradiated fuel stored in the spent fuel storage pool (SFP) racks.

COMPENSATORY MEASURES

- -- - - -- -- -- -- - - - - - - - - - - -- - - - - - - - - - - - - NOTE- - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - -- - -

RFO 1.0.3 is not applicable.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A.

Requirements of RFO not met.

A.1 Initiate actions to move the crane load from over the spent fuel storage pool racks.

Immediately Columbia Generating Station 1.9.2-1 Revision 44

1.9.2 Crane Travel SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 1.9.2.1

- - - - -. - - - - - - - - - - - -NOTE*, - - - - - - - - - - - -. -

Only required when crane is in use.

Perform system functional test.

7 days SR 1.9.2.2 Verify the CISP extension over fuel pool is less than 7 feet.

the spent At all times during CISP 1i ft SR 1.9.2.3 Verify the CISP height is less above the refuel floor.

than 6 feet At all time s during CISP 1i ft Columbia Generating Station 1.9.2-2 Revision 44

1.9.2 Crane Travel 17 16 15 14

[ 13

-' 12 w

>w 11 (t:

W 10

~

9 D.

u..

<Il 8

(t:

w 7

~

w 8

&l 5

~

4 J:

\\:l W

3 I

2 0

-1 830 I

i

/Ill" I

~

-r I

I IIIIII 1'1 III

~

i i

LOADS IN THIS AREA ARE PERMITTED TO TRAVEL OVER THE SPENT FUEL POOL 1500

~.

-1 i-I 890 950 1010 1070 1130 1190 1250 1310 1370 1430 1490 1550 HEIGHT ABOVE SFP WATER LEVEL VS. MAXIMUM LOAD TO BE CARRIED OVER SFP 960690.11 Figure 1.9.2-1 Crane Travel Columbia Generating Station 1.9.2-3 Revision 441

.s

=y

~

l IENERGY A;) NORTHWEST

~

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAfNfNG COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE PERFORM QEDPS (ADMIN) (TC)

LESSON LENGTH

.5 HRS Lesson Plan PQD Code Simulator Guide PQD Code JPM PQD Code Exam PQD Code MAXIMUM STUDENTS I

INSTRUCTIONAL MATERIALS INCLUDED LOOO1631 Rev. No.

Rev. No.

0 DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE OS/28108 REVISED BY DATE TECHNICAL REVIEW BY INSTRUCTIONAL REVIEW BY APPROVED BY Operations Training Manager DATE DATE DATE Verify materials current lAW SWP-TQS-OI prior to use

MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any Ie. If in classroom need access to ARP for moisture alarm.

Special Setup Instructions:

Log onto a Computer that has the QEDPS program on it. The computer should be connected to a printer. Ensure paper is loaded in the printer.

Student should have access to Operator Aid for Stability Class determination.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.

Tools/Equipment: Computer / Printer*

Safety Items: None Task Number: SRO-0029 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: Yes - 15 Minutes PPM

Reference:

PPM 13.8.1 Rev. 28 Location: Simulator / Classroom NUREG 1123 Ref: 2.3.10(2.9/ 3.3)

Performance Method: Perform LOOOl631 Rev. 0 Page I of 5

JPM CHECKLIST PROCEDURE VALIDATION:

Procedure copies for evaluator and student, ifprocedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The plant has experienced an event that has resulted in the following conditions:

CONDITIONS:

Columbia scrammed one hour and 45 minutes ago. An unisolable leak in the RWCU system has existed for the past two hours and 25 minutes. B SGT train is tagged out for maintenance. There is a 'HEPAA-l OUTLET MOIST HIGH' annunciator alarmed on H13-P827. Reactor Building radiation levels on RE-RMS-IA indicate 1.0 E+06 cps and RE-RMS-IB indicates 1.9 E+04 cps. Standby Gas Treatment flow is 4850 cfm. Wind direction is from 130°, wind speed is 7 mph, and delta Tis

+2.5°F.

INITIATING CUE:

You have been directed to perform a QEDPS using the computer based QEDPS program. Print out the QEDPS and associated map and hand them to your examiner.

When done - quit the QEDPS program and log off of the computer.

This is a time critical JPM and your time starts now.

Items are Critical Steps Comments ELEMENT Standard SatiUnsat RECORD START TIME:

Low range off Indicates Monitor used Checks RB Stack Intermediate S / U

scale high Range Enters Monitor reading Enters RE-RMS-l B indication S / U

of 1.ge+04 (or 19000)

SM-8 locked out STANDBY GAS TREATMENT Checks One Train S / U

Moisture alarm SGT FILTER STATUS Checks Damaged S / U

SGT FLOW RATE Enters 4850 S / U

Release duration is PROJECTED RELEASE Enters 5 hrs 0 minutes S / U

2 hr 2S min.

DURATION rounded up to three hrs and 2 hrs added TIME SINCE REACTOR Enters 1 hr and 45 minutes S / U

for a total of S hrs SHUTDOWN METEOROLOGICAL DATA:

Enters:

Wind Direction 130 S / U

Stability class is read otT of operator Wind Speed 7

S / U

aid using the

+2.S0F Stability Class F

S / U

LOOOl631 Rev. 0 Page 2 of 5

Items are Critical Steps Comments ELEMENT Standard SatJUnsat RUNS QEDPS Depresses RUN icon S I U

Prints QEDPS Depresses PRINT icon on QEDPS screen SI U

Prints associated Map Depresses MAP icon then the PRINT icon SI U

Termination Criteria: Student hands the printed out QEDPS and associated MAP to the examiner.

IF NOT DONE - INFORM THE STUDENT TO QUIT THE QEDPS PROGRAM AND LOG OFF OF THE COMPUTER.

RECORD TERMINATION TIME:

Transfer the following information to the "Results of JPM" page: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

L0001631 Rev. a Page 3 of 5

RESULTS OF JPM:

PERFORM QEDPS AND DETERMINE EAL Examinee (Please Print):

Evaluator (Please Print):

Task Standard: Accurately enters given plant parameters in the QEDPS program to calculate thyroid CDE Rate of 50.8 at 1.2 miles and associated map shows release into Section 4.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time 10 Minutes I NIA COMMENTS:

Evaluator's Signature:

Date:

LOOOl631 Rev. 0 Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant has experienced an event that has resulted in the following conditions:

Columbia was scrammed one hour and forty five minutes ago

An unisolable leak in the RWCU system has existed for the past two hours and twenty five minutes

B SGT train is tagged out for maintenance

There is a 'HEPA A-I OUTLET MOIST HIGH' annunciator alanned on H 13-P827

Reactor Building radiation levels on RE-RMS-l A indicate 1.0 E+06 cps

Reactor Building radiation levels on RE-RMS-l B indicate 1.9 E+04 cps

SGT flow is 4850 cfm

Wind direction is from 130°

Wind speed is 7 mph

Delta T is +2.5°P Cue:

You have been directed to perform a QEDPS using the computer based QEDPS program.

Print out the QEDPS and associated map and hand them to your examiner.

When done - quit the QEDPS program and log off of the computer.

THIS IS A TIME CRITICAL JPM AND YOUR TIME START NOW L0001631 Rev. a Page 5 of 5

Columbia Generating Station (QEDPS v. 3.0)

Run: 06/24/2008 07:26:10 Centerline doses and dose rates at selected distances Distance (miles) 0.6 1.2 2.0 5.0 7.0 10.0 TEDE (mrem) 25.2 16.6 13.2 7.5 5.6 4.0 External Dose 1.5 1.1 0.9 0.5 0.4 0.3 Thyroid CDE 387.9 253.9 201.5 113.5 85.4 61.2 TEDE Cloud Shine + 4-Day Ground Shine + CEDE Inhalation External Dose Cloud Shine + Initial Ground Shine NOTE:

* * * *

indicates a value greater than 100,000 mrem TEDE Rate (mrem/h) 5.0 3.3 2.6 1.5 1.1 0.8 External Dose Rate 0.3 0.2 0.2 0.1 0.1 0.1 Thyroid CDE Rate 77.5 50.8 40.3 22.7 17.1 12.3 Worker Adj. Factor 19.4 17.3 16.5 15.2 14.9 14.8 Transport Time (h) 5.1 5.2 5.3 5.7 6.0 6.4 NOTE:

Dose and dose rate values below 0.05 have been set to zero.

You have selected:

Int. Range Stack Monitor Reading 1.90E+04 cps Release is Unfiltered Flow =

4850. cfm Wind Dir. From (deg.) =

130.

Wind Spd (mph) 7.0 Stab. Class = F Release duration:

5 hr o min Holdup duration:

1 hr 45 min Source term:

A total of 1.8E+03 Ci were released.

Release Release Release Nuclide (Ci/s)

Fract.

Nuclide (Ci/s)

Fract.

Nuclide (Ci/s)

Fract.

Kr-85 1.3E-04 3.4E-06 Kr-85m 4.0E-03 3.4E-06 Kr-87 4.1E-03 3.4E-06 Kr-88 9.9E-03 3.4E-06 Sr-89 2.3E-04 3.9E-08 Sr-90 9.0E-06 3.9E-08 Sr-91 2.4E-04 3.9E-08 Y-91 2.0E-05 2.6E-09 Mo-99 1.0E-04 1.0E-08 Tc-99m 1.0E-04 6.3E-08 Ru-103 7.4E-05 1.0E-08 Ru-l06 1.6E-05 1.0E-08 Sb-127 7.4E-05 1.9E-07 Sb-129 3.1E-04 1.9E-07 Te-129m 6.7E-05 1.9E-07 Te-131m 1.4E-04 1.9E-07 Te-132 1.5E-03 1.9E-07 1-131 2.4E-03 4.5E-07 1-132 3.5E-03 4.5E-07 1-133 4.7E-03 4.5E-07 1-134 1.4E-03 4.5E-07 1-135 3.6E-03 4.5E-07 Xe-131m 2.2E-04 3.4E-06 Xe-133 3.8E-02 3.4E-06 Xe-133m 1.3E-03 3.4E-06 Xe-135 1.0E-02 3.4E-06 Xe-138 2.2E-04 3.4E-06 Cs-134 1.6E-04 3.2E-07 Cs-136 6.2E-05 3.2E-07 Cs-137 1.0E-04 3.2E-07 Ba-140 5.3E-04 5.2E-08 La-140 2.6E-05 2.6E-09 Ce-144 7.0E-05 1.3E-08 Np-239 1.3E-03 1.3E-08 Rb-87 1.9E-18 3.2E-07 Rb-88 9.9E-03 3.1E-06 Y-90 1.lE-08 2.6E-09 Y-91m 7.5E-06 2.6E-09 Tc-99 1.3E-14 1.0E-08 Rh-103 5.4E-05 1.0E-08 Rh-l06 1.6E-05 1.0E-08 Te-127m 5.8£-09 1.9E-07 Te-127 7.5E-06 1.9E-07 Te-129 6.7E-05 6.0E-08 1-129 3.3E-15 4.5E-07 Te-131 3.1E-05 1.9E-07 Xe-135m 3.6E-03 2.7E-06 Cs-135 4.9E-14 3.2E-07 Cs-138 2.7E-04 3.2E-07 Ba-137m 1.0E-04 3.4E-07 Pr-144m 2.0E-07 2.6E-09 Pr-144 7.0E-05 1.3E-OB Fract. is the fraction of the core inventory released.

NOT FOR DISTRIBUTION --

FOR INTERNAL USE ONLY!!

Computed By:

Reviewed By:

10-MILE EMERGENCY PLANNING ZONE (EPZ)

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'.0 280' 270' ~~-+--I--+-__f--+-+-*~~~.~~~-+--~I\\JI 240' LEGEND

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'r' COLUMBIA GENERATING STATION PLUME EXPOSURE PATHWAY EMERGENCY PLANNING ZONE 950141 Jan 2005 Columbia Generating Station (QEDPS v. 3.0)

Run: 06/24/2008 07:26:10 Plume centerline dose values (mrem) are listed below.

Distance (miles) 0.6 1.2 2.0 5.0 7.0 10.0 TEDE (mrem) 25.2 16.6 13.2 7.5 5.6 4.0 Thyroid CDE 387.9 253.9 201.5 113.5 85.4 61.2 Plume boundary on map is 10% of centerline value.

NOTE:

- - - - indicates a value greater than 100,000 mrem Worker Adj. Factor 19.4 17.3 16.5 15.2 14.9 14.8 APPROVED FOR RELEASE BY:

(Emergency Director)

EN,ERGY NORTHWEST INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RECLASSIFY A SECURITY EVENT (SAE) (TC) (ADMIN)

LESSON LENGTH

.5 HRS MAXIMUM STUDENTS INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code L0001569 Rev. No.1 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 06/20106 R VISED BY Ron Hayden DATE OS/28108 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current lAW SWP-TQS-Ol prior to use

MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval JPMSETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Have a blank CNF form, a copy ofPPM 13.1.1 EAL Chart, and PPM 13.1.1A available.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in IPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.

Tools/Equipment: None Safety Items: None Task Number: SRO-0529 Validation Time: 15 minutes Prerequisite Training: None Time Critical: 30 minutes PPM

Reference:

13.1.1 Rev. 36; PPM 13.1.1ARev.19 Location: Any NUREG 1123 Ref: 2.4.28 2.3/3.3 Performance Method: Perform L0001569 Rev. 1 Page 1 of 6

JPM CHECKLIST PROCEDURE VALIDATION INITIAL CONDITIONS:

INITIATING CllE:

Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the clitical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

The plant is operating at 100% power. One hour ago, the FBI notified security and plant management that a mid-western terrorist group has threatened to interfere with the operation of Columbia Generating Station. The FBI considers this a credible threat. An Unusual Event was declared 50 minutes ago.

Five minutes ago, security called and notified you that an explosive device has been discovered in the'A' Service Water Pump House. The device is of sufficient size that ifit should detonate, SW-P-lA would be destroyed. All personnel have been evacuated from the area.

Meteorological data:

Stability class E Wind direction is from 245 0

Wind speed 4 mph No precipitation You are the Emergency Director. Determine if an EAL change is required. The electronic CNF form is not available. Complete a paper CNF form if necessary and present the completed form to the examiner. If a CNF is not required, initial the line where indicated on the attached sheet and present that sheet to the examiner.

THIS IS A TIME CRITICAL JPM AND YOUR TIME STARTS NOW Candidate is allowed 15 minutes to determine if a change in classification is needed and 15 minutes to complete the CNF form for a total of 30 minutes.

L0001569 Rev. 1 Page 2 of 6

Items are Critical Steps Comments Element Standard SatfUnsat RECORD START TIME:

Complete the CNF CNF Form is completed as follows:

Form Block 1 - checks Emergency or Drill S IU Block 2 - Fills in '2' S I U Block 3 - Fills in his/her name and a S IU phone number Checks block 4.b (Reclassification) and S I U

fills in current Date and Time Checks block 5.c (Site Area Emergency)

S IU

Block 6 left blank S IU Block 7: Enters...

Wind Speed = 4 S/U Wind Direction: from = 245 0

S IU Precipitation = 'No' block checked S IU Stability Class = E S IU Block 8 checks 'No Release' S IU Block 9 checks 'NIA' S IU Block 10 checks 'N/A' S/U Block 11 checks 'No' S IU Block 12:

EAL # 9.1.S.1 or 9.1.S.2 S I U

Description - Similar to 'Bomb in SW pump house' S IU

Block 13: Checks a, b or c S/U Termination Criteria: Student presents the completed CNF to the examiner.

RECORD TERMINATION TIME:

L0001569 Rev. 1 Page 3 of 6

RESULTS OF JPM:

RECLASSIFY A SECURITY EVENT Examinee (Please Print):

Evaluator (Please Print):

Task Standard: Reclassifies the security event as a Site Area Emergency (9.I.S.1 or 9.I.S.2) and completes the CNF with required information.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for JPM (Initial Box)

Validation/Critical Time JPM Completion Time I

I 15 Minutes / 30 minutes I I

COMMENTS:

Evaluator's Signature:

Date:

L0001569 Rev. 1 Page 4 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant is operating at 100% power. One hour ago, the FBI notified security and plant management that a mid-eastern terrorist group has threatened to interfere with the operation of Columbia Generating Station. The FBI considers this as a credible threat. An Unusual Event was declared 50 minutes ago.

Cue:

Five minutes ago, security called and notified you that an explosive device has been discovered in the 'A' Service Water Punlp House. The device is of sufficient size that, if it should detonate, SW-P-IA would be destroyed. All personnel have been evacuated from the area.

Meteorological data:

Stability class is E

Wind direction is from 245 0

Wind speed is 4 mph

No precipitation You are the Emergency Director. Determine if an EAL change is required.

The electronic CNF form is not available. Complete a paper CNF form if necessary and present the completed fOffil to the examIner.

If a CNF is not required, initial the line where indicated on the attached sheet and present that sheet to the examiner.

THIS IS A TIME CRITICAL JPM AND YOUR TIME STARTS NOW L0001569 Rev. 1 Page 5 of 6

Based on the event presented, I have determined that an upgrade fronl the Unusual Event is required and I have completed a CNF Form.

Initials Based on the event presented, I have determined that an upgrade from the Unusual Event is not required.

Initials L0001569 Rev. 1 Page 6 of 6

Phone No.:

31~"

IOrrJ 0

COLUMBIA GENERATING STATION

@ENERGY

"':,.. NORTHWEST CLASSIFICATION NOTIFICATION FORM (CNF)

People' Vision* Solutions

( 1. TYPE OF EVENT:

a. [?'"Emergency O(

b. GYOrili

(,2)NO":

~

Classification/Status Time Date NOTIFICATION PROVIDED BY EMERGENCY DIRECTOR: (4

( 3

,._~/ a.D Initial Classification Name (Print) W\\ttJ~

b.~

Reclassification

"/,-1

}.I"J

c. D Termination c/

(509)¥t:r't'I<t£ d.D PAR Changes/Additions e.D Information

( 5 '. a. D UNUSUAL EVENT

\\.\\

360" 45"

__ I No offsite protective actions recommended (5"; b. D ALERT

~ _' No offsite protective actions recommended

~tEO

~

3' UNTING

( 5';: C:~~:E AREA. EME~GENCY Automatic Protective Action RecommendatIOns

~'-___J

'0' I ~

EVACUATE:

~'

Columbia River

Ringold Fishing Area

Horn Rapids Recreation

Wahluke Hunting Area RINGOLD

~

270 Area/ORV Park

Schools in EPZ

1----

---~-- -

I ASHING 90' ENERGY NORTHWEST ACnoNS ill c

Site Evacuation

~ e I

~

FFTF II v~ A

( 5~ ': d. D GENERAL EMERGENCY I.-/

Jt~

Ol

'-.j Automatic Protective Action Recommendations EVACUATE:

i-'"

SC:k>\\A

Columbia River

Ringold Fishing Area

-'~~_

"'.11'1 sc L

~

.......~, Ao

Horn Rapids Recreation

Wahluke Hunting Area om PARK ~Amf Area/ORV Park

Schools in EPZ 225" oFIN RAp"l..

135' ENERGY NORTHWEST ACnoNS

~;~,"t)2.

180' SCHOOL

Site Evacuation

'7 Meteorological Data:

Select the following additional PARs Wind Speed (mph) t/

( 6 ) NOTE: The minimum PAR for General Emergency is Wind Direction: from ~//C Evacuate All Sections 0-2 Miles and 10 Miles Downwind Precipitation: DYes.KI No and shelter remaining sections.

Stability Classification t:

1.

All Sections (0-2 Miles)

D Evacuate

2.

Evacuate (2-10 Miles) offsite Release Information:

D Section 1 D Section 2 D Section 3 D Section 4 18 : MNo Release D Release Start Time (A,B,C) 19 D Airborne D Water

~/A

3.

Shelter Remaining Sections (2-10 Miles)

( 10:' D Release Terminated Stop Time

~N/A o Section 1 D Section 2 o Section 3 D Section 4 (A,B,C)

State criteria met for administering KI (Infonnalion only) i 11\\;&

4.

Basis for PARs D Radiological D Plant No

5.

Specific PARs DYes D 250 mrem/hr thyroid o 1.4 x 10.7 Ilci/cc 1-131 EAL# q./..S.JVl-9./-5. L..

i12 DESCRIP~ON OF INCIDENT OR ADDITIONAL INFORMATION: (Please provide enough detail for understanding)

-8;"';'"

1.-1. n~

4)w LJdnlf-<J hotJ<; e I

(13 : Prognosis of Situation:

a. ~knownCJL-b. ~bleVLc. ~calating b'\\...,.d. ~roving (14) EMERGENCY DIRECTOR Approval Signature for release of the CNF:

Signature:

24075 R20

Number:

13.1.1 luse Category: REFERENCE Revision: 36

Title:

CLASSIFYING THE EMERGENCY Page: 28 of 38 CATEGORY UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 9

Hazards 9.1 Security Threats Confirmed security event which indicates a potential degradation in the level of safety of the plant 9.1.U.1 Security event in a Plant Protected Area 9.1.A.1 Security event in a Plant Vital Area 9.1.5.1 ITEEEB Security events as determined from the Safeguards Contingency Plan Site Attack 9.1.5.2 ITEEEB A notification from the site security force that an armed attack, explosive attack, airliner impact, or other HOSTILE ACTION is occurring or has occurred within the Protected Area Security event resulting in loss of physical control of the facility 9.1.G.1 ~

A hostile force has taken control of plant equipment such that plant personnel are unable to operate equipment required to maintain safety functions I 1 I 2 I 3 I 4 I 5 I def I I 1 I 2 I 3 I 4 I 5 I def I A validated notification from NRC providing information of an aircraft threat 9.1.U.2 Security events as determined from the Safeguards Contingency Plan Notification of an airborne attack threat 9.1.A.2 I 1 I 2 I 3 I 4 I 5 I def I Security events as determined from the Safeguards Contingency Plan 9.1.U.3 I 1 I 2 I 3 I 4 I 5 I def I A validated notification from NRC of an airliner attack threat less than 30 minutes away Notification of hostile action within the OCA 9.1.A.3 I 1 I 2 I 3 I 4 I 5 I def I Credible notification of a security threat to Columbia Generating Station I 1 I 2 I 3 I 4 I 5 I def I A notification from the site security force that an armed attack, explosive attack, airliner impact or other HOSTILE ACTION is occurring or has occurred within the OCA.1, Columbia Generating Station Emergency Classification Table

9 Hazards 9.1 Security Threats 9.1.S.2 Site Area Emergency NUMARC IC:

HS4 - Site Attack APPLICABILITY:

Operating Conditions EMERGENCY ACTION LEVEL:

A notification from the site security force that an armed attack, explosive attack, airliner impact, or other HOSTILE ACTION is occurring or has occurred within the Protected Area BASES:

This class of security events represents an escalated threat to plant safety above that contained in the Alert IC in that a hostile force has progressed from the Owner Controlled Area to the Protected Area.

Although NPP security officers are well trained and prepared to protect against HOSTILE ACTION, it is appropriate for Offsite Response Organizations to be notified and encouraged to begin preparations for public protective actions (if they do not normally) to be better prepared should it be necessary to consider further actions.

This EAL is intended to address the potential for a very rapid progression of events due to a dedicated attack. It is not intended to address incidents that are accidental or acts of civil disobedience, such as hunters or physical disputes between employees within the OCA. That initiating condition is adequately addressed by other EALs. Terrorist action identified above encompasses various acts including:

air attack (airliner impacting the protected area) land-based attack (HOSTILE FORCE penetrating protected area) waterborne attack (HOSTILE FORCE on water penetrating protected area). 1 NUMBER l3.1.IA REVISION 20 PAGE 1500f21O

bombs breeching the protected area This EAL is intended to address the contingency for a very rapid progression of events due to an airborne terrorist attack such as that experienced on September 11, 2001, and the possibility for additional attacking aircraft. It is not intended to address accidental aircraft impact as that initiating condition is adequately addressed by other EALs. This EAL is not premised solely on the potential for a radiological release. Rather the issue includes the need for assistance due to the possibility for significant and indeterminate damage from additional attack elements.

Although consequence analyses show NPPs to be robust, 1t 1S appropriate for Offsite Response Organizations to be notified and to activate in order to be better prepared to respond should protective actions become necessary. Federal agencies are expected to assist in the determination whether the aircraft impact was accidental or an attack. The Federal agency may be NORAD, FBI, FAA, or NRC.

However, the declaration should not be unduly delayed awaiting Federal notification. Airliner is meant to be a large aircraft with the potential for causing significant damage to the plant.

The NRC Headquarters Operations Officer (HOO) will communicate to the licensee if the threat involves an airliner. The status and size of the plane may be provided by NORAD through the NRC.

This EAL addresses the immediacy of a threat to impact site vital areas within a relatively short time.

The fact that the site is under serious attack with minimal time available for additional assistance to arrive requires ORO readiness and preparation for the implementation of protective measures.

Licensees should consider upgrading the classification to a General Emergency based on actual plant status after impact.

REFERENCE(S):

NRC Bulletin 2005-02, Emergency Preparedness and Response Actions for Security Based Events,, HS1, for NUMARC/NESP-007 EAL schemes NRC RlS 2006-12, EndorsementofNEI Guidance "Enhancements to Emergency Preparedness Programs for Hostile Action".1 NUMBER 13.1.1A REVISION 20 PAGE 151 of 210

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