ML051400286
| ML051400286 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/26/2005 |
| From: | Wilson M Dominion Nuclear Connecticut |
| To: | D'Antonio J Operations Branch I |
| Conte R | |
| References | |
| Download: ML051400286 (151) | |
Text
JOB PERFORMANCE MEASURE APPROVAL SHEET I
Title:
Validate an ECP (Faulted)
ID Number:
JPM-A1 RO Revision:
0 II.
Initiated:
Developer I I I. Reviewed:
IV. Approved:
User Department Supervisor k
Nuclear Traini Supervisor 1 /16/2005 Date Date
JOB PERFORMANCE MEASURE WORKSHEET Facility MP-2 Exam tnee JPM Number JPM-A1 RO Rev 0
Task Title Validate an ECP (Faulted)
System:
Administrative Time Critical Task:
Yes No X
Validated Time (minutes):
35 Task No.@):
NUTIMS #I 21 1 95 Applicable To:
SRO X
RO X
PEO K/A No.:
2.1.25 KIA Rating:
2.813.1 Method of Testinq:
S i m u I at e d Perform an ce :
Actual Performance:
X Location:
Classroom:
X Simulator:
X In-Plant:
X Task Standards:
The examinee reviews the completed ECP and determines that there is an error.
Required Materials
[procedures,equipment):
OP 2208, Reactivity Calculations, Rev. 13-05 Completed ECP Data and Analysis Sheet, OP 2208-001 ECP Reference Data Sheet, Attachment 1 General
References:
OP 2208, Reactivity Calculations, Rev. 13-05 READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.
2 of 16
JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
JPM-A1 RO Rev.
0 lnitiatinq Cues:
The US has directed you to validate a completed ECP in accordance with OP 2208, Reactivity Calculations, without the use of the PPC.
Initial Conditions:
The following conditions exist:
A Reactor startup is planned to begin within the next 30 minutes with criticality anticipated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from now.
The PPC is presently unavailable, but will be returned to service prior to the startup.
An ECP was completed 5 minutes ago.
Desired critical position is group 7 at 55 steps
- The plant tripped from 100% power 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ago.
- The plant had been at 100% for the past 220 days.
- Present Burnup provided by Reactor Engineering is 12,988 MWD/MTU RCS Tavg is being maintained constant at 532°F.
Reference data taken at 0900 on 0311 5/05 at 100% power is as follows:
572"Tavg 2.794 %Sp Xenon 0.900 % I p Samarium 12,850 MWDlMTU Burnup
- Group 7 CEAs at 180 steps Data is good until 14,000 MWDIMTU Simulator Requirements:
NIA NOTES TO EXAMINER *
- 1.
Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, When examinee states what hidher simulated actionlobservation would be, read the appropriate "Cue".
If necessary, question examinee for details of simulated actions / observations (i.e. "What are you looking at?" or "What are you observing?").
Under NO circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
critical steps must be completed correctly.
- 2.
- 3.
- 4.
3 of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-AIR0 TITLE: Validate an ECP (Faulted)
START TIME:
STEP I
__ Performance Steps: Verify the following:
Reactor Engineering has completed and provided reference critical position data on, ECP Reference Data Sheet (ECP Data Book)
Chemistry Department has been requested to sample and determine present RCS boron concentration.
0 GRADE- -
Standards :
Examinee obtains and/or asks for Attachment I, ECP Reference Data Sheet and the RCS Boron concentration.
- Cue, 0 Provide the filled out copy of OP 2208-001, ECP Reference Data Sheet and Attachment I, ECP Reference Data Sheet.
If requested, as chemistry, report that the RCS Boron concentration was reported 30 minutes ago.
Comments:
STEP 2 X Performance Steps: Refer To Attachment 1 and TRANSFER Reference Critical Data.
GRADE X
Standards:
Examinee verifies the critical data on OP 2208-001, ECP Data and Analysis Sheet is the same as the Reference Critical Data on Attachment I.
Cue:
Comments:
4 of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-AIR0 TITLE: Validate an ECP (Faulted)
STEP 3 X Performance Steps: RECORD the following Estimated Status at Criticality data:
Date and time RCS temperature ( T A V ~ )
GRADE-X Standards:
Examinee ensures the Estimated Status at Criticality is as fo//ows:
0 The date is today 0
The time is two hours from now TAvG is 532°F.
Cue:
Comments:
STEP 4 X Performance Steps: OBTAIN present burnup from one of the following and RECORD:
"CVBURNUP" (PPC) 0 Reactor Engineering.
GRADE X
Standards:
Examinee obtains Burnup from the initial data sheet and verifies 12,988 MWD/MTU is entered on the ECP Data and Analysis Sheet.
Cue:
5of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-AIR0 TITLE: Validate an ECP (Faulted)
STEP 5 Performance Steps: Unless otherwise specified by Reactor Engineering, CHECK core burnup change from reference data specified on Attachment I, to present burnup, does not exceed 1,000 MWD/MTU.
GRADE X
Standards:
Examinee determines the change in burnup is less than 1000 MWWMTU.
Cue:
If asked, as Reactor Engineering, there are no additional requirements for the core burnup change.
Comments:
STEP 6 2
Performance Steps: WHEN sample results are obtained, RECORD present boron concentration.
GRADE X
Standards:
Examinee verifies the recorded present boron concentration on OP 2208-001, ECP Data and Analysis Sheet is 4600 ppm.
Cue:
If asked, as chemistry, report that the RCS Boron concentration was reported 30 minutes ago.
Comments:
6 of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A1RO TITLE: Validate an ECP (Faulted)
STEP 7 Performance Steps: Refer to Attachment 1 and RECORD Desired Critical CEA Position.
GRADE- -
X Standards:
Examinee verifies the Desired Critical CEA Position on OP 2208-001, ECP Data and Analysis Sheet is the same as the value on the ECP Reference Data Sheet (group 7 at 55 steps).
Cue:
Comments:
STEP 8 X Performance Steps: DETERMINE Power Defect as follows:
- a. RECORD Reference Critical Data power value.
- b. Refer to OP 2208-018 and DETERMINE Power Defect at Reference Critical power value.
- c. Record Power Defect GRADE X
Standards:
Examinee verifies the Reference Critical Data power value is correctly recorded on the ECP Data and Analysis Sheet Examinee refers to OP 2208-018 and determines that the Power Defect at Reference Critical Power is correctly recorded on the ECP Data and Analysis Sheet.
0 Cue:
Comments:
7 of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A1 RO TITLE: Validate an ECP (Faulted)
STEP 9 X Performance Steps: DETERMINE Xenon Defect as follows:
- a. RECORD Reference Critical Data Xenon worth.
- b. Refer To one of the following and DETERMINE estimated Xenon worth at criticality:
0 Xenon-Samarium Post Trip Report (printed automatically on Control Room special typer following reactor trips) 0 XENON-SAMARIUM DEMAND program on Reactor Engineering
- c. RECORD estimated Xenon worth at criticality
- d. CALCULATE Xenon Defect as follows and RECORD:
Reference Critical Data Xenon worth - Estimated Xenon worth = Xenon Defect OP2208-004 PPC GRADE X
Standards:
0 Examinee verifies the Reference Critical Data for Xenon worth on the ECP Data and Analysis Sheet is the same as the ECP Reference Data Sheet.
Examinee refers to OP 2208-004 to obtain the estimated Xenon worth at criticality and verifies the value recorded on the E CP Data and Analysis Sheet is the same.
Examinee verifies the calculated Xenon Defect is correct.
0 Cue:
The Xenon-Samarium Post Trip Report is NOT available.
Comments:
8 of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A1 RO TITLE: Validate an ECP (Faulted)
STEP 10 -
X Performance Steps: DETERMINE Samarium Defect as follows:
- a. RECORD Reference Critical Data Samarium worth.
- b. Refer To one of the following and DETERMINE estimated Samarium worth at criticality:
0 Xenon-Samarium Post Trip Report (printed automatically on Control Room special typer following reactor trips) 0 XENON-SAMARIUM DEMAND program on PPC 0
Reactor Engineering
- c. RECORD estimated Samarium worth at criticality.
- d. CALCULATE Samarium Defect as follows and RECORD:
Reference Critical Data Samarium worth - Estimated Samarium worth = Samarium Defect OP2208-011 GRADE X
Standards:
0 Examinee verifies the Reference Critical Data for Samarium worth on the ECP Data and Analysis Sheet is the same as the ECP Reference Data Sheet.
Examinee refers to OP 2208-01 I to obtain the estimated Samarium worth at criticality and verifies the value recorded on the ECP Data and Analysis Sheet is the same.
Examinee verifies the calculated Samarium Defect is correct.
0 0
Cue:
The Xenon-Samarium Post Trip Report is NOT available.
Comments:
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PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A1RO TITLE: Validate an ECP (Faulted)
STEP 11 X
Performance Steps: DETERMINE CEA Worth Defect as follows:
- a. Refer To OP 2208-007 and DETERMINE CEA Worth for the following and RECORD 0
0 Desired Critical CEA Position
- b. CALCULATE CEA Worth Defect as follows and RECORD:
Reference Critical Data CEA Position worth - Desired Critical CEA Position worth = CEA Worth Defect Reference Critical Data CEA Position GRADE X
Standards:
0 Examinee refers to OP 2208-007 to obtain the CEA worth for the Reference Critical Data CEA Position and the Desired Critical CEA Position.
Examinee verifies the value recorded on the ECP Data and Analysis Sheet is the same as the values determined from OP 2208-007.
Examinee verifies the calculated CEA Worth Defect is correct.
0 0
Cue:
Comments:
10 of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A1 RO TITLE: Validate an ECP (Faulted)
STEP 12 X
Performance Steps: DETERMINE Boron Defect as follows:
- a. RECORD Reference Critical Data boron concentration.
- b. RECORD present boron concentration.
- c. Refer To OP 2208-005 and DETERMINE the Inverse Boron Worth at present burnup.
- d. RECORD Inverse Boron Worth.
- e. CALCULATE Boron Defect as follows and RECORD:
(Reference Critical Data boron concentration -
Present boron concentration) / - Inverse Boron Worth
= Boron Defect GRADE X
Standards:
0 Examinee verifies the Reference Critical Data for Boron concentration on the ECP Data and Analysis Sheet is the same as the ECP Reference Data Sheet.
Examinee verifies the present Boron concentration on the ECP Data and Analysis Sheet is 460 ppm.
Examinee refers to OP 2208-051 to obtain the liiverse Boron Worth at present burnup and verifies the value recorded on the ECP Data and Analysis Sheet is the same.
Examinee verifies the calculated Boron Defect is correct.
0 0
Cue:
Comments:
11 of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A1RO TITLE: Validate an ECP (Faulted)
STEP 13 X
Performance Steps: DETERMI NE Plutonium Buildup as follows:
- a. Refer To OP 2208-01 9 and DETERMINE Plutonium Buildup worth at criticality.
- b. RECORD Plutonium Buildup worth at criticality GRADE X
Standards:
0 Examinee refers to OP 2208-019 to obtain the Plutonium worth at criticality.
Examinee verifies the value recorded on the ECP Data and Analysis Sheet is the same as the value determined from OP 2208-01 9.
Cue:
Comments:
STEP 14 X
Performance Steps: DETERMINE the sum of all defects as follows:
- a. ENTER a// previously calculated reactivity defects.
- b. CALCULATE the sum of all reactivity defects and RECORD.
GRADE X
Standards:
0 Examinee verifies that each of the defects entered on the ECP Data and Analysis Sheet is correct.
0 Examinee adds the defects and determines that the total matches the total on the ECP Data and Analysis Sheet.
Cue:
Comments:
12 of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-AIR0 TITLE: Validate an ECP (Faulted)
STEP 15 X
Performance Steps: DETERMINE Boron Equivalent of Defects as follows:
- a. Record the following:
Sum of defects 0
Inverse Boron Worth at present burnup
- b. Calculate Boron Equivalent of Defects as follows and record:
Sum of Defects x lnverse Boron Worth = Boron Equivalent of Defects GRADE X
Standards:
0 Examinee verifies that the sum of defects and the inverse Boron worth entered on the ECP Data and Analysis Sheet are correct.
Examinee determines that the value of Boron Equivalent of Defects entered on ECP Data and Analysis Sheet is correct.
0 Cue:
Comments:
STEP 16 -
X Performance Steps: DETERMINE Boron Equivalent of Reactivity Change Due to Burnup as follows:
- a. If the difference between present burnup and Reference Critical Data burnup is less than or equal to 200 MWD/MTU, record N/A in this section and go to step 4.1.17.
GRADE X
Standards:
Examinee determines that this step is Not Applicable and is correctly marked on ECP Data and Analysis Sheet.
Cue:
Comments:
13 of 16
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-AIR0 TITLE: Validate an ECP (Faulted)
STEP 17 X
Performance Steps: DETERMINE Determine Required Boron Change for Criticality as follows:
- a. Record the following:
0 Boron Equivalent of Defects 0 If any, Boron Equivalent of Reactivity Cahnge Due to Burnup.
- b. Calculate critical boron concentration as follows and record:
Present Equivalent of Defects + Boron Equivalent of Reactivity Change Due to Burnup = Required Boron Change.
GRADE X
Standards:
Examinee observes that an incorrecf value for Boron Equivalenf of Defects has been entered on the ECP Data And Analysis Sheet. (-18 should be entered.)
Examinee informs Reactor Engineering of the error on the ECP Data and Analysis Sheet.
0 Cue:
As Reactor Engineering, acknowledge the error on the ECP Data and Analysis Sheet.
Comments:
The examinee may NOT find the error until he/she calculates Critical Boron Concentration.
Comments:
When Reactor Engineering is informed of the error on the ECP, the JPM is complete.
STOP TIME:
14 of 16
VERIFICATION OF JPM COMPLETION Job Performance Measure No.
JPM-A1 RO Rev.
Date Performed:
Operator:
Eva1 uato r( s) :
0 -
For examinee to achieve a satisfactory grade, Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
critical steps must be completed correctly. If task is Time Critical Task?
Yes No X
Validated Time (minutes):
35 Actual Time to Complete (minutes):
Result of JPM:
(Denote by an 5 for satisfactory or a u for unsatisfactory)
Areas for Improvement:
15 of 16
EXAMINEE HANDOUT JPM ID Number:
JPM-AIR0 lnitiatinq Cues:
Initial Conditions:
The US has directed you to validate a completed ECP in accordance with OP 2208, Reactivity Calculations, without the use of the PPC.
0 The following conditions exist:
A Reactor startup is planned to begin within the next 30 minutes with criticality anticipated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from now.
The PPC is presently unavailable, but will be returned to service prior to the startup.
An ECP was completed 5 minutes ago.
Desired critical position is group 7 at 55 steps
- The plant tripped from 100% power 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ago.
- The plant had been at 100% for the past 220 days.
- Present Burnup provided by Reactor Engineering is 12,988 MWD/MTU
- RCS Tavg is being maintained constant at 532°F.
Reference data taken at 0900 on 03/15/05 at 100% power is as follows:
- 572"Tavg
- 2.794 %Ap Xenon
- 0.900 %Ap Samarium
- 12,850 MWDIMTU Burnup
- Group 7 CEAs at 180 steps Data is good until 14,000 MWD/MTU 0
0 16 of 16
I (Sheet 1 of 1)
I@
I O I
The following is recommended for use as reference data in support of OP 2205-001, ECP Data and Analysis Sheet, up to an exposure of
/q, 0 00 MWD/MTU:
---A!@-
TAVG 5 7 2 F
Power BurnuP
/ 2,frO MWDIMTU RCSBoron
,3qfi ppm Xenon 2.799 %A@
%AQ Current version of ECP software 2 *OM?
Desired Critical Position: CEA group 7 at C T steps Reactivity Bias following Hot Zero Power Shutdown - 22 2 pcln Reviewed By:
-c.
Date most rWentb completed attachment is retcrrned in ECP Data Book.
OP 220s Rev. 01 3 -OS 29 of 4J W
A STOP THINK nformation
Form Approval I l >, l l C Time 0 700 Burnup 5,
c; 5
7 "F /2,grJ hlWD/hlTU Approval Dale I
Power Xenon c/o 2, 79q 'CAY
/ l i D 3L;/S ppm
- 0.
9QO CrAg Samarium Boron 10/18/04 T~~~
DareiTime 53 z O F
/
/ d a y i n z Lours Desired Critical CEA Position Effective Date Biirnup (presenr) 1 2, 988 MWD!'hiTu Boron (present) 12/16/04 Reference Critic;il Data power value power Defect at Reference critical D~~~~
YO power value (OP 2208-018)
Irn ECP Data and Analysis Sheet Power Defect 2. 0 2 9 rrAp I CEA Group 7 at 5.S steps I
Xenon Delect I Samarium Defect I
I Samarium Defect 0, 9 9 7 1 CEA Worth Defect (OP 2208-007)
OP 220s-001 Rev. 007-01 Page 1 of 3
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I ECP Data and Analysis Sheet Plutonium Buildup Worth Ylutoniuni Buildup Worth at Criticality (OP 2208-019)
I Pu Buildup Worth I
Boron Equivalent of Reactivity Change Due to Burnup (SP 21018-002)
(N/A if present burnup minus Reference Critical Data burnup is 5 200 MWD/MTU)
I Concentration
- 16' PPm I + I R
PP"'
PPm Limits on CEA Position at Criticality
- I imrts for initial criticality 'ifter refueling <ire +/- 0 9 For all subsequent iextor st'irtripc. the limits,ire +i- 0.5
- Insertion must be above 0% PDIL, E below 0% PDIL, CEA croup 4 at 72 step5 is entered OP 220s - 00 I Rev. 007 - 0 I Page 2 of 3
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Date: /
l e Any Dale:
Time:
15-M;d. 90 Time:
'AVG Dntenime "F
CE.A Position CEA Group at steps Rein arks:
Critical Number Boron PPm Reviewed By Reactor Engineer:
or 220s - 00 1 Rev. 007-01 Page 3 of 3 lhte:
~
~
ECP Reference Data Sheet (Sheet 1 of 1)
The following is recommended for use as reference data in support of OP 2205-001, ECP Data and Analysis Sheet, up to an exposure of Daterime
.3//s/dcf 700
/q, 0 00 MW D/MTU:
I Power 1
0 96 TAVG 5 7 2 O
F Burnup
/ 2, f ~ ~ O MWDMTU RCSBoron 330 ppm Xenon 2,794
%A@
Samarium d.9QfJ
%A@
Controlling 7
at (6.30 steps Regulating Group Current version of ECP software zOoiA Desired Critical Position: CEA group 7 at 5 T steps Reactivity Bias following Hot Zero Power Shutdown Reactivity Bias following Cold Shutdown - 2 73 pcm
- 22 2 pcin Performed By:
6 Reviewed By:
-2.
. f L Date The most recently completed attachment is wtuined in ECP Data Book.
or 220s Rev. 013 - 05 29 of 41 STOP Tt-4 rp ACT REVIEW nformation IG IO
I Form Approval I 1211 6/04 Effective Dale 1011 8/04 Approval Date I
Date 3//.$05-
'.4VG I
Power Xenon Time 2.79q
%A@
Samarium ha Boron 0 900 Burnup CEAGroup L
a t
S-X steps 5 72 "F /2,fxJ MWD/MTU I
L, 76d' MWD/MTU Boron (present) 3c;/C' ppm
- 0.
900 %Ae Reference Critical Data power value Im, 70 I
erence Critical Data power Defect at Reference Critical Data power value (OP 2208-018)
Power Defect I
I CEA Worth Defect (OP 2208-0071 I
CEA Worth Defect I Boron Defect I
OP 220s - 001 Rev. 007-01 Page 1 of 3
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ECP Data and Analysis Sheet Plutonium Buildup Worth Plutonium Buildup Worth at Criticality (OP 2208-019)
Pu Buildup Worth I
Sum of Defects I
I Boron Equivalent of Defects I
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Baron Equivalent of Reactivity Change Due to Burnup (SP 21018-002)
(N/A if present burnup minus Reference Critical Data burnuD is < 200 MWD/MTU\\
I Concentration I Limits on CEA Position at Criticality I
I Desired Critical CEA Position worth c
limits ;Ire +/- 0.5
.... - Insertion must be above 0% PDIL, E below 0% PDIL, CEA group 4 at 72 steps, is entered.
OP 2205-001 Rev. 007-01 Page 2 of 3
ECP Data and Analysis Sheet Date:
J Approved By SMNSIRE:
Date:
Time:
iSln;n.
lime:
Actual Critical Data (power at approximately 1 x Critical Number T~~~
Datemime "F
CEA Position Boron PPm I CEA Group at steps Remarks:
Reviewed By Reactor Engineer:
Diire:
1 OP 220s - 00 1 Rev. 007-01 Page 3 of 3
Form Approval 1 Approval Date I
I Reference Critical Data Date Time Power Xenon
%tie T~~~
MWDMW PPm
%he 1 EffectiveDate T~~~
I DateRime "F
Desired Critical CEA Position CEAGroup I_ at steps 10/18/04 Bumup (present)
MWDMTU Boron (present)
PPm 12/16/04 1
Power Defect Reference Critical Data power value Power Defect power Defect at Reference Critical Data power value (OP 2208-018)
%A@
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YoAe -
%he -
ECP Data and Analysis Sheet Yobp I Controlling Regulating Group
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at steps I
1
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I Samarium Defect I
Samarium Defect I
CEA Worth Defect OP 220s - 00 1 Rev. 007 -01 Page 1 of 3
OP 2208 - 001 i
Rev. 007 - 01 Page 2 of 3
ECP Data and Analysis Sheet ECP Calculated By (signature):
Date:
Time:
Approved By SM/US/RE:
Date:
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JOB PERFORMANCE MEASURE APPROVAL SHEET I.
Title:
RO Tan Clearance Preparation ID Number:
JPM-A2RO II.
Initiated:
Developer I l l.
Reviewed:
IV. Approved:
User Department Supervisor Revision: -
0 1/28/05 Date Date Date
SUMMARY
OF CHANGES I~~~
1 All 8, Date DESCRIPTION 1
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Developed new JPM R EVlCHANG E 0
2
JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number:
J P M -A 2 R 0 Rev.
0 Task
Title:
Perform Tagging Operations System:
Administrative Time Critical Task:
Yes No X
Validated Time (minutes):
25 Task No.(s):
NUTIMS #119-03-170 Applicable To:
SRO X
RO X
PEO X
KIA No.:
2.2.13 KIA Rating:
3.613.8 Method of Testinq:
Simulated Performance:
X Actual Performance:
Location:
Classroom:
X Simulator:
X In-Plant:
X Task Standards:
At the completion of this JPM, the examinee will present a recommended tagging clearance to the tagging authority.
The clearance must be similar to the ANSWER KEY attached to this JPM except for the exceptions as noted in the step 3 of this JPM.
Required Materials WC 2 Tagging
[procedures, equipment):
P&ID 25203-26027 sheet 2 of 4 P&ID 25203-3001 1 sheet 12F OP-233OC-001 General
References:
WC 2, Section 1.3 (Rev. 6-06)
READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments.
and log entries as if the evolution was actually being performed.
3 Tagout Request (Sheet 1 of 1)
NOTE: When this request is used, all sections should be tilled out in detail.
Work Package Number:
Component to be Isolated(*) : E 11 - / 3 Multiple isolation points or non-component (i.e.: pipeltube section): Yes M i-0 ~ f -
0 3 (0 8 b Q' NO Q (If yes, walkdown required by Tagging Authority)
Recommended 'pags Color Isolation Point Position(1)
(1) For Biue Tags indicate initial position or if initial position is nof required enter NIA.
bplifying Instructions:
L Contact Person (for multiple shifts, Contact Person is required for each shift) phone:
Date:
A - J k -
phone: 2 1 1 q Team Leader / Planner / Engineering Approved By:
wc 2 Rev. 006-06 73 of 86 nformation
JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
JPM-A2RO Rev.
0 Initiating Cues:
Initial Conditions:
Simulator Requirements:
The WC-SRO has reviewed the work package and has directed you to prepare a tagout for 2-CHW-123 Chill Water Pump (P-149C) Discharge Isolation valve.
The valve must be replaced due to leakage past the seat.
Restoration information is not required.
The Tagout Number (Section Number) is 233OC62-003 The AWO number is M2-04-03686 The contact person is V. Team Chemistry will advise as to the disposal of water per NPDES.
All drawings have been verified Controlled, Approved. and Up to Date.
The examiner will review and approve the tagout.
2-CHW-123 Chill Water Pump (P-149C) Discharge Isolation valve is leaking by its seat.
Maintenance advised removal and replacement of the valve.
The Station Tagging Computer Program is unavailable.
The need for a manual tagout has been evaluated and approved by all required personnel.
The tagout will be entered into the computer as soon as the computer is available.
None NOTES TO EXAMINER * * * *
- 1. Critical steps for this JPM are indicated with an X. For the examinee to achieve a satisfactory grade, When examinee states what his/her simulated action/observation would be, read the appropriate Cue.
If necessary, question examinee for details of simulated actions / observations (i.e. What are you looking at? or What are you observing?).
critical steps must be completed correctly.
- 2.
- 3.
- 4.
Under circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A2RO TITLE: RO Tan Clearance Preparation START TIME:
STEP 1 J-Performance Steps:
GRADE-X Standards:
Per WC-2, Attachment 8, Manual Tagouts Prepare a Manual Tagout using (Attachment 9), Manual Tagout Sheet, and appropriate sections in this procedure.
The examinee obtains a copy of WC-2. Tagging, and WC-2 Attachment 9 Manual Tagout Sheet.
Using the following references:
P&ID 25203-26027 sheet 2 of 4 P&ID 25203-3001 I sheet 12F OP-233OC-001 Chilled Water System Valve Alignment The examinee determines the:
Components being tagged.
Colors for each tag.
Cue:
0 When requested, provide the examinee with the required documentation, including the enclosed WC2, Tagging.
If requested, provide examinee with Attachment 7, Tagout Request.
Comments:
The examinee may use equivalent documentation for determining components to be tagged.
5
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A2RO TITLE: RO Tan Clearance Preparation STEP 2 X Performance Steps: Enter the sequential steps for establishing a safe working area to include:
Components Equipment ID Tag color Appropriate instructions Appropriate Tag Position GRADE X
Standards:
On attachment 9, enter the following:
Tagout number Date AWO number Contact person Equipment Reason Tagged Special instructions Cue:
Comments:
Special Instructions may reference chemistrys involvement in draining fluids and/or NPDES.
6
PERFORMANCE INFORMATION JPM ID NUMBER.
JPM-A2RO TITLE: RO Tag Clearance Preparation STEP 3 Performance Steps: Enter the component name, identification number, location, tag type, and required position on.
GRADE Standards:
Examinee enters the following information on Attachment 9:
- 1. Yellow, P149C-HS~.
Non-Vital Chilled Water Pump C Turbine Building 146. (Optional)
- 2. Red, B2175 Pl49C Non-Vital Chilled Water Pump C Turbine Building 31 6: (Open)
- 3. Red, B2174, Xl96B Vital Chiller Supplemental Turbine Building 31 6: (Open)
- 4. Red; 2-CH W-1 16, Chill Water Pump (P-149C)
Suction Isolation, Turbine Building 14 6 (Closed)
- 5. Red; 2-CHW-125, P-149B Cross Tie to X-196B Turbine Building 146 (Closed)
- 6. Red; 2-CHW-126, X-196B Outlet Isolation Turbine Building 146 (Closed)
- 7. No Tag; 2-CHW-123, Chill Water Pump (P-149C)
Discharge Isolation Turbine Building 146: (Open)
- 8. Red; 2-CHW-147, Chill Water Pump (P-149C)
Discharge Drain Turbine Building 14 6 (Open)
- 9. Red; 2-CHW-174, P149C Crosstie Header Vent:
Turbine Building 14 6 (Open)
Cue:
Comments:
The component order may differ slightly provided:
Breakers, B2175 and B2174, are tagged open before the boundary valves are closed, (i,e., the pump & compressor breakers must be opened prior to closing the pump discharge and suction valves).
The boundary valves are closed before opening the vent and drain valves.
7
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A2RO TITLE: RO TaQ Clearance Preparation STEP 4
__ Performance Steps: Complete block number 11, Prepared by:
GRADE __ __ Standards:
Examinee enters his (her) name in block 7 1 of.
Cue:
Comments:
After this step is completed, the JPM is considered complete.
c-------L--_----_5--~-----------~--
STOP TIME:
8
VERIFICATION OF JPM COMPLETION For examinee to achieve a satisfactory grade, critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
J Job Performance Measure No.
JPM-A2RO Rev 0
Date Performed:
Operator:
Eva I ua to r( s) :
Time Critical Task?
Yes No Validated Time (minutes):
25 Actual Time to Complete (minutes):
Result of JPM:
(Denote by an 5 for satisfactory or a u for unsatisfactory)
Areas for Improvement:
9
EXAMINEE HANDOUT JPM Number:
J PM-A2RO Rev.
0 Initiating Cues:
The WC-SRO has reviewed the work package and has directed you to prepare a tagout for 2-CHW-123 Chill Water Pump (P-149C) Discharge Isolation valve.
The valve must be replaced due to leakage past the seat.
Restoration information is not required.
The Tagout Number (Section Number) is 233OC62-003 The AWO number is M2-04-03686 The contact person is V. Team Chemistry will advise as to the disposal of water per NPDES.
All drawings have been verified Controlled, Approved, and Up to Date.
The examiner will review and approve the tagout.
Initial Conditions:
2-CHW-123 Chill Water Pump (P-l49C) Discharge Isolation valve is leaking by its seat.
Maintenance advised removal and replacement of the valve.
The Station Tagging Computer Program is unavailable.
The need for a manual tagout has been evaluated and approved by all required personnel.
The tagout will be entered into the computer as soon as the computer is available.
10
ONLY ANSWER KEY Manual Tagout Sheet Y
3 I3a. Tagout correct and equiprnent ma) be isolated SM/I.JS notified for poner block Boundark approved by:
Authorized to be hung by:
Red: 2:CHW-147, Chill Water Pump (P-l49C) Discharge Drain Turbine Building 146 (Open).
Red; 2-CHW-174. P I49C Crosstie Header Vent, Turbine Building 146 (Open)
STOP THIZIK ACT REVIEW wc 2 Rev. 006-06 76 of86
JOB PERFORMANCE MEASURE APPROVAL SHEET I
Title:
Review RWP and Survey Map ID Number:
JPM-A3RO It.
Initiated:
k!$&
R. J. Ashev Developer Ill. Reviewed:
IV. Approved:
User Department Supervisor Revision:
0 -
10/29/04 Date Date
JOB PERFORMANCE MEASURE WORKSHEET Facility MP-2 Examinee:
JPM Number:
J P M-A3R 0 Rev.
0 Task
Title:
Review RWP and Survey Map System:
Radiation Control Time Critical Task:
Yes No X
Validated Time (minutes):
10 Task No.(s):
NUTIMS # 404-01-004 Applicable To:
PEO K/A No.:
2.3.1 K/A Rating:
2.6/3.0 Method of Testinq:
Simulated Performance:
Actual Performance:
X Location:
Classroom:
X Simulator:
X In-Plant:
X Task Standards:
At the completion of this JPM the examinee has reviewed the applicable RWP and survey map to determine the radiological requirements to perform the assigned task.
Required Materials
{procedures,equipment):
General
References:
Operations blanket RWP No. 5.
Survey map for -45 6 elevation of the Auxiliary Building RPM 5.2.2, Basic Radiation Worker Responsibilities, Rev. 009-03 READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.
2
JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
J P M-A3 R 0 Rev.
0 Initiating Cues:
0 You have been directed to align 2-SI-306, SDC Total Flow Control Valve, for remote operation and to perform the position indication surveillance.
0 Based on previous experience, it is estimated that this task will take 40 minutes.
0 State the radiological requirements for entering this area. Include in your discussion:
Which RWP task (job step) is appropriate for this assignment Protective clothing required in the work area Highest radiation level in the work area Expected dose for this assignment Dose rate alarm The examiner will act as Health Physics (HP) for any related questions.
0 Initial Conditions:
0 The plant is in MODE 3 and cooling down in preparation for a refueling outage.
The crew is preparing the Shutdown Cooling System for operation 0
in accordance with OP 2207, Plant Cooldown.
Simulator Requirements:
N/A NOTES TO EXAMINER * * *
- 1 Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, ALL critical steps must be completed correctly.
When examinee states what hidher simulated action/observation would be, read the appropriate "Cue".
If necessary, question examinee for details of simulated actions / observations (i.e. "What are you looking at?" or "What are you observing?").
- 2.
- 3.
- 4.
Under circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
3
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A3RO TITLE: Review RWP and Survey Map START TIME:
STEP 1
__ Performance Steps: Review Operations Blanket RWP No. 5 and Radiation Survey Figure 2 GRADE Standards :
Examinee reviews Operations Blanket R WP No. 5 and Radiation Survey Figure 2 Cue:
0 0
Provide examinee with Operations Blanket RWP No. 5 and Radiation Survey Figure 21A.
If required, state that the HP brief is complete.
Comments:
0 0
Examinee may state that a briefing with HP is required prior to entry into the work area.
The examinee may perform the following steps in any order.
STEP 2
-& Performance Steps: Review survey map and determine the following:
0 0
Contamination level in the work area Highest radiation level in the work area GRADE X
Standards:
Examinee reviews the survey map and states:
The work area is NOT contaminated.
The highest radiation level it7 the work area is 90 mdhr.
Cue:
Comments:
The examinee may point out the 200 mr/hr hot spot on the SDC Heat Exchanger, but the assigned task does NOT require him/her to approach that area.
4
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A3RO TITLE: Review RWP and Survey Map STEP 3 Performance Steps: Review the RWP and determine the following:
Which RWP task (job step) is appropriate for this assignment 0
Protective clothing required in the area 0
Expected dose for this assignment Dose rate alarm GRADE Standards:
Examinee reviews the RWP and states that:
X X
X 0
Expected dose is 60 mr.
X Dose rate alarm is 700 mr/hr.
0 0
Task ('job step) No. I is appropriate for this task There is NO contamination in the work area; therefore, NO additional protective clothing is required.
Cue:
If required, ask examinee what protective clothing helshe thinks should be worn.
Comments:
Although NO protective clothing is required, the examinee may opt to don PCs due to the potential for contamination.
Examinee may also state the need to obtain a key for the locked high rad area door.
Comments:
After this step is completed, the JPM is considered complete.
STOP TIME:
5
VERIFICATION OF JPM COMPLETION Job Performance Measure No.
JPM-A3RO Rev.
0 -
Date Performed:
Operator:
Eva I ua tor( s) :
For examinee to achieve a satisfactory grade, critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task?
Yes No X
Validated Time (minutes):
10 Actual Time to Complete (minutes):
Result of JPM:
(Denote by an S for satisfactory or a u for unsatisfactory)
Areas for Improvement:
6
EXAMINEE HANDOUT JPM ID Number:
JPM-A3RO Initiating Cues:
Initial Conditions:
0 You have been directed to align 2-Sl-306, SDC Total Flow Control Valve, for remote operation and to perform the position indication surveillance.
0 Based on previous experience, it is estimated that this task will take 40 minutes.
State the radiological requirements for entering this area. Include in your discussion:
Which RWP task (job step) is appropriate for this assignment Protective clothing required in the work area Highest radiation level in the work area Expected dose for this assignment Dose rate alarm The examiner will act as Health Physics (HP) for any related questions.
0 0
The plant is in MODE 3 and cooling down in preparation for a refueling out age.
The crew is preparing the Shutdown Cooling System for operation in accordance with OP 2207, Plant Cooldown.
0 7
RADIATION WORK PERMIT - 5 RWP Type RWP Category RWP Expiration ALARA Review NO RWP DBSCRIPTION Hours-Estimated Authorized Internal(DAC)- Estimated Authorized External(mRem)-Estimated Authorized 26000 00000 0000 0000 026000 026000 Operations General RWP i
TASK
SUMMARY
SPECIAL INSTRUCTIONS
~~~
~
~
~ ~ ~ _ _ _ _ _ _
~
~~
~~
~~
~
~
_ _ _ _ _ _ ~
General access to RCAs to perform routine and special Entry on this RWP requires the worker to understand rounds, inopections, tagging, surveillances, and comply with the following:
and training and qualifications during Power
- Be knowledgeable of radiological conditions of operations.
the work area
- f Adhere to the requirements of the RWP
- f Notify HP before entering overhead areas
- Monitor electronic dosimeter frequently,
- Unless specifically briefed otherwise, if especially in high noise areas DOSE RATE alarm sounds, move to a lower dose area and notify HP
- If DOSE alarm sounds, leave the area and notify HP
- If electronic dosimeter malfunctions, notify HP
- Modesty garments will be worn whenever PCs are worn BEFORE logging out RWP Term/Rev Date/Time Terminated/Rev by i
RADIATION WORK PERMIT - (5) JOB STEP - I OF 4 Department/Company OP/DNC Plant Code lYear /RWP Number IRev. lRWP Start I
5 1 0005 I 00 I 01-jan-2005 Job Supervisor/Extension Department/Company WILLIAM HOFFUER/C2OO OP/DNC
~ R W P Type
~ R W P Category IRWP Expiration 1
I POWER I
0 5 - jan-2006 I
G I
Loc at ion LEVELs/MULTIPLE AREAS Responaible Individual/Extension I WILLIAM HOFFNEi1/6200 Plant Equipment Rad. Area Type MISCELLANEOUS U-2 EQUIPMENT j Building j Floor 2 AUX ALARA Review Hours-Estimated Authorized Internal(DAC)- Estimated Authorized No 10000 00000 0 0 0 0 0 0 0 0 0 0 j Zone External(mRem)-Estimated Authorized 010000 010000 System Code Component Code Task NRC Task Alara Zone Location 2000 MISC OPS RO 2MISC 2 2 0 0 WRITTKN DESCRIPTION OF JOB (HATERIALS & METHODS)
Operatxons activities in RCAs, Radiation Areas, and High Radiation Areas.
Plant Equipment 2MISC Health Physics Representative Date RWP Tenn/Rev Date/Tlme SURVEY XEASURXMENTS Terminated/Rev by RADIATION (MR/HR)
CoNTAMINATION(DPM/100CM2)
AIRBORNE (DAC)
Review latest radiological surveys or historical data prior to entering RCA.
SPECIAL INSTRUCTIONS NO entry t o Tech Spec Locked High Radiation Area9 permitted using this Job Step.
systems.
PCs required in contaminated areas.
HP eupervision may adjust protective clothing requirements based on any of the following:
Notify HP before venting or draining any contaminated TEDE ALARA reviews
+ Heat otreos evaluations FME controls Requirements for High Radiation Area entries:
Dose rate meter or alarming doeimeter AND knowledge of area dose rates, OR continuous HP coverage Health Physics briefing for High Radiation Areas Lab coats may be worn for inspection-related tasks only; no physical work in contaminated areas may be performed.
Dose Limit Alarm(Stay Time)= 0025 mrem D o s e Rate Alarm= 0100 mr/hr Elansed Time Alarm= 0000 m i n.
RADIATION WORK PERMIT - (5) JOB STEP - 2 OF 4 Responsible Individual/Exteneion WILLIAM HOFFNER/62OO Building Floor Zone I
2 AUX IRWP Type IRWP Category IRWP Expiration 1
I. G 1,
POWER I
05-jan-2006 1,
Department/Company Job Supervisor/Extension Departrnent/Cmpany OPIDNC WILLIAM HOFMER/6200 OP/DNC I
I Location Plant Equipment Rad. Area Type LEVELS/MULTIPLE AREAS MISCELLANEOUS U-2 EQUIPMENT Solid Rad Waste 5 - 1500 clK
-5' West Penetration 10 - 2000
<1K L e t down Heat Exchanger 10 - 1200
<1K
_____ ~~
~~
1 ( T S L G ) Operations activities in Tech Spec Locked High Radiation Areas
<. 3
<. 3
<. 3 ALARA INFORMATION Health Physics Representative Date RWP Term/Rev Date/Time I
~
Estimated Authorized Internal(DAC)- Estimated Authorized External(mRem)-Estimated Authorized 005000 005000 05000 00000 00000 0 0 0 0 0 I Terminated/Rev by Plant Equipment I 2MISC System Code IComponent Code ITask Loca t ion I
2000 MISC OPS I
RO I 2 2 0 0 PCs required in contaminated areas.
HP supervision may adjust protective clothing requirement8 based on any of the following:
TEDE ALARA reviews Heat stress evaluations
Lab coats may be worn for inspection-related tasks only; no physical work in contaminated areas may be performed.
Requirements for Tech Spec Locked High Radiation Area entry:
Dose rate meter, or alarming dosimeter AND knowledge of area dose rates OR continuous H P coverage specific work area Review most current survey results of the Area MUST be locked or guarded at ALL times
- Health Physics briefing for Tech Spec Locked Refer to RPM 2.5.8 and determine Stay Time High Radiation Areas IDose Limit Alarm(Stay Time)= 0050 mrem D o s e Rate Alarm= 0500 mr/hr BlaDsed Time Alarm= 0000 min.
RBQUIRXXENTS Lab coat Electronic dosimeter TLD Health Physics Coverage Periodic Minimum Margin:
0225 nu-em
RADIATION WORK PERMIT - (5) JOB STEP - 3 OF 4 Plant code 2
Year RWP Number Rev. RWP Start RWP Type RWP Category RWP Expiration 5 1 0005 1'00 1 01-jan-2005 I
G 1 '
POWER I
05-jan-2006 I
I 1
1 I
Location i LEVELS/MULTIPLE AREAS Responsible Individual/Extension WILLIAM HOFF'NER/6200 i
Plant Equipment Rad. Area Type j MISCELLANEOUS u-2 EQUIPNENT j
Department/Company Job Supervisor/Extension Department/Company OP/DNC WILLIAM HOFFNER/6200 OP/DNC WRITTEN DESCRIPTION OF JOB (MATERIALS P HERIODS)
ALARA Review Hours-Estimated Authorized Internal(DAC)- Estimated Authorized No 01000 00000 0 0 0 0 0 0 0 0 0 0 Operations Training classes activities in RCAs, Radiation Areas, and High Radiation Areas.
I External(mRem)-Estimated Authorized 001000 001000 System Code Component Code Task 2000 MISC OPS SuRVgy MEASURKMRNTS RADIATION (MR/HR)
CoNTAMINATION(DPM/100CM2) AIRBORNE (DAC)
NRC Task Alara Zone Location Plant Equipment RO 2MISC 2200 ZMISC Review latest radiological surveys or historical data prior to entering RCA.
Health Physics Representative Date RWP Term/Rev Date/Time SPECIAL INSTRVCTIONS NO entry to Tech Spec Locked H i g h Radiation Areas permitted using this Job Step.
Terminated/Rev by PCs required in contaminated areas.
I I
HP supervision may adjust protective clothing requirements based on any of the following:
- Heat stress evaluations
- FME controls I
Requirements f o r High Radiation Area entries:
- Health Physics briefing for High Radiation Areas Lab coats may be worn for inspection-related tasks only; no physical work in contaminated areas may be performed.
Dose Limit Alarm(Stay T i m e ) = 0025 mzem Dose Rate Alarm= 0100 mr/hr Elapsed Time Alarm= 0000 m i n.
I
RADIATION WORK PERMIT - (5) JOB STEP - 4 OF 4
' Plant Code YeaqRWyNumber 1 Rev. I RWP St art IRWP Type IRWP Category IRWP Expiration
~
I 2
s I 0005 I 00 I 01-jan-200s I I G I
POWER I
05-jan-2006 1
I 1
I I
1 Responsible Individual/Extension Department/Company Job Supervisor/Extension Department/Company WILLIAM HOFFNER/C 2 00 OP/DNC WILLIAM HOFFNER/BZOO OP/DNC I Building Floor 2AUX
-25' Zone Location Plant Equipment Rad. Area Type CHARGING PUMP CUBICLES MISCELLANEOUS ALARA Review NO
~
(&CRFek Alara Zone Locat ion Plant Equipment 1 2226 I 2226 12300 p?;; Code Hours-Estimated Authorized Internal(DAC)- Estimated Authorized External(mRem1-Estimated Authorized 10000 00000 00000 0 0 0 0 0 010000 010000
~
SURVEY MEASUR-TS Review latest radiological surveys or hiotorical data before entering RCA.
RADIATION (MR/HR) coNTAMINATION(DPM/lOOCMZ)
AIRBORNE (DAC)
~~
NO entry to Tech Spec Locked nigh Radiation Areas permitted using this Job Step.
r
~~~~~
HP will establish dosimetry placement based on intended taeks and work area surveys.
i PCs required in contaminated areas.
Notify AP before dieassembling components HP supervision may adjust protective clothing requirements based on any of the following:
TEDE ALARA reviews 9 Heat stress evaluations FME controls Requirements for High Radiation Area entries:
- Dose rate meter or alarming dosimeter AND knowledge of area dose rates, OR continuous HP coverage Health Physics briefing for High Radiation Areas Lab coats may be w o r n for inspection-related tasks only; no physical work in contaminated areas may be performed.
Notify HP before entering overhead areas Dose Limit Alarm(Stay T i m e ) = 0025 n u e m Dose Rate Alarm= 0100 mr/hr Elapsed T i m e Alarm= 0000 m i n.
RXQUIREMRNTS Protective clothing:
Cotton liners Booties
- Coveralls
- Shoe covers
- Rubber gloves
- Modesty gamente Lab coat Electronic dosimeter TLD Health Physics Coverage Routine Minimum Margin:
0125 mrem I
IRWP Term/Rev Date/Time Tenninated/Rev by I
I (Health Phyeice Representative Date
mLLm -
y r r r r 1 -
RAD Comtu. A m RAD MAT. AREA CONTMWATED AREA RAD AREA HIGH RAD AREA TECH SPEC HRA GRAVE DANGER ARE^
NEW-100 - gamma(y) at waist level in mremlhr (iJ
- contamination survey point 1 OO* - gamma(y) contact in mremlhr 50 mrad - beta (p) reading in mrad/hr 2511 - neutron(@) in mremlhr
JOB PERFORMANCE MEASURE APPROVAL SHEET I.
Title:
Use RATS to Determine and Prioritize the Safety Functions ID Number:
JPM-A4RO Revision: -
0
- 11.
Initiated:
Developer I I I. Reviewed:
IV. Approved:
User Department Supervisor 1 /21 I05 Date Date Date
SUMMARY
OF CHANGES DESCRIPTION Developed new JPM All 8, Date R EVICHANG E 0
1 111 912004 (DAP) 2
JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number:
J P M-A4 R 0 Rev.
0 Task
Title:
Use RATS to Determine and Prioritize the Safety Functions System :
Administrative Time Critical Task:
Yes No x
Validated Time (minutes):
20 Task No.(s):
NUTIMS #OOO-05-226 Applicable To:
SRO X
RO X
PEO KIA No.:
2.4.21 KIA Rating:
3.714.3 Method of Testinq:
Simulated Performance:
X Act ua I Perfor ma nce :
Location:
Classroom:
X Simulator:
X In-Plant:
X Task Standards:
The examinee will correctly identify and prioritize the Safety Function Success Paths.
Required Materials (procedures,equipment):
Assessment Tree Form 2540-002 rev. 001, Functional Recovery Resource 2540 rev-21 page 8, Safety Function Status Checklist General
References:
EOP 2540, Functional Recovery READ TO THE EXAMINEE * * *
- I will explain the initial conditions. which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure wilt be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports. alarm acknowledgments, and log entries as if the evolution was actually being performed.
3
JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
J PM-A4 RO Rev.
0 Initiating Cues:
The crew has just transitioned to 2540. You are an extra license on shift. The SM has directed you to:
Determine the Safety Function Success Paths Prioritize all nine safety functions Submit your determination to the SM for comparison.
The plant conditions are as follows.
Initial Conditions:
At the completion of EOP 2525, the following conditions exist:
Power is at 2 x and stable RVLMS is 100%
CEAs 45 and 46 are fully withdrawn, all other CEAs are fully inserted A and B Charging Pumps are operating Both 6.9 kV buses are de-energized Bus 24C is energized from the A D/G (RSST is de-energized)
Bus 24D is de-energized (B D/G will not start)
Both DC buses are energized VA-10 and VA-20 are energized Facility 1 RBCCW and Service Water Pumps are operating A Auxiliary Feed Pump tripped when started The Terry Turbine will not start
- 1 SG level is 95 inches and lowering
- 2 SG level is 280 inches and slowly lowering
- I SG pressure is 485 psia and lowering
- 2 SG pressure is 820 psia and stable Pressurizer pressure is 1700 psia and slowly rising (Pressurizer level is 9% and rising very slowly)
CETs are reading 475 deg. F and slowly lowering (CET subcooling is 138 deg F and rising)
Loop delta-T is 36 deg F and stable Containment pressure is 27 psig and lowering Containment rad monitors are not in alarm and stable SJAE and blowdown rad monitors are not in alarm and stable Enclosure Building D/P is normal.
SIAS, CIAS, EBFAS, MSI, and CSAS have actuated A Containment Spray Pump flow is 1450 gpm.
RWST is 97% and lowering slowly Total SI flow is 0 gpm Simulator Requirements:
None 4
NOTES TO EXAMINER * * *
- 1 Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, When examinee states what hidher simulated action/observation would be, read the appropriate "Cue".
If necessary, question examinee for details of simulated actions / observations (Le. "What are you looking at?" or "What are you observing?").
Under NO circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
critical steps must be completed correctly.
2
- 3.
- 4.
5
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A4RO TITLE:
Use RATS to Determine and Prioritize the Safety Functions START TIME:
STEP 1 X Performance Steps:
Identify success paths to be used to satisfy each safety function using both of the following:
Resource Assessment Trees Safety Function Tracking Page GRADE X
Standards:
The examinee identifies the Safety Function Success Paths for the given plant conditions per attached Safety Function Status Checklist.
Comments:
STEP 2 Cue:
Give the examinee a copy of the Resource Assessment Trees and the Safety Function Tracking Page.
_--_1----__---55______________
X Performance Steps: Prioritize safety functions to de addressed first based on ALL of the following:
Safety functions which do not meet the Safety Function Status Checklist for the selected success path.
Safety functions for which the equipment to support the success path is not operating.
Safety functions for which success path three has been selected.
Safety functions for which success path two has been selected.
Safety functions for which success path one has been selected.
6
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A4RO TITLE: Use RATS to Determine and Prioritize the Safetv Functions GRADE-X Standards:
The examinee prioritizes the Safety FunctiolJ Success Paths for the given plant conditiolis per attached Safety Function Status Checklist.
Cue:
Comments:
When the examinee submits the completed Safety Function Status Checklist, this JPM is complete.
STOP TIME:
7
VERIFICATION OF JPM COMPLETION Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
JPM-A4RO Rev Date Performed:
Operator:
Evaluator( s) :
0 Time Critical Task?
Yes No Validated Time (minutes):
20 Actual Time to Complete (minutes):
Result of JPM:
(Denote by an 5 for satisfactory or a u for unsatisfactory)
Areas for Improvement:
8
Success Path SFSC Met Priority Safety Function
~
Reactivity Control Maintenance of Vital DC Power Equipment 0 pe ra ti ng Y
RC -2 Y
3 MVA-DC-1 Y
Y 6
Maintenance of Vital AC Power MVA-AC-2 Y
Y 4
IC-2 Y
Y Y
N Y
5 RCS Inventory Control RCS Pressure Control Y
7 PC-1 RCS and Core Heat Rem ova I Y O R N 1
HR-3 Containment Isolation CI-I Y
a Containment Temperature and Pressure Control CTPC-3 Y
Y 2
Containment Com bustible Gas Control CCGC-I Y
Y I
9 9
EXAMINEE HANDOUT JPM Number:
J PM-A4 RO Rev 0
Initiating Cues:
Initial Conditions:
The crew has just transitioned to 2540. You are an extra license on shift. The SM has directed you to:
Determine the Safety Function Success Paths Prioritize all nine safety functions Submit your determination to the SM for comparison.
The plant conditions are as follows.
At the completion of EOP 2525, the following conditions exist, Power is at 2 x and stable CEAs 45 and 46 are fully withdrawn, all other CEAs are fully inserted A and 8 Charging Pumps are operating Both 6.9 kV buses are de-energized Bus 24C is energized from the A D/G (RSST is de-energized)
Bus 24D is de-energized (B D/G will not start)
Both DC buses are energized VA-10 and VA-20 are energized Facility 1 RBCCW and Service Water Pumps are operating A Auxiliary Feed Pump tripped when started The Terry Turbine will not start
- I SG level is 95 inches and lowering
- 2 SG level is 280 inches and slowly lowering
- 1 SG pressure is 485 psia and lowering
- 2 SG pressure is 820 psia and stable Pressurizer pressure is 1700 psia and slowly rising (Pressurizer level is 9% and rising very slowly)
CETs are reading 475 deg. F and slowly lowering (CET subcooling is 138 deg F and rising)
Loop delta-T is 36 deg F and stable Containment pressure is 27 psig and lowering Containment rad monitors are not in alarm and stable SJAE and blowdown rad monitors are not in alarm and stable Enclosure Building D/P is normal.
SIAS, CIAS, EBFAS. MSI, and CSAS have actuated A
Containment Spray Pump flow is 1450 gpm RWST is 97% and lowering slowly Total SI flow is 0 gpm RVLMS is 100%
10
Ennova D ~ U Safety Functmn success Pat h Conditions hurcc notive Rc~ourcc nee A
Reactivity Control t
I I
CEA Insertion w c SUR ncgarwc a Reactor power c lo-%
ath
- a. Boratlon addition rate k > 40 g p.
If SI borabon addition rate
> 40 gprn, go du-to aaptance nitcna helow f
cQnuanl a.Boratwn addlrion rate IS > 40 gpm.
b Reactor power dropping.
c SUR negahve.
LmmL2 a.Relslor power <
- b. R e ~ 1 0 r power stable or droppin&
1 RC-3 I
OPS Form 2540-002 Rev. 001 Page 1 of 10
hnditions bum Motive Path Rcsourcc nee B-1 Vltal Dc Power Charger 480v BUS Z2F 1
.)
+
Statton Slation Battery Battery A
B Battery Charger B
I A
+
480v BUS Z2F 1
.)
+
Statton Slation Battery Battery A
B Battery Charger B
I A
+
a Mtsl DC Bus 201A t~ energzed.
Bus VAlOis energzed.
Aoccptancc Cn tcna sucscu Path OPS Form 2540-002
Safety Function success Path MVA-AC-1 RSST P
I 1
1 Conditions Path Acceptance Cntcria succcas Path Vital Vitpl 4.16 KV 4.16 KV Bus 24C Bus 24D t
v.
- a. Bus 24C is encrgucd.
- b. Viral DC Bw 201A L encrgued
- c. Fadity 1 RBCCW is operating.
d Facility 1 Service Wafer U operating.
- a. Bus 24D is encrgizod.
- b. Vital DC Bus 2018 U energized.
- c. Facility 2 RBCCW is operating.
- d. Facility 2 Senicc Water is operating.
I MVA-AC-1 1
M VA - AC-2 Emergency
! h ! d m d a Bus 24C is energized b Viral DC Bus 20lA IS cncrgucd c Fanhry 1 RBCCW IS opcratlng.
- d. Facihty 1 SCMCC Water IS opcmtlng.
clmimR2 a Bus 24D is cncrgzcd b Vila1 DC Bus 2018 u cnergmd c Faulity 2 RBCCW IS operaung
- d. Faulity 2 SCMCC Water IS opcratlng.
I MVA-AC-2 I MVA-AC-3 Bur 34N34R V
Unit 3 Power i2Q&mnl a Bua 24C IS cncrgmd.
- b. Vital DC Bus 20lh IS encrgued
- c. Facihty 1 RBCLW is opcratlng.
d Fanlity 1 Sums Water is operatmg l2lduml a Bus 24D IS energmd b Vital DC Bur 2018 IS cncrgucd c Fdrty 2 RBCCW IS operalurg.
- d. Fadh, 2 SCIVICC Water is opcramg I
MVA - AC-3 OPS Form 2540-002 Rev. 001 Page 3 of 10
Safety Function success Path Reaoura Tree
+
I 1c cvcs I
I I
Conditions Source Motive Path Acceptance criteria Charging Charging Pump A Avail Avail Avail t
t t
I Boric Aud Gravity GWiW Feed t
t W
a Pressurizer lcvcl is > 20%.
- b. RCS subcooling is 2 minimum subcooling lme of Ihe,
PTT CUIM.
v Cntmt Emcrg Sump Level Rising Lvl > 9% n arc not met. then all avulabk chargrng pumps arc operating.
not met, thwl L E I flow u mthin SI Ilaweurvc.
w h n 51 flow curve.
- b. If SRAS har not occurred and LPSI termmation mtena arc
Id. Reactor vewl level is 2: 7%.
IC. Reactor vessel level is 2 43%.
1 suca.ss I
1 I
I Path I IC-1 I 1 IC-2 J OPS Form 2540-002 Rev 001 Pare 4 of 10
Safety Functwn suaccu Path All of the PC-1 paths should be evaluated to dctcrminc if the cquiprncnt is required to maintain the PC-1 RCS Pressure Control S u b l c d 1
a Conditions jource Motive Pzr Lvl 20%
I v
+
C C
> c VCT BAST RWST Avdable Lvl > 10%
Lvl z 9%
\\
v 4
> 40 gpm, go directly to acceptance 3
Rvr Avail ldght On
- a. Rcssurizer pressure U within the Pm curve limits.
I I
PC-I
safety Function IfHPSlfloor>
critui.bPlow SI a w CWC, eo directly to acceptance suecess Path IfLPsIflOW>
cntelia below SI flow w e go.
diectly to aczepunce Conditions source POW Rvr Avad Molive Path sump Level Rising Lvl w 9%
I&]
Lvl > 9%
f a 1fSRASbmoccurrsd;rodHPSI
- b. If SRAS hu not occurred and LPSI thmttlwbtop aitcria not met, then all availablc charging pumps arc operating.
termination aitcria are not ma, then P S I tkw is within SI flow curve.
PC-2 L
- a. Pressurizer pressure is within the Pm NIVC limits.
OPS Form 2540-002 Page 6 of 10
, : *wa6rr k r
' F ( < i,
Rev. 001
safety hncllon Success Pa: h
- A: leas: one steam generator WR level is l e u :han or q u a l :o 70 mches.
Conditions source Motive
arc not met, then all avallable &rgtng pumps are opcratmg
- % If SRAS has not occurred and LEI tcrminaiim u~teria arc not met. then LPSI llow IS wthm SI flow curve d IF tWSI throttldr:op mtcna arc not me:. then HPSI flow IS wthm SI flow curve
- a. A: least one SG Lcvel ir within 40 to 70% or being restored.
- b. If RCPI are operating. then loop delta T it <1O'E
- d. TH and CET temperature is < 600°F
- e. RCS subcooling is 2 minimum subcoolmg linc ofthe Pm CUNC.
- f. Reactor vessel level is 2 43%.
i.;o ADVs
'ath SO Available for Heat Removal Dumps ADVs f
1
- a. At leas: one SG Level is wthin 40 :o 70% or being
- b. restored.
CETtempcrature IS e 700'E E. If SRAS har not occurred and HPSI throt:k/stop criteria
- d. If SRAS hac not occurred and LPSl tmmnation criteria
- e. If HPSI throttldsiop criteria arc not mct. then HPSI fluw is are not met, then all available charging pumps are opcnhng.
arc no: met. then LEI flow is wilhin SI Ow curve.
within SI flow NWC.
HR-2 Kl Once-Through-Page 7 of 10
Safety Function succeu Path Condttlons sourcc Motive Path Acceptance Criteria s u m r r Path I
I Remote Manual Valve Operation CIAS Resource Ree Lou1 valve Opention AutomaticlManual Containment Isolation Normal Containment ALLof thc following:
- 1. Onml prmure < 4.42 prig.
- 2. Radiation monitors insiic amnt h.ve no unuplained alums and no uuplainud riw.
- 3. Radiationmonitoring ouraide cntmt have no unexplained alarms and no unexplained rises.
- 4. Seam phnt radiation miton have no unexplained alarms and no unexplained riw.
t Normal Containment Conditionr Both of the Abnormal Containment conditions should he evaluated to determine if thc quipment is required to maintain the CI-1 Acceptance Criteria.
Abnormal Containment i
t w
/ L o C A / E S D E Y ANY of the followino:
- 1. Cbnt praswe a 4.42 pig.
- 2. Radiation monitorsinbide cntmt have unexplained alarm or unexplained rises
- 3. Radiation monitoring oulsidc mlmt have uncxplaincd alarmror unexplained rises.
z
. Steam phnt radiation monilws have uncxp1am.d alum and unexplained nses.
t Mort Affected SG is hlated 1
~~~~~
- a. ONE of the following:
- Steam plant radiatim monitors have no unuplaincd alarms and no unupluncd rim.
If a SGI-R cxisu, all release paths from most affected SO to the environment not hcing urcd for planned release arc isolated
- b. Contanmcnt preuurc < 4.42 psi4.
c Radiation monitors wide containment have no unrqlained alarms and no unuplatnrd k s.
- d. Radiation mnitors outside conlainmen1 have no unexplained alarms and no unexplained rises.
- e. SG pressure c 920 psia.
- a. ONE of the following:
- Steam plant radiabon monitors haw no uncxplamcd alarms and no unexplained riscs.
If a SGl'R exists, all relcnrc paths horn most affected SG to the environment not being used for planned rcleax are isolated
- b. Each contninment penetration required to be closcd for w e n t plant mnditiotu has an isolation valve dosed.
%%on Sufcers Path Conditions Source Motive
'ath 4cceprance Xtctia lUceCY
'ath Facility 1 CAR FUU Power Avail Resource 'Ree Containment Tcmpcrature and Prcrsure Control The determination for the (JIPC success path should be t
I I
Fscitity 2 CAR Fans Power Avail Containment Fans (Nonnal Mode)
Containment
< 4.42 psig
- b. Containment pressure < 4.42 psig.
'7' mc-2 Containment Fans (Emergemy Mode)
Contaiamcnt R c u w Z 4.42 psig
< 9.48 p i g Facility 1 Facilify 2 CAR CAR Fans Fans h e r Power Avail Avail
+
+
- a. L 2 CAR fans operahog in emergency
- b. Containment temperature c 190'E
- c. Containment pressure< 9.48 psi&
mode.
Containment Containment 2 9.48 psig Lvl > 9%
Qltml Emerg Sump L N c l One Facility CAR Fans Power Avail
- b. Containment pressure IS < 51 pig.
- a. L 2 CAR fans operating in emergency
- h. mode.
OneCSpumpwith 5: 1300gpm.
- c. Containment pressure is < SI psig.
1
~-
I CTPC-3 I
safety Function SufcwS Palh Conditions Motive Path Acceptance criteria succcss Path Containment Combustible Gas Control Safety Function is considered satisfied unril the hydrogen analyzer can be placed in service and the warm up is complete.
Resource Tree P.
Containment Combustible t
CCGC-I PkuiveRiydrogen Recombiners HZ < 1.4%
12 2 1.4%
I L
a Containment hydrogen concentration
< 1.4%.
a All available hydrogen recombinen
- b. Containment hydrogen concentranon cnerpucd c 3.8%.
I c c
a Hydrogen I
Purgc
- a. Hydrogen purge system operating.
ccoc-2 OPS Form 2540-002 Rev. 001 Pane 10 of 10
I Millstone Unit 2 I
EOP2540 Revision 21 RCS and Core Heat Removal Containment Isolation Containment Temperature and Prcssure Control Con tainrnen t Combustible Gas Control I
Functional Recovery HR-1 SI not operating HR-2 ST operating HR-3 0-T-C cI -
CTPC-1 CARs (Normal)
CI'PC-2 CARs (Emerg) m c - 3 Containment Spray CCGC-1 Hydrogen Rccombi ners CCGC-2 Hydrogen Purge Au toma tic/Manual Page 8 of 30 Safety Function Status Checklist 1 4.0 SAFETY FUNCTION STATUS CHECKLJST
~
~-
EOP ENTRY TIME w
I Millstone Unit 2 I
EOP2540 Revision 21 RCS and Core Heat Removal Containment I sol at i on Containment Temperature and Prcssure Control Containment Combustible Gas Control Functional Recovery PC-3 PORVs HR-1 SI not operating HR-2 SI operating HR-3 0-T-C I
CI-1 Automatic/Manual CTPC-I CARs (Normal)
CTPC-2 CARs (Emerg) mc-3 Containment Spray CCGC-1 Hydrogen Recombiners CCGC-2 Hydrogen Purge I
Page 8 of 30 I
Safety Function Status Checklist
, i.
JOB PERFORMANCE MEASURE APPROVAL SHEET I.
Title:
SRO Review and Approve a Radioactive Liquid Waste Release Permit ID Number:
JPM-A3SRO Revision: -
0 I I.
Initiated:
Developer II I. Reviewed:
IV. Approved:
User Department Supervisor d
Nuclear Traini Supervisor 0 1 /27/05 Date Date I 3 / d
//
Date
JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number:
JPM-A3SRO Rev.
0 Task
Title:
SRO Review and Amrove a Radioactive Liauid Waste Release Permit System:
Radiation Control Time Critical Task:
Yes No X
Validated Time (minutes):
10 Task No.(s):
NUTIMS # 119-02-026 Applicable To:
SRO X
2.3.6 K/A Rating:
2.113.1 Method of Testing:
Simulated Performance:
X Actual Performance:
Location:
Classroom:
X Simulator:
X In-Plant:
X Task Standards:
At the completion of this JPM, the examinee will have discovered a plant operating condition that will NOT allow authorizing a radioactive liquid waste discharge.
Required Materials
[procedures, eq ui Dment 2:
0 SP 261 7A Aerated and Clean Radioactive Liquid Waste Discharges Chem Form 2864-1, Millstone Unit 2 Liquid Discharge Permit Number 2000 General
References:
SP 2617A, Steps 4.2.6 and 4.2.7 (Rev. 027-05)
READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.
2
JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
JPM-A3S Rev.
0 Initiating Cues:
As the SM, you have directed the Radwaste PEO to make preparations to discharge the AWMT. Perform the required actions to authorize the discharge.
Initial Conditions:
Simulator Requirements:
No other radioactive discharges are in progress.
SP 2617A, section 4.2; steps 4.2.1 through 4.2.5 have been completed.
Chemistry sample results are acceptable.
RM-9116 is operable.
AWMT level is 89%.
The plant is in MODE 5 preparing the RCS for refueling.
2 Circulating Water Pumps operating, 2 Service Water Pumps operating.
It is one hour past high tide.
N/A NOTES TO EXAMINER * * * *
- 1.
Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, When examinee states what hidher simulated action/observation would be, read the appropriate "Cue".
If necessary, question examinee for details of simulated actions I observations (i.e. "What are you looking at?" or 'What are you observing?").
Under NO circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
critical steps must be completed correctly.
- 2.
- 3.
4 3
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A3SRO TITLE: SRO Approve a Radioactive Liquid Waste Release Permit START TIME:
STEP 1 GRADE -
- Performance Steps: When Chem. Form 2864-001 (Discharge Permit) is obtained from Chemistry Department, SM review and authorize Chem. Form 2864-1, Millstone Unit #2 Liquid Discharge Permit No. 2005, for discharge.
- Standards:
SM should review and initial Chem Form 2864-001. I f examinee determines that the discharge should NOT be made at this point, he may elect NOT to initial the permit.
Cue:
0 Provide Chem. Form 2864-1 to the examinee.
0 If the examinee determines that the discharge CANNOT be authorized, ask, Why?
Comments:
STEP 2 X
Performance Steps: When Chem. Form 2864-001 (Discharge Permit) is authorized, refer to OPS Form 261 7A-001 and perform the following:
Review plant conditions and authorize discharge.
Ensure no other radioactive discharges are in progress (other than SG blowdown) and initial.
If discharge is to be performed with radiation monitor not OPERABLE, Ensure 2 independent samples have been analyzed for AWMT, as specified on Chem Form 2852-1, Unit 2 Liquid Radwaste Effluent Rad Monitor Inoperative, and Initial.
GRADE Standards:
Examinee reviews plant conditions and:
X determines that the discharge CANNOT be authorized X
because the actual dilution flow rate (with 2 circ Water and 2 Service Water Pumps operating) is less than the Required Dilution Flow Rate on the Discharge Permit.
Cue:
If the examinee determines that the discharge CANNOT be authorized and does NOT provide a reason, ask, Why?
Comments:
Comments-After this step is completed, the JPM is considered complete.
STOP TIME:
4
VERIFICATION OF JPM COMPLETION Job Performance Measure No.
JPM-A3SRO Date Performed:
Operator:
Evaluator(s):
Rev.
0 For examinee to achieve a satisfactory grade, critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactorv arade.
Time Critical Task?
Yes No X
Validated Time (minutes):
10 Actual Time to Complete (minutes):
Result of JPM:
(Denote by an 5 for satisfactory or a u for unsatisfactory)
Areas for Improvement:
5
EXAMINEE HANDOUT JPM ID Number:
JPM-A3SRO Initiating Cues:
As the SM, you have directed the Radwaste PEO to make preparations to discharge the AWMT. Perform the required actions to authorize the discharge.
Initial Conditions:
0 0
No other radioactive discharges are in progress.
SP 261 7A, section 4.2; steps 4.2.1 through 4.2.5 have been completed.
Chemistry sample results are acceptable.
RM-9116 is operable.
AWMT level is 89%.
The plant is in MODE 5 preparing the RCS for refueling.
2 Circulating Water Pumps operating, 2 Service Water Pumps operating.
It is one hour past high tide.
6
SIGNATURE ON FILE Approved 09-05-03 09-12-03 Approval Date Effective Date MILLSTONE UNIT #2 LIQUID DISCHARGE PERMIT NO. 2000 (SP4307 5)
Tank................ : AWMT Minimum Recirc Time..... : 0.5 hr w/ mixer; 4.0 hr w/ pump Date/ time sampled......... : [Today]
Date/time on recirc........ : [Today]
(AWMT limit = 45 ppm; CWMT limit = 22.5 ppm) 07: 15 06:25 Sampled by...... :
c, TSS (ppm).....................
8.8 Boric acid conc (ppm)...... :
237 pH
(>2 pH <12.5) 8.8 Eff. Monitor Blcg = (cpm)..:
1.65E+04 Isotope MN-54 (20-57 co-58 co-60 AG 1 10hl SB-125 XE-133 CS-134 CS-137 H-3 Totals 2 circulating water pumps must be in operation during this discharge During Unit 2 shutdown a minimum dilution flow rate of 20,000 gpm is allowable with the discharge rate limited to 30.5 gpm.
Activity MPC Activity/ MPC (u Ci / ml)
(u Ci / ml) 4.766E-06 3.166E-07 4.45 1E-06 1.032E-04 9.981E-06 7.137E-06 3.0953-06 7.43 1E-07 2.167E-06 3.780E-02 1.3283-04 1.000E-04 4.000E-04 9.000E-05 3.000E-05 3.000E-05 1.000E-04 9.000E-06 2.000E-05 3.000E-03
(@I 4.766E-02 7.9 14E-04 4.945E-02 3.442E+00 3.327E-0 1 7.137E-02 8.257E-02 1.084E-0 1 1.260E+O 1 1.673E+01
((2) N o gasses or H-3 included in totals, however, H-3 is in Activity/MPC col.
Diluted gas concentration (uCi/ml) = 3.5 17E-09c L
L INIT Minimum recirc time is Administrative quarterly release limit (Ci)............. :
Total acti\\Tity released this quarter (Ci)................. :
Estimated volume this discharge..........................
Estimated activity this discharge..........................
Est total activity released this quarter (Ci)............ :
........ : 0.5 hr w/mixer; 4.0 hr w/pump 5.000E-02 3.490E-03 4000.
2.01 1E-03 5.50 1E-03 (1) Reduction factor.............................................
5.9763-02 (2) Required dilution flow rate.............................
308000.
(gpm) 3 circ water, (3) Normal rate limit (flow rate =#1*#2*0.1).......... :
(5) Liquid effluent monitor alarm setting 2 service water pump(s) 350 kpm)
(ALARM).... :
(CPW
( e m )
Maximum approved rate.......................................
(Authorization required to exceed normal rate limit.)
Source check performed.......................................
S.M. init DISCHARGE DILUTION INTEGRATOR
DATE/TIME FLOW RATE (gpm)
Start End READING DISCHARGE OPERATOR (4*DIFF=gal)
RATE (gpm)
Liquid eff monitor reading 15 min after start of discharge (CP4 (ml)
Total licluicl waste discharged =
(gal) -* 3785 Liquid eff monitor Bkg reading after flush (CPm)
S M / U S Date Time Chem Form 2864-1 Rev. 1 Page 1 of 1 Evaluation of Rad Monitor Response Based on lsotopic Mix (Sheet 1 of 1 )
Isotope Activity (pciicc)
CO-60 I#. 032 E 4
/
Date:
/ Ody Tank Being Discharged: J?Mql YO of Total Activity 75.9 NOTE Consider gamma yieJd of each isotope before calculating response factor.
Latest RM response during Cs-137 calibration: /,9O E+ 0 g cpm/pCi/cc Current R M response factor based on isotopic mix:
= [ 1 +(%C0-60/ I OO)]X[RM response to Cs-I371
= [1+75) 9 / I O O ) ~ X [ ~ - ~ O E B c p m / p ~ i / c c ~
Current RM response factor based on isotopic mix =
3.34 E g cpm/pCi/cc Information SP 2864 53 O S 5 5 Rev. 00.5-01
09/05/03 Approval Date 09/12/03 Effective Date Millstone Unit 2 Liquid Discharge Permit Number T:i n k............. :
Sampled by.... :
Datehime sampled:
Date/time on recirc:
Minimum recirc time is.:2.0 hr w/mixer; 7.7 hr w/pump (CWMT) 0.5 hr whixer; 4.0 hrw/pump (AWMT)
TSS (ppm).:
Boric acid concentration (ppm) =
Eff. Monitor Bkg pH.:
(AWMT limit = 45 ppm: CWMT limit = 22.5 ppm)
(2<pH < 12.5) 2 circulators must be in operation during this discharge During Unit 2 shutdown a minimum dilution flow of 20,000 gpm is allowable with the discharge rate limited to 30.5 gpm.
I Isotopic Data found on attached form Manual Discharge Calculation Worksheet Dilutcd gas concentration (pCiiml) =
INIT (limit : 1.100E-2)
Administrative Quarterly Release limit (Ci)............. : 5.OE-02 Total activity released this quarter (Ci)....................
Estimated volume this discharge (gal).....................
- Estimated activity this discharge (Ci)......
Estimated total activity released this Quarter (Ci).:
Estimated Activity values do not include tritium (1)
Reduction factor...................
-Circ water, __
S.M. Init.
(2) Required dilution flow rate..
(gpn1)
(epm)
(4) Liquid effluent monitor alert setting:................. :
(CPm)
(3)
Flow rate limit...( #l * #2
- 0.1)..........................
( 5 ) Liquid effluent monitor alarm setting:................. :
(CPm)
Maximum approved rate.........................................
k p m )
(authorization required to exceed normal rate limit).
Source check performed................. (y es/no)..................
DISCHARGE*
- DILUTION DATE TIME FLOW RATE (gpm)
Oper.
INTEGRATOR SP 2864 - 001 Rev. 002 Page 1 of 2
1
~
~~
~~
~
Liquid eff. monitor reading 15 min. after start of discharge Liquid effluent monitor reading after flush =
(CPm)
(gal)
- 3785 =
(ml)
~
I I
Total liquid waste discharged =
( CPm )
S M i U S.
Date:
Time:
SP 2864-001 Rev. 002 Page 2 of 2
JOB PERFORMANCE MEASURE APPROVAL SHEET I
Title:
Classify the Event ID Number:
J P M-A4S R 0 Revision:
0 II.
Initiated:
R. J. Ashey Developer I l l.
Reviewed:
IV. Approved:
User Department Supervisor d
Nuclear Trai g Supervisor 112 1 I05 Date Date
SUMMARY
OF CHANGES All 8 Date DESCRIPTION REVCHANGE 2
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A4SRO TITLE: Classifv The Event JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number:
JPM-A4SRO Rev.
0 Task
Title:
Classify the Event System:
Admin Time Critical Task:
Yes No X
Validated Time (minutes):
20 Task No.(s):
NUTIMS # 303-05-091 Applicable To:
SRO X
2.4.41 WA Rating:
2.3/4.1 Method of Testinq:
Simulated Performance:
Act u a I Perform an ce :
X Location:
Classroom:
X Simulator:
X In-Plant:
X Task Standards:
At the completion of this JPM the examinee will determine the classification of the scenario to be an Alert/CI.
Required Materials (procedures, equipment):
MP-26-EPI-FAPOI-001 Control Room-Director of Station MP-26-EPI-FAP06-002, Rev. 003 EAL Tables Emergency Operations (CR DSEO)
MP-26-EPA-REF02 MP2 EAL Technical Basis Document Genera I References :
EP-MP-26-EPI-FAPOG Rev. 006 Classification PAR READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.
3
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A4SRO TITLE: Classifv The Event JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
J P M -A4S R 0 Rev.
0 Initiating Cues:
0 You are the Shift Manager.
0 Classify the event you have just completed on the simulator.
o o
You are to consider all plant conditions during the scenario.
Your classification should reflect the most severe classification level reached.
Initial Conditions:
As observed during the previous simulator session.
Simulator Requirements:
Simulator scenario that was run for the elduation. (ES04LI 1)
NOTES TO EXAMINER * * * *
- 1.
Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, & critical steps must be completed correctly.
2.
When examinee states what hidher simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question examinee for details of simulated actions / observations (i.e. "What are you looking at?" or "What are you observing?").
- 4.
Under circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A4SRO TITLE: Classify The Event START TIME:
STEP 1 X Performance Steps:
GRADE X
Standards:
Examinee utilizes EPI-FAP02 EAL Tables and classifies the simulator event that was just completed.
Examinee determines the classification is Barrier Failure, BA 1; Alert C-1.
Based on RCS Barrier, RCB4, Reactor Coolant leak
> CVCS capacity AND entry into EOP-2534. Steam Generator Tube Rupture or EOP 2540, Functional Recovery, to address Steam Generator Tube Rupture.
Cue:
When asked, provide requested reference material.
Comments:
Examinee will have the use of the other reference material, including: MP EPI-FAPO1 Control Room - Director of Station Emergency Operations (CR DSEO), MP-26-EPA-REF02 MP2 EAL Technical Basis Document.
Comments:
After this step is completed, the JPM is considered complete.
STOP TIME:
5
VERIFICATION OF JPM COMPLETION Job Performance Measure No.
JPM-A4SRO Rev.
0 Date Performed:
Operator:
Eva I u a to r( s) :
For examinee to achieve a satisfactory grade, Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
critical steps must be completed correctly. If task is Time Critical Task?
Yes No Validated Time (minutes):
20 Actual Time to Complete (minutes):
Result of JPM:
(Denote by an for satisfactory or a u for unsatisfactory)
Areas for Improvement:
6
EXAMINEE HANDOUT JPM ID Number:
JPMA4SRO Classify the Event Rev. 0 Initiating Cues:
0 You are the Shift Manager.
0 Classify the event you have just completed on the simulator and provide the basis for your answer.
o You are to consider all plant conditions during the scenario.
o Your classification should reflect the most severe classification level reached.
Initial Conditions:
As observed during the previous simulator session.
Classification Level NRC:
State:
Has i s :
7
MILLSTONE 2 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE gencg Conditions Will Occur Within 2 CTMT BARRIER IhIMINENT -
NDICATORS Hours THREE BARRIERS
- AFETY FUNCTION
- TATUS/
UNCTIONAL lECOVERY
- ORE EXITTC
.EMPERATURES
'RESSURE RADIATION WATER LEVEL JUDGEMENT o Turnaround in Safety System Perform; 7x7 m
FUEL CLAD BARRIER Not Applicable POTENTIAL LOSS p
NO RCS Heal Removal Method Meels SFSC Crllsria In S e ~ w
> 15 Minutes AND Shutdown Cooling Syslem IS NOT
-1 r;l Core Ex81 Thermocouple Readings > l3W F CJ 3
Cora Ex11 Thermocouple Readings > 800 F POTENTIAL LOSS RM.824018241 Reading,
300 Rihr R$&~4;~@+241 Rsadlng,
5 Rlhr W\\thOul RCS Release At Least 5% Fuel Clad Damage As Determined By Core Damage Estimate Dose Rats at One Foot from Unpressurized RCS Sampls NOI Applicable L 28 mR1hr'ml I POTENTIAL LOSS ]
pq Not Applicable POTENTIAL LOSS RVLMS Reading 1 0 %
m Any Condition For WhlCh Judgement Ind8cates LOSS 0' Potential Losa 01 Fuel Clad Barrier Due to lmmmenl Barrier Degradat on Based On Current Safety System Petlormance Barrier Slatus Indeterminate Degraded Fisrlon Barrier Mon+~r#rig Capability Making e is Expected AND Escalation to General Em RCS BARRIER Uncontrolled RCS Cooldown AND RCS PressureTempersture To the Len 01 the PTS Limit 200 F Subcooling Marmum Cuwe NO RCS Heat Removal Method Meets SFSC Criteria
> I 5 Minutes AND Shutdown Cooling System Is NOT I" SeMce P E I RCS Subcooltng < 30 F POTENTIAL LOSS Not Applicable Not Applicable POTENTIAL LOSS Uncontrolled RCS Pressure Decrease and Increasing Containment Radiation Monrlor~
Reanor Coolanl Leak > CVCS Capacity AND Entry Into EOP.2534. Steam Generator Tube Rupture or EOP 2540 Functional Recovery to Addieas Slsam Generator Tube RUP'U'n 1 POTENTIALLOSS I Reanor Coolant Leah > CVCS Capacity AND Enlry Into Reanor Coolant Leak Rate >capaclW 01 One 11) charging pump AND 5 CVCS Capacity AND ANY of Ihe lollowing En!? Into EO? 2 S V Sicrm Gcncrrtw The Ruplurc Entry In!u AOP 2569. S t c m Gcnerdrar Tube Leak Emr) l n t ~
EOP 2510. R n ~ t t o n d i Rcro\\erv. lo Addres Steam Gcneraior luhc Kupnirc EOP-2525. Standard Post Tnp Actions RM-8Z4O18241 Reading.%
5 Rlhr Without Fuel Clad I POTENTIALLOSS I Not ApplNrabIe Any Condition For Which Judgemenl lnd8cales Loss or Potent8al Loss of RCS Barrier Due to Imminent Barrier Degradation Eased On Current Safely System Performance Degraded Flsslon EarrNer Monalorsng Capab#l#ly Making Barrlsr Status lndeterm~nate Not Applicable
[ POTENTIAL LOSS I Core Exit TC Temperature Readings >t3W'F AND
!I DO NOT Decrease Within 15 Mlrrutes CNB2 Rapid Unexpla ned CTMT Presswe Decrease NO CTMT Pressure Increase When Expectat on Exists CTMT Pressure > I O PSlG AND Increasing CTMT ti2 Concentration 2 4%
4 I POTENTIAL LOSS 1 4 a 3 ;;,;g~ry to Secondary 1 Tech Spec bmits and EITHER Non~solab18 Steam Release liom Anecled SIG to environmenl Prolonged Release From Anected SIG to Environment When Used lor Cooldown (see bass tor descr8pllon 01 prolonged release) 1 F~IIUIB 01 BOTH 1sotal~on valve8 AND a Palhwav to Ihe 3 Environment E m ~ t r 1 POTENTIAL LOSS Entry Into EOP.2532 Loss 01 Primary Coolant AND Ons\\te Dose Plume Rate L I O Times RM.824018241 Rsadlng 11 Ralease 1s to CTMT POTENTIAL LOSS RM 8240'8241 Reading z 1 200 R,hr At Least 20% Fuel Clad Damage A i Determined By Core Damage Estimate No CTMT Sump Level Increase When ExpectatlOn INS1 POTENTIAL LOSS Not Aoolicsble Any Condition Far Which Judgement Ind8cates LOSS 0' Polent~al Loss 01 CTMT Barrier Due lo
+
Imminent Eamer Degradation Based On Current Safety System Perlormance Degraded F
~
s s
~
Barrier Maniloring Capabitity Marlnq Eamer Status lndeleimfnate MORE THAN ONE BARRIER AFFECTED I
NO I
TWO BARRIERS ONLY ONE BARRIER AFFECTED UNUSUAL EVENT DELTA - ON E
Y l d U I l z l i l O q Approval Date Effective Date Control Room - Director of Station Emergency Operations (CR-DSEO )
NOTE If the applicable unit is Unit 1, the Unit 2 SWCFH will classify the event and become the CR-DSEO.
~~
Section A: Emergency Response Immediate Actions
- 1. Evaluate the conditions using EPI-FAP06, Classification and PARS.
0 Notify the SDO and Emergency Communicator to report to the control room and 0 Review the EAL tables:
provide a briefing.
For Unit 1, EPI-FAP06-001 For Unit 2, EPI-FAP06-002 For Unit 3, EPI-FAP06-003 0 Evaluate the status of the fission product barriers.
- 2. Declare the emergency.
0 Announce the emergency declaration level and time to the CR staff and assume the role of CR-DSEO.
NOTE Offsite notification shalI be accomplished within 15 minutes of an emergency event classification.
0 Direct the Emergency Communicator to initiate offsite notifications per EPI-FAP07, Notifications and Communications.
- 3. Go To the applicable section and perform the immediate actions.
0 Unusual Event........................ Section B 0 Alert....................................... Section C 0 Site Area Emergency............. Section D Cl General Emergency................ Section E MP-26-EPI-FAPO 1 -00 1 Rev. 002 Page 1 of 15
I I
NOTE The CR-DSEO may choose to activate or partially activate the Emergency Response Facility (Facilities) for an Unusual Event. This can be done via individual pager notification, phone call, etc.
I Section B: Unusual Event Immediate Actions
- 1. Notifications 0 Notify the unaffected unit control room of the event.
NOTE
- 1. During a security event, it may not be advisable to sound an alarm or make a PA announcement.
- 2. StateAocal authorities may deploy offsite responders such as the National Guard or StateAocal police to the Millstone Station in response to a security-related threat. The State of CT and Waterford Police will be responsible for protective measures for these forces, as necessary (i.e., providing and issuing potassium iodide (KI) in a timely manner? maintaining doses A L M A, and upgrading exposures, issuing and tracking dosimetry). The SSS will notify the control room of any protective actions put in place.
3, For an emergency went, radiological or non-radiological, that does not involve a security threat, the station would consider offsite responders located onsite as non-essential to the event and evacuate them fiorn the site. However, they are still under the States authority and the State may require they stay on site.
0 the event involves a situation where site personnel should be sheltered, Refer To EPI-FAP08, Evacuation and Assembly, She1 tering, and perform actions.
R E sheltering actions are not being conducted, perform the following:
Attention all personnel; attention all personnel. An Unusual Event has been declared at (Unit ##
) due to (briefdescription of event
). Members of the SERO monitor your radiopager for further instructions and information. All other personnel continue with your present duties.
MP-26-EPI-FAPOI-001 Rev. 002 Page 2 of 15
Section 8: Unusual Event lnunediate Actions 0 a partial activation is being conducted, announce the following:
A partial activation of SERO is being conducted. All (EOF)(TSC)(OSC) members report to your designated facilities.
0 Repeat the PA message.
Cl Log time of announcement on EPI-FAP 15-012, SERO Log Sheet.
0 Review and approve the Incident Report Form (IRF) for transmittal.
0 Refer To EPI-FAP15-001, DSEO/ADTS Briefing Sheet, and complete.
0 Obtain information &om the SSS of offsite responders (i.e., National Guard) reporting to the site.
0 E the emergency event occurs off-hours (6:OOpm to 4:OOam) or on weekends, direct SDO to voice-record EPI-FAP15-001 information and fax completed form to EOF and TSC.
- 2. NRC Notification 0 Direct the SDO to notify the NRC via the ENS.
D Verify the Emergency Communicator or SDO has contacted the resident inspector.
- 3. Loss of Power R E event is Loss of Off-Site Power (LOP), evaluate what loads are being carried and what loads are necessary.
0 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the LOP, evaluate the need to order emergency diesel generator fuel to extend on-site capacity and direct on-shift Ops Procurement Coordinator or Motor Pool Coordinator to order fuel, as required.
- 4.
no upgrade to classification is warranted, Go To Section F, Routine and Follow-up Actions.
I-26-EPI-FAPO1-00 1
Rev. 002 Page 3 of 15
~~~
Section C: Alert Immediate Actions
- 1. Notifications Ll Notify the unaffected unit control room of the event.
Cl Request Security to restrict site access and have them notify Waterford Police and CT I State Police to prepare for a precautionary dismissal, as appropriate.
NOTE
- 1.
- 2.
- 3.
Hazardous conditions or Security-related events may impact the ability to move personnel. Ifthese conditions exist, it may be better to shelter personneI on site.
During a security event, it may not be advisable to sound an alarm or make a PA announcement.
Statedlocal authorities may deploy offsite responders such as the National Guard or Statdocal police to the Millstone Station in response to a security-related threat. The State of CT and Waterford Police will be responsible for protective measures for these forces, as necessary (i.e., providing and issuing potassium iodide (KI) in a timely manner, rnaintainhg doses ALARA, and upgrading exposures, issuing and tracking dosimetry). The Manager of Security (MOS)/SSS will notify the CR DSEO of any protective actions put in pIace.
For an emergency event, radiological or non-radiological, that does not involve a security threat, the station would consider offsite responders located onsite as non-essential to the event and evacuate them from the site. However, they are still under the States authority and the State may require they stay on site.
0 E the event involves a situation where site personnel should be sheltered, Refer To EPLFAPO8, Evacuation and Assembly, Sheltering, and perform actions.
0 WHEN appropriate, announcc termination of sheltering.
0 WHEN appropriate, conduct fill SERO activation and precautionary dismissal, as applicable.
0 E sheltering actions are not being conducted, perform the following:
0 Activate the outside speakers.
0 Review the wording for the station notification message and announce the following over the station PA system:
Attention all personnel; attention all personne!. An Alert has been declared at (Unit #
) due to (brief description of evenf
- 1.
MP-26-EPI-FAPO1-001 Rev. 002 Page 4 of 15
Section C: Alert Immediate Actions 0 the designated emergency response facilities available, announce the following:
All on-duty SERO members report to your designated emergency response facility. All off-duty SERO members report to your designated Assembly Area.
0 either the EOF the TSC is unavailable, announce the following:
The (EOF) (TSC) is unavailable at this time. At! on-duty SERO members who report to the (EOF) (TSC), report to your backup focations. All off-duty SERO members report to your backup Assembly Area.
0 Repeat the PA message(s).
0 Log time of announcement on EPI-FAP15-012.
0 Review and approve the Incident Report Form (IW) for transmittal.
0 Refer To EPI-FAP15-001, DSEO/ADTS Briefing Sheet, and complete.
0 Inform the DSEO/ADTS of offsite responders (i.e., National Guard) responding to the site.
0 E the emergency event occurs off-hours (6:OOpm to 4:OOam) or on weekends, direct SDO to voice-record EPI-FAP 15-001 information and fax completed form to EOF and TSC.
- 2. NRC Notification 0 Direct the SDO to notify the NRC via the ENS.
CI Verify the Emergency Communicator or SDO has contacted the resident inspector.
- 3. Precautionarv Dismissal
\\ / c A u T I o N V Precautionary dismissal may NOT be desired during certain events (e.g., Security-related).
These actions should be reviewed periodically and implemented as quickly as possible after the threat has been resolved.
0 E precautionary dismissal is not desired due to the nature of the event (eg., Security-related, weather), consider postponing until threat has been resolved.
Ll no constraints exist, Refer To EPI-FAP08, Evacuation and Assembly, and conduct a precautionary dismissal, as events warrant.
MP-26-EPI-FAPO 1-001 Rev. 002 Page 5 of 15
Section C: Alert Immediate Actions offsite responders (i.e., National Guard) are onsite and considered non-essential to the event, request the SSS/MOS evacuate them also.
- 3. E no upgrade to classification is warranted, Go To Section F, Routine and Follow-up Actions.
MP-26-EPI-FAFO1-00 1 Rev. 002 Page 6 of 15
Section D: Site Area Emergency Immediate Actions
- 1. Notifications 0 Notify the unaffected unit control room of the event.
0 Request Security to restrict site access and have them notify Waterford Police and CT State Police of the restriction.
- 1.
- 2.
- 3.
NOTE Hazardous conditions or Security-related events may impact the ability to move personnel. If these conditions exist, it may be better to shelter personnel on site.
During a security event, it may not be advisable to sound an alarm or make a PA announcement.
Statdocal authorities may deploy offsite responders such as the National Guard or Statdlocal police to the Millstone Station in response to a security-related threat. The State of CT and Waterford Police will be responsible for protective measures for these forces, as necessary (ix., providing and issuing potassium iodide (KI) in a timely manner, maintaining doses ALARA, and upgrading exposures, issuing and tracking dosimetry). The Manager of Security (MOS)/SSS will notify the CR DSEO of any protective actions put in place.
For an emergency event, radiological or non-radiological, that does F Z O ~
involve a security threat, the station would consider offsite responders located onsite as non-essential to the event and evacuate them from the site. However, they are still under the States authority and the State may require they stay on site.
0 the event involves a situation where site personnel should be sheltered, Refer To EPI-FAF08, Evacuation and As~enibly,~
Sheltering, and perform actions.
0 WHEN appropriate, announce termination of sheltering.
0 WHEN appropriate, conduct full SERO activation and evacuation, as applicable.
MP-26-EPI-FAPO 1-001 Rev. 002 Page 7 of 15
Section D: Site Area Emergency Immediate Actions R E sheltering actions are being conducted, perform the following:
0 Activate the outside speakers.
VCA U T I ON\\/
ImpIementation of station evacuation shall not be delayed unless constraints are in place (e.g., Security-related) and doing so creates a threat to personnel safety.
0 Review the wording for the station notification message and announce the following over the station PA system:
Attention all personnel; attention ail personnel. A Site Area Emergency has been declared at (Unit #
) due to (brief description of event 0 E the designated emergency response facilities available, announce the following:
All on-duty SERO members report to your designated emergency response facility. All off-duty SERO members report to your designated Assembly Area.
0 E the EOF QFJ TSC is unavailable, announce the following over the station PA system:
The (EOF)(TSC) is unavailable at this time. All on-duty SERO members who report to the (EOF)(TSC), report to your backup locations. All off-duty SERO members report to your backup Assembly Area.
0 Repeat the PA message(s).
0 Log time of announcement on EPI-FAP15-012.
0 Review and approve the Incident Report Form (IRF) for transmittal.
\\/c A U T I ON\\/
Station evacuation may not be desired during certain events (e.g., Security-related).
station evacuation could endanger plant personnel, consider the following:
Defer actions until the threat has been resolved.
WHEN threat has been resolved, perform evacuation and accountability as quickly as possible.
I 0
MP-26-EPI-FAPO 1 -001 Rev. 002 Page 8 of 15
Section D: Site Area Emergency Immediate Actions 0 Refer To EPI-FAP08, Evacuation and Assembly, and conduct evacuation.
0 offsite responders (ix., National Guard) are onsite and considered non-essential to the event, request the SSSMOS evacuate them also.
NOTE The State of CT is responsible for issuing KI to offsite responders located onsite supporting the event.
-~
~
~~~
~
~~
0 Obtain information from the SSSMOS on protective actions (issuance of KI) being implemented by offsite responders located at the site and log.
0 Refer To EPI-FAP 15-001, DSEO/ADTS Briefing Sheet, and complete.
0 W o r m the DSEO/ADTS of offsite responders (ie., National Guard) responding to the site.
the emergency event o m s off-hours (6:00pm to 4:OOa.m) or on weekends direct SDO to voice-record EPI-FAP15-001 information and fax completed form to EOF and TSC.
- 2. NRC Notification 0
0 Direct the SDO to noti@ the NRC via the ENS.
0 Verify the Emergency Communicator or SDO has contacted the resident inspector.
no upgrade to classification is warranted, Go To Section F, Routine and Follow-up 3.
Actions.
MP-26-EPI-FAPOI-001 Rev. 002 Page 9 of 15
Section E: General Emergency Immediate Actions I. Notifications 0 NotifL the unaffected unit control room of the event.
D Request Security to restrict site access and have them notify Waterford Police and CT State Police of the restriction.
NOTE
- 1. Hazardous conditions or Security-related events may impact the ability to move personnel. If these conditions exist, it may be better to shelter personnel on site.
During a security event, it may not be advisable to sound an alarm or make a PA announcement.
- 2. StateAocal authorities may deploy offsite responders such as the National Guard or Statellocal police to the Millstone Station in response to a security-related threat. The State of CT and Waterford Police will be responsible for protective measures for these forces, as necessary (i.e., providing and issuing potassium iodide (KI) in a timely manner, maintaining doses ALARA, and upgrading exposures, issuing and tracking dosimetry). The Manager of Security (MOS)/SSS will notify the CR DSEO of any protective actions put in place.
- 3. For an emergency event, radiological or non-radiological, that does not involve a security threat, the station would consider offsite responders located onsite as non-essential to the event and evacuate them from the site. However, they are still under the States authority and the State may require they stay on site.
D the event involves a situation where site personnel should be sheltered, Refer To EPI-FAP08, Evacuation and Assembly, Sheltering, and perform actions.
0 WHEN appropriate, announce termination of sheltering.
0 WHEN appropriate, conduct full SERO activation and evacuation, as applicable.
MP-26-EPI-FAPO 1-00 1 Rev. 002 Page 10 of 15
Section E: Gencral Emergency Immcdiatc Actions 0 E sheltering actions are not being conducted, perform the following:
Cl Activate the outside speakers.
\\/c A u T I o N V Implementation of station evacuation shall not be delayed unless constraints are in place (e.g., Security-related) and doing so creates a threat to personnel safety.
0 Review the wording for the station notification message and announce the following over the station PA system:
Attention all personnel; attention all personnel. A General Emergency has been declared at (Unit #
) due to (brief descripfion of event Cl E the designated emergency response facilities availabk, announce the following:
All on-duty SERO members report to your designated emergency response facility. All off-duty SERO members report to your designated Assembly Area.
Cl the EOF system:
The (EOF)(TSC) is unavailable at this time. AH on-duty SERO members who report to the (EOF)(TSC), report to your backup locations. All off-duty SERO members report to your backup Assembly Area.
TSC is unavailable, announce the following over the station PA 0 Repeat the PA message(s).
0 Log time of announcement on EPI-FAPl5-012.
0 Review and approve the Incident Report Form (IRF) for transmittal.
NOTE The State must be notified within 15 minutes after a decision is made to issue a I
PAR.
R Review and develop PARs in accordance with EPI-FAP06, Classification and PARs.
0 IF PARs are warranted, issue them in accordance with EPI-FAP06-005, Control Room Protective Action Recommendations.
MP-26-EPI-FAW1-001 Rev. 002 Page 11 of 15
Section E: General Emergency Immediate Actions 0 the status of the fission product barriers or offsite radiological or meteorological conditions change, perform the following:
0 Evaluate the impact on PARs per EPI-FAPO6, Classification and PARs.
IF PARs change, provide changes to PARs to the State, as appropriate (non-delegable).
\\/c A u T I o NV Station evacuation may not be desired during catah events (e.g., Security-related).
station evacuation could endanger plant personnel, consider the following:
0 Defer actions until the threat has been resolved.
WHEN threat has been resolved, perform evacuation and accountability as quickly as possible.
0 Refer To EPI-FAPO8, Evacuation and Assembly, and conduct evacuation.
0 offsite responders (ie-, National Guard) are onsite and considered non-essential to the event, request the SSSMOS evacuate them also.
NOTE If emergency exposure upgrades are needed, the State of CT will authorize limits in accordance with EPA-400 guidelines.
0 Obtain information fiom the SSSMOS on protective actions being implemented by offsite responders located at this site and log.
0 Refer To EPI-FAP15-001, DSEO/ADTS Briefing Sheet, and complete.
0 Inform the DSEO/ADTS of offsite responders (Le., National Guard) responding to the site.
0 the emergency event occurs off-hours (6:OOpm to 4:OOam) or on weekends, direct SDO to voice-record EPI-FAP 15-OO1 information and fax completed form to EOF and TSC.
- 2. NRC Notification 0 Direct the SDO to notify the NRC via the ENS.
0 Verify the Emergency Communicator or SDO has contacted the resident inspector.
MP-26-EPI-FAPO 1-00 1 Rev. 002 Page 12 of 15
Section F: Routine and Follow-up Activities L
NOTE The State of CTAocaI agencies are responsible for upgrading exposures of offsite responders assigned to the station.
i NOTE The initial stages of any emergency may require CR personnel to perform several required tasks. If necessary, the CR-DSEO has the authority to reassign tasks (other than classification, PARs, and emergency exposure dose extensions) to other available CR individuals.
[II 1.
Ensure SAS has activated the Community Alert Network (CAN).
- 2.
Log all activities and decisions on EPI-FAP15-012, SERO Log Sheet.
0 3.
a release of radioactive material is in progress or is imminent, direct the Chemistry Technician to perform initial on-shift dose assessment.
E any of the following was defmed, consider perfoxming at this time:
Precautionary dismissal Evacuation Accountability 0 4.
SERO activation andor facility activation
- 5.
Continuously evaluate or direct the evaluation of the EAL tables and fiswn product barriers for changes in event status.
- 6.
Ensure the NRC is notified within 60 minutes of any event classification and whenever significant changes in conditions occur during the emergency.
0 7. Ensure follow-up notifications are routinely provided to the State and local agencies as appropriate.
MP-26-EPI-FAPO1-001 Rev. 002 Page 13 of 15
1 Section F: Routine and Follow-up Activities a 10. WHEN appropriate, announce termination of sheltering.
0 1 1.
§50.54(x) action is invoked (such as suspension of safeguards) ensure that the NRC is notified of the departure as soon as possible (but within one hour) using the ENS.
!J
- 12. Direct the RMT #1 to perform control room and plant habitability surveys and sampling.
NOTE The State of CTAocal agencies are responsible for issuing M to offsite responders assigned to the station.
0 13.
necessary, issue Kl tablets to control room staff in accordance with EPI-FAP09-003, KI Tablet Issue Authorization and Tracking Sheet, and log time of issue on SERO Log Sheet (nondelegable).
0 14. Conduct periodic briefings with the control room staff.
- 15. E events have been controlled to the point where termination of the emergency can be considered, Refer To EPI-FAP06, Classification and PARS, for guidance.
Section G: Transfer of Command and Control NOTE Activation of the EOF and TSC/OSC should occur within 60 minutes of SERO notification.
During certain events (e.g., Security-relatsd, toxic gases) immediate SERO activation may be deferred because of the threat to plant personnel. This could prevent activation of facilities within 60 minutes.
The control room may transfer certain response functions (such as team dispatch, exposure upgrade, accident mitigation, etc.) to TSC or EOF individuals before the facilities are declared activated, provided command and control is maintained by the CR-DSEO. (These fimctions cannot be the non-delegable ones unless the EOF DSEO responder assumes command and control of the event and becomes the DSEO.)
It is preferred that turnover with the ADTS and the EOF DSEO be conducted at the same time but events may occur which require separate turnovers to be completed.
0 1.
precautionary dismissal, and/or evacuation and accountability have been deferred due to certain constraints (e.g., Security-related, weather), perform the following:
0 Discuss constraints with the EOF DSEO and the ADTS.
Conduct turnover with the EOF DSEO and the ADTS.
Consider whether deferred actions can be performed.
0
- 2.
NOTE For a Unit 1 event, the Unit 2 CR-DSEO becomes the MCRO.
a 3.
0 4.
Upon formal relief by the DSEO, rccord turnover date and time in the logbook.
Conduct a briefing with the EOF DSEO and ADTS using EPI-FAP15-001, DSEO/ADTS Briefing Sheet.
Go To EPI-FAPOI-002, Manager of Control Room Operations.
a
- 5.
Prepared by:
Signature Print Date MP-26-EPI-FAPO 1-00 1 Rev. 002 Page 15 of 15
JOB PERFORMANCE MEASURE APPROVAL SHEET I.
Title:
SRO Tan Clearance Approval ID Number:
JPM-A5SRO I t.
Initiated:
I I I. Reviewed:
Developer R. J.Ashe$
Technical Reviewer IV. Approved:
N/A User Department Supervisor Nuclear Train g Supervisor P
Revision:
0 -
01 127105 Date
' Date Date
SUMMARY
OF CHANGES A/I 8, Date 11-23-2005 I SRM)
..~
DESCRIPTION REVlCHANGE Developed new JPM 0
2
JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number:
J PM-A5S RO Rev.
0 Task
Title:
Perform Tagging Operations System:
Administrative Time Critical Task:
Yes No X
Validated Time (minutes):
15 Task No.(s):
Applicable To:
SRO X
2.2.13 WA Rating:
3.613.8 NUTIMS #I 19-03-1 70 Method of Testing:
Si m u I a ted Perform an ce :
Actual Performance:
X Location:
Classroom:
X Task Standards:
Required Materials (procedures, equipment):
General
References:
Simulator:
X In-Plant:
X At the completion of this JPM, the examinee will have discovered that the tag out is in error. He will recommend the clearance not be approved until the Cross tie valve 2-CHW-125 is added to the clearance and the other Cross tie valve 2-CHW-124 is removed.
WC 2 Tagging Tagout Request 0, Work Package Tagout Verification/Boundary Sheet P&ID 25203-26027 sheet 2 of 4 P&ID 25203-3001 1 sheet 12F OP-233OC-001 Chilled Water System Valve Alignment WC 2, Section 1.4, 1.5. (Rev. 6-06)
READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.
3
JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
JPM-ASSRO Rev.
0 Initiating Cues:
You are the UC-SRO. the work package for 2-CHW-123 Chill Water Pump (P-149C) Discharge Isolation \\ al1.e has been I-e\\.ie\\ied. Appro\\x the prepared tagout.
The I all e inust be replaced due to leakage past the seat.
Restoration information is not required.
All dra\\i.ings 1ia1.c been \\.erified Controlled. Appro\\,ed and up to date.
Tass are p i n g to he made up by the PEOs.
In it ial Conditions 2-CHW-123 Yiil1 Water Puiiip (P-149C) Discharge Isolation
\\.al\\,e is leaking by its seat.
Maintenance ad\\rised removal and replacement of the v a l ~
- e.
The Station Tagging Computer Program is una~~ailable.
The need for a manual tagout \\%as evaluated and appro\\.cd by all required personnel.
The tagout w i l l bc entered into the computer as soon as the computer is a\\ ailable.
Simulator Requirements:
None NOTES TO EXAMINER *
- 1 Critical steps for this JPM are indicated with an X. For the examinee to achieve a satisfactory grade, critical steps must be completed correctly.
- 2.
When examinee states what h i d h e r simulated action/observation would be, read the appropriate Cue.
- 3. If necessary, question examinee for details of simulated actions / observations (i.e. What are you looking at? or What are you observing?).
- 4. Under NO circumstances must the examinee be allowed to manipulate any devices during the Derformance of this JPM [in-Plant onlv).
4
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-ASSRO TITLE: SRO TaQ Clearance Approval START TIME:
STEP 1
-& Performance Steps:
Review prepared Manual tag out, referring to appropriate sections of WC-2, the P&ID drawings, and the valve alignment OP233OC-001 GRADE X
Standards:
The examinee reviews Manual tag out sheet using WC-2, Tagging, Attachments 9: 10, & 16 as necessary The examinee also refers to the P&IDs for the Chill Water system, and the valve alignment OP 233OC-001 Using the following references:
P&ID 25203-26027 sheet 2 of 4 P&ID 25203-3001 7 sheet 12F OP-233OC-001 Chilled Water System Valve Alignment WC-2 Tagging Aft. 9,10, & 16.
Cue:
When requested, provide the examinee with the required documentation, including WC2, Tagging.
Comments:
5
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A5SRO TITLE: SRO Tan Clearance Approval STEP 2 2
Performance Steps: -
Review Tagout for the following:
X VERIFY tagout provides personnel and equipment safety for the tasks and hazards involved.
sources and isolation points have been considered.
VERIFY tagout does not compromise the operability of other components.
IF tagout is a blue tag tagout, ENSURE all work is assigned to a single contact Person.
instruments or controls and need for compensatory actions.
VERIFY completeness and sequencing of steps.
VERIFY correct tag selection for all work packages.
Unless required by procedure, ENSURE blue tags are not hung on redundant trains of operable safety related equipment.
REFER to Attachment 4 and VERIFY all energy REVIEW effects of tagout on indications, GRADE X
Standards:
Examinee refers to the P&IDs for the Chilled Water System, OP 233OC-001 Chilled Water Valve Alignment and discovers that the tag out is in error.
He also refers to WC-2 Tagging section 1.4 8, 1.5 Cue:
If requested, provide Attachment 7, Tagout Request.
Comments:
STEP 3 Performance Steps: IF tag out indicates a deficiency, PERFORM one of the following:
- a. NOTIFY a Tag Control Coordinator and RESOLVE the problem.
- b. RETURN tagout to a Tag Control Coordinator for resolution.
GRADE -
Standards:
Examinee states that he would:
notify the Tag Control Coordinator (PEO) of the issue.
x Recommend adding tag for 2-CHW-125, removing tag for 2-CH W-724.
6
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A5SRO TITLE: SRO Tag Clearance Approval Cue:
If examine does not recommend the tag out be modified then, ask the examinee for his recommendations.
Comments:
The order may differ slightly provided the examinee ensures the tag out is changed.
STOP TIME:
7
VERIFICATION OF JPM COMPLETION Job Performance Measure No.
JPM-ASRO 0
Rev.
Date Performed:
Operator:
Evaluator(s):
r I For examinee to achieve a satisfactory grade, ALL critical steps must be completed correctly If task is 1 Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade Time Critical Task?
Yes No Validated Time (minutes):
15 Actual Time to Complete (minutes):
Result of JPM:
(Denote by an 5 for satisfactory or a u for unsatisfactory)
Areas for Improvement:
8
EXAMINEE HANDOUT JPM Number:
JPM-ASRO Rev.
0 lnitiatin,q Cues.
You are the WC-SRO, the work packagc for ?-('I lit.- 12-3 "C'hill Water I-'unip (P-I 49C) Discharge Isolation" iilj e has lice11 reviewed. Appro1.e the prepared tagout.
The \\,ahre must be replaced due to leakage past the seat.
Restoration information is not required.
All dra\\\\ings 1 ~ n - e been verified "Controllecl..Ippro\\wl and up to date".
Initial Conditions 2-CHW-123 "Chill Water Pump (P-149c') l)iscIiaryc Isolation"
\\.ahre is leaking b! it's seat.
Maintenance adkised removal and replacement of'the I :I]\\ e The Station ragging Computer Program is 111ia1 ailahlc.
The need for a manual tagout was evaluated and appro\\ et1 by all required personnel.
The tagout \\fill be entered into the computcr as soon ;IS the computer is airailable.
9
1 0 4-(Sheet 1 of 1)
Work Package Tagout Verification/Boundary Sheet c
7%mcle e This form is for Manual use on@, it is not intended to match a computer generated form.
)I 1. Tagout Number I 2. Date
- 13. AWO Number (or Multiple)
- 4. Contact Person Date Init Date Init STOP THINK ACT REVIEW wc 2 Rev. 006-06 77 of 86
- 0 Work Package Tagout Verification/Boundary Sheet (Sheet 1 of 1)
This form is for Manual use only, it is not intended to match a computer generated form.
ONLY Z
n
- 2. Date
- 1. Tanout Number K
wc 2 Rev. 006-06 77 of 86 0
Work Package Tagout Verification/Boundary Sheet (Sheet 1 of 1)
This form is for Manual use only, it is not intended to match a computer generated form.
ONLY I
u Level of Use nfo r m at i o n wc 2 Rev. 006-06 77 of 86
.Tm-A c can 0
Work Package Tagout Verification/Boundary Sheet T R A I N 1 N G U S (Sheet 1 of 1)
This form is for Manual use only, it is not intended to match a computer generated form.
nformation STOP THiNK ACT REVIEW wc 2 Rev. 006-06 77 of 86
JOB PERFORMANCE MEASURE APPROVAL SHEET I.
Title:
SRO Shift Turnover ID Number:
JPM-A1 SRO II.
Initiated:
n R. J. AshGy Developer I I I.
Reviewed: a nical Reviewer IV. Approved:
b User Department Supervisor Revision: -
0 1/28/05 Date Date
JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number:
JPM-A1 SRO Rev.
0 Task
Title:
SRO Shift Turnover System:
Conduct of Operations Time Critical Task: Yes No X
Validated Time (minutes):
20 Task No.(s):
NUTIMS # 119-02-034 Applicable To:
SRO X
2.1.3 K/A Rating:
3.013.4 Method of Testing:
Simulated Performance:
X Actual Performance:
Location:
Classroom:
X Simulator:
X In-Plant:
X Task Standards:
At the completion of this JPM, the SRO has performed a review of turn over documents and found incorrect information related to a shift turnover Required Materials Shift Manager Log (eSOMS)
Iprocedures, equipment):
MP-14-OPS-GDL200, Attachment 2, MP2/3 Shift Turnover Report MP-14-OPS-GDL200, Operations Standards, Section 3.6 and Section 3.7 (Rev. 009)
DNOS-0306, Dominion Nuclear Standards, Shift Turnover 0
General
References:
MP-14-OPS-GDL200, Operations Standards, Section 3.6 and Section 3.7 (Rev. 009)
DNOS-0306, Dominion Nuclear Standards, Shift Turnover 0
READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and loa entries as if the evolution was actually being oerformed.
~~
Page 2 of 7
JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
JPM-A1 SRO Rev.
0 Initiating Cues:
Review the required documents prior to assuming shift duties I will act as the off going US.
Initial Conditions:
You are the oncoming US and have just arrived in the control room for the beginning of your shift.
The eSOMS program is NOT available; however, a hard copy of the Narrative Log for the off-going shift has been printed out. The IT Department is presently working to restore the program.
S i m u I at o r Re q u ire m en t s :
N /A NOTES TO EXAMINER * * *
- t *
- 1 Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, &J critical steps must be completed correctly.
- 2.
When examinee states what hidher simulated action/observation would be, read the appropriate "C ue".
- 3.
If necessary, question examinee for details of simulated actions / observations (i.e. "What are you looking at?" or "What are you observing?").
- 4.
Under circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
Page 3 of 7
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-AISRO TITLE: SRO Shift Turnover START TIME:
STEP 1 X Performance Steps: Obtain the documents that need to be reviewed prior to assuming shift duties.
GRADE-X Standards:
Examinee requests the documents that he/she would review. As a minimum, the list should include the The examinee may include additional documents for review [i. e., Surveillance Schedule, Temporary Modifications, Red Tag Index, Night Order Log (for any new night orders), Radwaste Log Book (eSOMS),
Radwaste Night Order Book, or Control Room Daily Surveillance MODES 1 & 2, SP 2619A-001 (NOT required)].
(There is NO requirement to review these documents prior to assuming the shift, but they may be utilized in a turnover. )
following:
MP-14-OPS-GDL200, Attachment 2, MP2/3 Shift Turnover Report Control Room Log book (ie. eSOMS Narrative Log)
Cue.
0 Provide the MP2/3 Shift Turnover Report and the SM Log (eSOMS Narrative Log).
0 Inform the examinee that NO surveillances are scheduled for hidher shift.
0 If requested, provide MP-14-OPS-GDL200, Operations Standards, and /or DNOS-0306, Shift Turnovers (The above listed additional documents will NOT be available to the examinee. If the examinee does request them, state that they are in use by other individuals, but will be provided prior to the completion of shift turnover.)
Comments:
0 MP-14-OPS-GDL200, Attachment 2, MP2/3 Shift Turnover Report lists items that should be reviewed prior to assuming shift duties.
The examinee may also refer to MP-14-OPS-GDL200. Operations Standards, Attachment 3, Operating Practices, and/or DNOS-0306, Shift Turnovers, for any additional requirements.
Page 4 of 7
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-AISRO TITLE: SRO Shift Turnover STEP 2 Performance Steps: Review the MP2/3 Shift Turnover Report and the SM Log (eSOMS Narrative Log) and ask the off-going operator about anything out of the ordinary.
GRADE-X Standards:
0 During the review of the SM log (eSOMS Narrative log) and the MPU3Shift Turnover Report, the examinee should recognize that there is a problem with taking the 3 LPSl out of service while Facility 2 is protected.
The examinee should also note that there is NO entry on the MPY3 Turnover Sheet for the B LPSl Pump under either the TS LCO and TRM ACTION Statements or Plant Systems And Alternate Plant Configurations.
Cue:
0 If necessary, review equipment out of service.
0 The B LPSl Pump is being removed from service to perform the scheduled PMs.
Comments:
STOP TIME:
Page 5 of 7
VERIFICATION OF JPM COMPLETION Job Performance Measure No.
JPM-AlSRO Rev Date Performed:
Operator:
Evaluator(s):
0 For examinee to achieve a satisfactory grade, & critical steps must be completed correctly If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade Time Critical Task?
Yes No X
Validated Time (minutes):
20 Actual Time to Complete (minutes):
Result of JPM:
(Denote by an S for satisfactory or a u for unsatisfactory)
Areas for Improvement:
Page 6 of 7
EXAMINEE HANDOUT JPM ID Number:
JPM-1ASRO Initiating Cues:
Initial ConditionS:
Review the required documents prior to assuming shift duties.
I will act as the off going US.
You are the oncoming US and have just arrived in the control room for the beginning of your shift.
The eSOMS program is NOT available; however, a hard copy of the Narrative Log for the off-going shift has been printed out. The IT Department is presently working to restore the program.
Page 7 of 7 MPOh Shift Turnover Report (Sheet 1 of 8)
DATE-TIM E 02 21 05 0520 TRAINING ONLY PREPARED BY SHIFT
~
U Woole\\ "NIGHTS" Shift 18 00 - 06 00 Action Requirement LCO Infinite action: Establish hourly fire watch.
Infinite action: Notify U2 USiSM Infinite action: 2619A-1 shift logs TRMAS 3.7. I O UITRMAS 6 7 TSAS 3.3.3.h f'l~:l.\\'T.S7~-l Tt!:S:
.\\/ODE: 1
,\\lE(i.,l l l ~ ~ l TTS:
Thermal: m M W T H Electric: W M W e Identified: 0. I IOepm Unidentified: 0.0 I2opm Date!Tirne:02/2 1 l05 04 I 5 K '. S LEL-lK,4GE:
Action Equipment Reason I
See AIL See Active Impairment List.
1 See AIL M2-04-09986, Security Mods 3
RC-200 AVMS Failed 24 1014 R\\ POIl'ER 1009" PZR PRESS 2250 psis RC'S 7 - A I %
=degrees I..
rral n Fac I I it)
PRO TE( 'TED Once per shift. record lower 4, I60 VAC Switchgear Room temperature (TI-6429) ON peo IlOliNDS 1669-I : see temporary log for details regarding actions required upon exceeding 95°F.
24E on 24D. record temperature per OP 2343.
(TB PEO) rcaclings in the narrative log (see photo of positioner gauges.) Immediately report any sustained air pressure less than 20 psig.
Check oil absorbent pads at the turbine front standard and change out as required. Perform weekl!..
concurrent with Turbine Overspeed Trip Test. (usually Fridays.)
Check [Init I Spent Fuel Pool leak detection outlet valve once per Dal. Shift and document no Ieakaw found in the narrative loe.
hlonitor positioner air pressures on 2-FW 5 IA. $ 1 SG Feed Regulating Valve, once per shift and log 22 (YELLOW) 0 7/2 5 !04 11~01/04 12:'15,104 10'09.!04 TS LCO and TRM ACTION Statements Coming Due (if more than one ACTION requirement per LCO, list each separately)
Ihte I Time I LCO I Action 1 Action Reauirement I Eauimnent I Reason Start Date 09/02/04 09i24i0.1 08!'11/04 04! 1304 I PLANT SYSTEMS AND ALTERNATE PLANT CONFIGURATIONS:
1 LIST the following information: (Provide procedure references as applicable.)
Compensatory measures Systems, components out of service.
Deviations from required system alignments.
The need for valve lineups or other restoration activities.
Temporary Mod installation and removals (Printed 02/20/05 0537), Unit 2 MP-14-OPS-GDL200 Rev. 008 MPOk Shift Turnover Report I
TRAINING ONLY Alternate Plant Configuration: Lighting panel L5 I,
breaker I8 has separation issues.(VSZ). Breaker 18 is RTO.
M2-02-03507 (ELEC) status ' I ' SSD 2R 16.
. \\ I,R LV Initiation Date: I I 0 I
('R# 01-1 127')
Clearanrr: X ' I5-2.344C'~N-OOOl 13attel-J Chargers Boric Acid C o d e nsat e Condenser Air I<elno\\~al Containment CRAC cs 1' (Sheet 2 of 8)
I. RCS:
249 ppni Roroii. 03'20'05 :(!' 0745
- 2.
SFP:
2 1 13 ppin Boron. 0-3 I 9 OS 123 0650
- 3. RWST: 2187 ppin Boron, 03,'18'05 (G; 0100 None.
~
~~
None.
Ref Night Order 10-07-04-01. Do not crosstie non-vital load centers in Modes 1-4. CR-04-09083, A!'R 04005973 ( 10: I7:04)
- 1.
Ref.: Night Order 7-30-04-0 I. Snapping 24E Supply Bus (7;'30:04)
- 2.
24E on 24D (2i2 I ;05)
None.
1.
Also see "Sumps".
I.
See Rad Waste Night Letter.
Procedural Tenip Motl: "Radiation Monitor Flow Lo" (CO2-3. D-9) alarm defeated with a half card per WC-IO. Attachment 2. WC-IO, Attachment 3 in Temp h4od book (to be retired in place.
Ref. EWR bl2-98 106). Dire for abandonment on 2/28/05.
Procedural Temp Motl: loinper to defeat the lower seal temp hi alarm due to failure of T-I7 I *.
Temporary PPC alarms established for T6107. TI 74*, M2 I 4 I8 I SSD 2R 16.
Procedural Temp Mod: "l.etdwon Line Radiation HiiFailore" (C02.'3. B-9) ala-in defeated with a half card per OP 2387A. Attachment 2. Attachment 2 in Temp Mod book. To be retired as parta of EWR M2-98106 for replacing Letdown Line Rad Monitor. Due for abandonment on 2/28/05.
Procedural Temp Mod: "SGFP Turbine 'A' Oil Cooler Discharge Temp Hi" (C-06!7, D-39) alarm defeated \\\\.it11 a half card per OP 2387A. (712 1/04) AWO h12-04-07353. scheduled for 7R 16.
- 2.
- 3.
- 4.
Ref.: Night Order 8-19 I. Recetting the Terr), Turbine Trip Throttle lever and trip hook.
None.
backwashing as soon possible after shift turnover. 0212 1/05.
Procedural Temp Mod: CLRW 'Temporary Filter Skid installed.
None.
1.
Continuous f i l l to the 'A' Condenser Expansion Joint water seal though (boot seal), IAW Design Change Notice DM2-00-0245-02, under A WO M202062 I8 & Tag Section 2LT 1-23 19A99-002, hung 1/5/04, Temp Mod to be removed under the same AWO in 7R 16.
The 'B' Condenser Expansion joint has been filled about once ever) 4 da>s for the last few weeks.
Continuing to trend. l0/20!'04 SJAE steam supply PCV would not respond to lowering stein pressure or changes in its setpoint.
DCN for actuator replacement h~1~-03-03599.Status
'E'. SSD ZR16 or SDH3, SERT item 'A' SJAE water trap needs to be bypassed to operate the SJAE properl?.. C R 04-02229. AWO M2 02322, status 'S', SSD 2R I6 or SDH3.
Both sets of SJAEs are in service to support backwash activities. 2/20 - 2/2 1!05
?.
I.
done.
D' Demin is currently in the amine form. in service IAW Chemistry SPROC.
done.
done.
(Printed 02/20/05 0537). Unit 2 MP-14-OPS-GDL200 Rev. 008 TRAINING ONLY MPOk Shift Turnover Report (Sheet 3 of 8)
None.
- 1)
- 2)
Alternate Plant Configuration: CIi-52 1 is closed. Ltdn
'A' Charging Pump determined to be leaking approximatel! 5 gph ( - 2 O. O in AWDT'shifi) M2 0 I 107. (9/27.'04) llWP for non-rounds CVCS activities is RWP 5, Task 4.
I Initiiitioii Date: 3-3 1-01 rad monitor is isolated. NMOD for abandonment due
?,'?Si05
.L\\lteriiate Plant Configuration: PIC-2 15 in inanual.
Maintaining pressure betlveen 60 and 75 psiig IAW 2201.
step 4. IO. 1 I.b.
A W O : bl2-0 1-06639 Clearance: 2C 15-2304AA02-0002 I n it i ii t io 11 Date : 1 3 6 '0 2 CR: CR-02-09747 AWO: M2-0 1-03686 Alternate Plant Configuration: El IC-Pis-2B failed during adjustment of the other 22 VDC power supply, and was turned off.
None.
Initiation Date: 9i24i04 AWO: M2-04-09807 Clearance: 2C16-2323A99-0003 None.
I.
The "B" Heater Drains Pump has leaking seal cooling lines. (MI-03-14572). Status 'D' for 2R16.
- 2.
The Heater Drains common discharge check valve, 2-HD-12. lcaks by. (M2 13692) Status 'S' for 2R 16.
3, The 3 8 feed heater sightglass has a stem leak. Isolated and tagged by FIN Team on 6/l 1/04. M2-P41A, "A" HPSl Pump is in 'alert' status. Also pump had Fe material found in inboard bubbler. M2-01-01 105, Status
- I., SSD 2"28/05 Procedural Temp Mod: The following CETs are bypassed by OP 2387G: H.ICT Probe 7A UJTEM7-A, HJCT Probe 7A I-leated tIJCT. HJCT Probe 5 HJCT SB, HJCT Probe 5 UJTEMS-B. HJCT Probe A
~ 2 4 H.
CET Probe I330 (Y-14). CET Probe F19, CET Probe J 16. CE7' Probe SI I. CET Probe X I I,
HJCT 2A heated and unheated. CET Probe L6.
- 1. Procedural Temp Mod: Temporal-), air coinpressor is installed. Procedure for operation of the temporary air compressor is in the blue folder on the US desk.
- 2. Numerous oil leaks have been found on "C" IAC. (CR-04-09396) Operate compressor as scheduled and monitor for additional oil leaks. Document accordingly.
04-05878.
- 3. Small air on flange on "A IAC (CR-04-0882), M2-04-09937 SSD 2/28/05 Procedural Temp Mod: Thermal barriers installed IAW OP 233511. Attachment in SM office.
(S/7/04)
None.
(Printed 02/20/05 0537). Unit 2 MP-14-OPS-GDL200 Rev. 008
3l;iin Steam N:tOCI Nlc Nitrogen Non-Lital Chillers NSST IhlW ivc Itirification R;rd Monitor RBCC W RCS TRAINING ONLY MPOh Shift Turnover Report (Sheet 4 of 8)
I.
The turning gear for the A SGFP does not properly engage or disengage. M2-03-00648 (2R 16)
- 7.
B SGFP oil leak on steam side. Turbine inboard bearing. Changing oil absorbent onceishift.
AWO M20001377 (2R16)
Removed the following Stator Har Outlet Temperature alarm (Deviation fiom average) from A L A R M -
SCAN: T9565 thru T9572. inclusive due to low from average temperatures. All actions of OP Zi24U.
step 4.5, that can be performed. have been. Possible loose connection. CR-0409999. (2R 16)
I.
2-MS-297 has body to bonnet leak. 1/4/04 M2-04-00106 (2R16)
- 2.
7-MS-I 10. ST-I29 (A SGFP) Inlet Isolation. is on the backseat due to packing leakage. 1 6:O-l
-3.
2-MS-367 has body to bonnet leak. M2-04-04646 (2R16)
- 4.
- 5.
M2-04-01379 2-MS-64B PPC digital point is failed. Removed form scan. R12-04-00620. Status 11.. SSD 2/28/05 Z-JvlS-64B indications: When valve is closed, green light may not fiinction reliably due to sticky upper limit switch. If red light is out or blue light is on. valve is confirmed to be closed. AWO M2-04-02 145 to bwe worked during HOT SHUTDOWN. (3/15.0-1)
ST-I 16 (A SGFP 111 Stream Supply) has leak and is isolated. On hot shutdo\\\\.n \\+ark list. See coinp measures. 4iI 2 9 4 M.2-04-035 16, Status.1.
No. 3 CIV steam leak is directed outdoors via hard pipe in 3 16 of Turbine Building. (C 01 200.4) Areas around the Turbine Building truck access have been posted as hizh niose level areas due to the steam noise from the discharge ofthe hard pipe. M20.102584 (2R16). Muffler installed I 012 I io4 Master Trip Solenoid A voltage does not have the proper voltage causing the solenoid to stick during surveillance testing. M2-04-006S2, Status E. to be norked during 2R 16.
Turbine turning gear light does not light when on gear. Bulb is OK, socket is loose. Also. gear does not shift to fast. 3\\16/04 AWO M2-04-02478. HSD work.
Per Chemistry Supervisor notes: Verify injection flow rate with Chem until further notice.
Chemistry will no longer sample each night, they have resumed weekly sampling per NPDES requirements. ( I2,%04)
Engineering requested NaOCl injection time to be raised to 15 min.bay. I 1!17!04
- 6.
I.
- 2.
- 3.
I.
- 2.
None.
I.
- 2.
- 3.
X 196A secured due to Freon and oil leakage, 2118/05, CR#-0500107. Blue tagged to prevent use but keep oil!Freon separated.
Nitrogen supply bottle low-pressure alarm defeated. 811 1104 M2-03-14569 (WW503)
Dual indication for 6 n u i m when runnine. FIN team minor maintenance. 2120/05 Nitrogen tagged to the A RCP SEXAS, tube # 1, electrical penetration. M2-03-0252 I. Status E.
2C15-2333x99-0002 (2RI6) Verified 4i23104 Nitrogen isolated to D RCP electl-acal penetration SWXA8. Tube $2. M.20305969. Status E.,
2R I6 (4/24:04)
Nitrogen isolated to SEXA4, tube #2. M2-04-03661. Status E. 2C16-2333x00-001 (5/26/04)
If 2 PPC monitors lock up. do not open any new PPC \\cindows on any PPC terminal. Ensure other PPC screens are updating. call Jim lheniig, who will fail over the PPC. DO NOT attempt to use OP 2349B. Manual Failover, as this will NOT work. AR 0300841321 Purification is aligned to the Spent Fuel Pool. 02116105, Deinin removed from sewice per Clieniistt-:
reauest 913104.
RM-8 168, CR-04-03736 documents a condition where the alarm setpoint defaults to a value of
>2pCi/cc under certain faulted conditions. If RM-8 168 is declared INOP due to an instrument failtit-e.
do not return to OPERABLE status until l&C has declared the alarm setDoint to be correct.
B. RBCCW Heat Evchanger isolated and drained for maintenance. (2i20105)
RWST FIX on recirc with AS-76, Temperature Control Valve, closed. OP 2350 marked up in Blue Folders. Procedure Chance submitted 2/23/05 None.
(Printed 02/20/05 0537), Unit 2 MP-14-OPS-GDL200 Rev. 008
SCIH ice \\\\!stet xtiitoi- ('ooling I CR-04-09208. T R I iM22 120830. AWO M2-04-01597. (l2/28!04)
I 1.
S I T ' S
I.
- 7.
- 3.
2-SW-12C. "B" SW I Ieacler Supply to "B' EDG. has an active leak. Schetlulecl for irepair 3R10.
2-SW-S.IA is CRiTR's for erratic flow control. M2-04-0773 I. Status -4.
(IU,J.'04)
When performing SW Pump testing using FIT-6471 or FIT-6472. l i a \\ ~ IST Coordinator or qualified CBM support to ensure the tlow meter is using a correct value Tor sonic \\ielocit\\,. 1-his check should be performed prior to each pump test that follo\\vs swapping ofpumps. ARg 04005525, due 31'1 5/05 to replace flow transmitters with a new model.
- 3. Ref.: OD MP2-071-04. 2-SW-8. I A and 2-SW8.l B solenoids are bqond their qualitied service lives. CR-04-08085.
- 5.
Ref.: OD MP2-074-04. Relief discharge line (2-SW-I 89) is not adequatel>, supported tor a design based seismic event. CR-04-09446.
Ref.: Night Order 10-14-04-01. received "Generator Protection Circuit Energized" alarm during retest M2-02-04963, StatLls.PI..
s 11 nips mccw
\\'en t i I ;it i o t i Vital Chillers Cross Unit System Status: List status of unit's equipment/alignments that impact this unit, i.e, fire protection, electrical, Circulating Water (dilution flow)
SYSTEM I
NOTES
- 2.
- 3.
- 4.
RBCCW Sump aligned to LIS through filter to support "B" RBCCW HX work, (220.'05)
Ref.: Night Order 5-05-04-01. TBCCW is contaminated with Freon 22 at 6.8 ppb. Significant leakage and intentional drainage must be collected and disposed of properly in barrels labeled as Freon contaminated. (AR# 04000027-30)
TB Exhaust Fan, FI I I I is tagged for motor replacement. 6/20!04 (AWO M2-03-10008. 'WP'. 12.'7:04)
None.
PDT sampled for Boron. Contained 21 I9 ppm. (6/13/04)
$3 SIT last filled on 1/17/05 ff 1 SIT last filled on 2i'I9;05 @ 0939 113 Aus Steam U3 IJO\\Y~I-to 24E I In service I 34B aliened to 24E I! 3 Service Air S\\\\,itchywcl None.
Ensure nobody enters the switchyard until Unit 3 authorizes the entr>'. This is athe case at all times, not just during S!D.
All entries into the switchyard should be scheduled. NUC WC 12.
page 5.
130 P Vent i Iat ion Fire Check ventilation after "blips" on Flanders Line, it trips even when other equipment stays running. The evaporator continues to run after power blip.
I-Fire-IO1 tagged closed to isolate leak on I-Fire-362 (Rx Bldg Airlock Sprinler Drain)
ADM?IN-332 10-001 0 1:'26i'O5)
(Prhted 02/20/05 0537), Unit 2 I
SFPI Garage Doors II: lec t ri ca I I?\\,aporattor MP-14-OPS-GDL200 Rev. 008 None.
GTS looking for a groirntl on MCC SFPI-M3, Bkr 2A. Ground suspectctl to e\\ist on I opf?
heaters powered by this breaker. (2/18105)
To prevent inadvertent tilling of staging tank during recirc or during evaporator processing, open FAC-DP-I I. Bkr 5 (Rx Bldg Floor Drain Sump Pump 'A'. M8-18)
hiisc S
I 1 l<\\'Ell,L,ANCES IN PROGRESS I' L c' SFPI DHR Drop Derrri Form Lead Drite Locrrtiott Dcpt SI-PI I-uel Pool Cooling leiltl.
I'rilei-ctl c'-OP-200.4. Response to Significant Plant Leaks due IO #3 CIV leak in Turbine Building. h4P-
?I)-\\\\ I>-( i [)I 20. Att. 13, Drainage Review and Permit, ivith procedure.
( )I' 3i.32 1. l.eiiiporary Air Compressor Operation
( 'ticinisti-! SPROC CH03-2-02, Amine Form Operation. Hi Effluent Conductivity alarm defeated at C.05 tliii.iri2 this test. Chemistry is monitoring conductivity. (9i2104)
<\\II> suspicious incidents such as actual or suspected surveillance, physical or communication attacks that coirld impact our facility \\%rill be re[ported to local. federal agencies, and IS0 N E IAW NEPOOL 0 1 ' :!Io.
Or' 7343. Ti-ansfei-ring Bus 24E Supply from Bus 24C to Bus 24D.
C 1: 1'1
\\I en t I Iat ion Blue Folder 3'22'04 Blue Folder 7/ I XO4 Blue Folder 8'30'04 Blue Folder I Oi 1 9/04 Blue Folder 3 19:'05 MPOh Shift Turnover Report (Sheet 6 of 8)
TRAINING ONLY 1.
Change to SC-I (effective 9:'30/04) requires at least 2 ~wople 10 be present \\\\hen pertormiiig non-routine maintenance or operational activities. Adtiitionall>. \\\\or-k activities pet-tbrmed near the SFP require additional security measures and miist be scheduled prior t o start of work.
Safet!. Dept. requires respirators for Dry Well entr! due to high mold readings. (923 '04)
If entering Mold Posted areas. must wear Tyvek suit, 1.ates L'inal gloves and coordinate with HP to determine proper respirator to wear prior to entering area. CJiiit I rad\\\\aste building recently posted as Respirator Required due to niold. (03; 1 1/04)
Torus Room posted as Mold and Radiation Area. SE corner is still clean. jX!13;04)
- 2.
- 3.
- 4.
None.
TemD Mod 1-01-3. Temuorarv Deinion for clean uu of DHR svsteni. I10'28:04)
Inform NRC (Bob Prince @, 610-337-5376) of any 'planned' 01- 'unplanncd' loss of SFP cooling anticipated to last ;>8 how, or an) unanticipated rise of5'F in ;I 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. See Breaker oDen on Dre-heater due to ground ~solation~troubleshootinrr.
CR-04-002 18 and CR-04-00344.
~~~~
~~
kl'l<OC7 ( IIOi-2-01. Air Iiijection of theCond&ate $sternfor Cotrosion Control Mihe Luno) I\\ ~
[ X
~
i e
Folder -1 2 0 (Printed 02/20/05 0537), Unit 2 MP-14-OPS-GDL 200 Rev. 008
A MPOla Shift Turnover Report (Sheet 7 of 8)
TRAINING ONLY Signature is not required when using electronic signature via ESOMs Narrative Log.
My signature indicates that I have completed all requirements of "Shift Relief and Turnover," required to assume my watch station.
I SIGNATURE 4
Shift Manager CO-Primary CO-Secondary PEO-ALJX Bldg. r PEO-U1 Rounds FTA Work Control Supv./
Emergency Coin m u nica t or 4
4 4
4 4
b b
TURNOVER REPORT SIGNATURE PAGE The following log books have been reviewed prior to assuming shifi duties:
Control Room The following have been, or will be, performed:
Temp. Modification (Outstanding Clearance) log book review Key control for Shift Manager keys (SM locker set #172. includes one (1)
MEDCO key)
Night Orders Conduct Shifl Brief The following log books have been reviewed prior to assuming shift duties:
Control Room The following have been, or will be, performed:
Night Orders Reviewed IAW COP 200.7.
The following log books have been reviewed prior to assuming shift duties:
Control Room Night Orders The following log books have been reviewed prior to assuming shifl duties:
Control Room Night Order Performed Key control for PEO-Aux Bldg. Keys (Control Room key locker set #197).
Performed Key control for PEO-Turb Bldg Keys (Control Room key locker set #196).
Performed Key control for PEO-Float Keys (Control Room key locker set #198).
ADDITIONAL ONCOMING WATCHSTATION REQUIREMENTS:
Review surveillance schedule to determine which tests your shift will perform (Tech. Spec., non Tech. Spec., ISI)
Temp. Modification (Outstanding C1earance)log book review.
Red Tag (issued since last watch) review (ON LINE ONLY).
Key control for Unit Supervisor keys ( SM key locker set #168. includes one (1)
MEDCO key).
Performed Key control for Unit 1 Rounds Keys (Control Room key locker set # S I )
Position is manned. If unmanned, SM has verified opposite unit is manned.
(Prmted 02/20/05 0537), Unit 2 MP-14-OPS-GDL200 Rev. 008 MPOk Shift Turnover Report (Sheet 8 of 8) 90 1165 1 05 00 i i o n s per Dilution
/Total Amount
~-
Di I ut ed
?;:of Last Dilution I
~
i Gallons per Boration N/A Total Amount Borated N/A Time of Last Boration N/A Gallons Blended M/U N/A
~
t-i I
Reactivity Briefing Sheet Current Rod Height Number of Steps Moved
~~ Control Rod Status 7 @ 180 0
gFJ I Boron
-. Pot
-. ___ Setting/Blend Ratio I 30.6:l Control Rod Movement Number of Steps Moved -
N/A Axial Flux Trend Stable
/Initial b--
Pot Setting i._
Current Pot Settiing Xenon Trend Stable 841 841 TRAINING ONLY Current Shift
~-
7 RCS Make-up Gallons per Dilution
---_I Total Amount Diluted Time of Last Dilution
-~
Gallons per Boration Total Amount Borated Time of Last Boration i
Gallons Blended M/U A
1 Boron Pot Setting/Blend Ratio 1 N/A Axial Flux Trend Stable Xenon Trend Stable
~~~
Current Pot Settiing Notes:
Received NE-04-F-090 Equilibrium Shape Index Value memo from Reactor Engineering. The memo specifies an ESI of +0.01.
RX Thumb Rules for:
1 YO Power Change:
3.7 steps on rods 633 gallons of PMW 7 gallons of B.A.
2130 gallday PMW Maintaininq 100% Power:
(Printed 02/20/05 0537). Unit 2 MP-14-OPS-GDL200 Rev 008
Unit 2 Control Room OPS Monday February 21,2005 TRAINING ONLY Night Shift MM-14 GDLOOP
-~
x x
2
~
~
0 5
1920 2/20/05 19122 Held pre-job brief to support Backwashing the A CW Bay IAW OP 23250.
Held Risk review meeting. Added backwash of the A Circ Bay to the work. 24E will be swapped back to 24D sometime prior to backwash of the D Bay on Monday AM.
See previous shift log entries for CDF values. PRA Condition remains GREEN.
~
(WOOLEY, WAYNE - MISC)
(STROLL, MARK - MISC) x 2
~
~
0 5
19126 Diluted 35.0 gallons of PMW to the VCT to maintain reactor power. (HARROD, ANDREW B - CO PPO) x 2120105 20:38 Pumped Containment Normal Sump 32% to 10% to support SP 2605G. (MILLS, WILLIAM R - CO SPO) x 2/20/05 2053 Received C-03/03 B35 PRIMARY DRAIN TANK PRESS HI/LO alarm. Pressure is 5 psig. Pressure increase is due to leakage from # I SIT to PDT. Vented PDT to 3 psig to clear alarm. (HARROD, ANDREW B - CO PPO) panel. SFP level is 366. (JOBBS, KEVIN M. - PEO AB) for backwashing operations per OP-2325D. Started B SWPump, Secured A SW Pump to PTL
~-
x 2m05 2 1 : r Completed Aux Building Compensatory Actions: Verified no new alarms on EHC M
2/20/05 215~5 Entered Unit: 2 type: TS Section: 3.7.4.1 Action Statement: (0), Service Water swaps 2-P-2326A 02-001 6 (WOOLEY, WAYNE - MISC) x x
x 2/20/05 21:28 2 ~ ~ 0 5 2131 2/20/05 21137 Started B Service Water pump, secured A Service Water Pump to support A circ bay backwash. (MILLS, WILLIAM R - CO PPO)
Diluted 35.0 gallons of PMW to the VCT to maintain reactor power. (HARROD, Exited Unit: 2 type: TS Section: 3.7.4.1 Action Statement: -(O), Service Water swaps for backwashing operations per OP-2325D. Started B SW Pump, Secured A SW Pump to PTL, is restored and operable.
ANDREW B - CO PPO)
~
2-P-2326A 02-0016 (WOOLEY, WAYNE - MISC)
M 2~0105 21:42 Intake Structure Condition Determination Surveillance complete. Plant Factor is 0, GREEN. Environmental Factor is 16, GREEN. 24Hour forecast: Plant Factor is 0, Environmental Factor is 14. (STROLL, MARK - MISC)
~.
J
~ ~ m O 5 21:45 Commenced educting A Circ Bay. (WOOLEY, WAYNE - MISC) x 2/20105 Completed Turbine Building Compensatory Actions: Lower 4160 Volt Swgr temperature = 83 degrees F. Stroked MS-IOOC/D to drain condensation because ST-116 is isolated. 2-FW-51A positioner air pressures 30 & 38. (MORRIS, MATTHEW L
- PEOTB) x 2
~
~
~
0 5
22:08 Shift Manager reviewed and accepted Unit 1 and Unit 2 electronic logs. (PAIN, x
~20105 22122 Secured A Circ Water Pump to support backwash of A bay. (MILLS, WILLIAM R -
x 2/20/05 22130 Started A Circ Water Pump. Completed backwash of A bay. (MILLS, WILLIAM R -
MICHAEL P - SM) co SPO) co SPO) z 2/20/05 22144 Completed 18-24 portion of SP-2619A-1, Control Room Daily Surveillance.
Acceptance Criteria satisfied. (HARROD, ANDREW B - CO PPO)
M 2/2005 2245 Secured educting A Circ Water Bay. (WOOLEY, WAYNE - MISC) i~
2m1105 22146 Reviewed and accepted 2651 K-001, Emergency Seal Oil Pump Automatic Start Test, SAT. (WOOLEY. WAYNE - MISC)
Page 1 of 5
Unit 2 Control Room OPS Monday February 21,2005 TRAINING ONLY Night Shift MM-14 GDLOOP
-~
~
J J
2120105 23:OO Entered Unit: 2 type: TS Section: 3.7.4.1 Action Statement: (0), Service Water swaps 2/20/05-2T47 Reviewed and accepted 2651 G-001, Motor Suction Pump Automatic Start Test, SAT.
(WOOLEY, WAYNE - MISC) for backwashing operations per OP-2325D. Started A SWPump, Secured 6 SW Pump to PTL 2-P-2326A 02-001 7 (WOOLEY, WAYNE - MISC)
N 220105 23:06 Shift Manager reviewed and accepted OPS Form 2619A-1, Control Room Daily x
J Surveillance, Modes 1 & 2, (18-24). (PAIN, MICHAEL P - SM) 220105 2 3 3 8
- /20/05 2 3 3 0 Started A Service Water pump, secured 6 Service Water. (MILLS. WILLIAM R -
Exited Unit: 2 type: TS Section: 3.7.4.1 Action Statement: -(O), Service Water swaps for backwashing operations per OP-2325D. Started A SW Pump, Secured 6 SW Pump to PTL, is restored and operable.
~
~
co SPO)
___________ 2-P-2326A 02-001 7 (WOOLEY, WAYNE - MISC) 2/21\\05 O w 5 Sampled RBCCW Sump. Results: Temp 71.4 degrees F, FAC ~ 0. 0 3 ppm, Act.
X X
<MDA, H-3 9.78E-06 pc/mI.
All parameters within limits for alignment to LIS. [This Entry Copied From Unit 2 Chemistry - Night Shift - 02/20/2005 by NORTON, JEFFERY< On duty Chem Tech]
Sampled 6-RBCCW HX prior to draining. Results: FAC <0.03 ppm, Act <MDA.
Draining to sump is permitted. [This Entry Copied From Unit 2 Chemistry - Night Shift
- 02/20/2005 by NORTON, JEFFERYc On duty Chem Tech] (NORTON, JEFFERYe On duty Chem Tech) 2/21/05 O k i 2 F Diluted 35.0 gallons of PMW to the VCT to maintain reactor power. (HARROD, 2/21/05 0 0 1 3 ~ Held Risk review meeting. No changes to scheduled activities are expected. PRA
._____. (NORTON, JEFFERY< On duty Chem Tech) 2/21/05 00:20 ANDREW B - CO PPO)
~
Condition remains GREEN as planned. (Barnett, Terry L - STA)
Aligned RBCCW area sump to LIS with filter bypassed for draining 6 RBCCW HX.
2/21\\05 0 0 3 5 J
FQI-9144 reading 197392. (JOBBS, KEVIN M. - PEO AB)
Secured X169B, B DC SWITCHGEAR ROOM CHILLER (VITAL CHILLER), and P122B, B DC SWITCHGEAR ROOM CHILLER (169B) CHILLED WATER PUMP following extended run post-maintenance. (SEAMAN, EDWARD R - WC SRO)
Reviewed and accepted SP 2651 R-001 Turbine Bearing Lift Pump Operational Test Sat. (WOOLEY, WAYNE - MISC)
Reviewed and accepted SP 26056-007, Containment Isolation System CIV Stroke and Timing IST.
Reviewed and accepted SP 2605G-004, RCS CIV Stroke and Timing IST.
Swapped protected facilities. Facility 2 is now protected. (WOOLEY, WAYNE - MISC)
Completed 261 9G-005, AC Sources Daily Surveillance, SAT. (HARROD, ANDREW B Started A Condenser Air Removal Fan, F-55A, secured B Condenser Air Removal 2/21/05 00.39
__- ~ _ _ _
2/*1/05 O1:Oo 2/29/05 01:OI (WOOLEY, WAYNE - MISC)
(WOOLEY, WAYNE - MISC) 2/24/05 01:02 2/21/05 01:08 2/27/05 01:18 2/21/05 01:19
- co PPO)
Fan, F-556 to support maintenance activities. (MILLS, WILLIAM R - CO SPO)
Page 2 of 5
Unit 2 Control Room OPS Monday February 21, 2005 TRAINING ONLY Night Shift MM-14 GDLOOZ
_ _ _ ~
~
~
2\\21/05 01:25 2/21/05 01133
~ -~~ __
- m 0 5 01137 2/21/05 01:41 Reviewed and Accepted 261 9G-005, AC Sources Daily Surveillance, SAT. (WOOLEY7 Performed Risk Review using EOOS to determine the impact associated with swapping electrical buses 24E to 24D. Risk is GREEN. (Barnett, Terry L - STA)
Completed Auxiliary Building Compensatory Actions: Verified no new alarms on EHC panel. SFP level is 366. (JOBBS, KEVIN M. - PEO AB)
Entered Unit: 2 type: TRM Section: 2TRM-7.1.20 Action Statement: a (I),
Transferring bus 24E Supply from Bus 24C to Bus 24D.
WAYNE - MISC)
~ ~ ~ ~ _ _ _
~~
2-P-2343 02-0009
.____ (WOOLEY, WAYNE - MISC) 2/21/05 01:41 Entered Unit: 2 type: TRM Section: 2TRM-7.120 Action Statement: b l (2),
Transferring bus 24E Supply from Bus 24C to Bus 24D.
2-P-2343 02-0009 (WOOLEY, WAYNE - MISC) 2/21/05 01:41 Entered Unit: 2 type: TRM Section: 2TRM-7.1.20 Action Statement: b2 (3),
Transferring bus 24E Supply from Bus 24C to Bus 24D.
2-P-2343 02-0009 (WOOLEY, WAYNE - MISC)
~~
~~
~
~~ _ _
~
2/21\\05 01:OO Entered Unit: 2 type: TS Section: 3.8.1.1 Action Statement: a (0), Transferring bus 24E Supply from Bus 24C to Bus 24D.
2-P-2343 02-0009
_ _ ~
(WOOLEY, WAYNE - MISC) 2121/05 01:46 Diluted 35.0 gallons of PMW to the VCT to maintain reactor power. (HARROD, ANDREW B - CO PPO)
_~
2/21/05 07:50 2/21/05 0 1 5 2 2/21/05 01:54 Completed 261 9G-001, AC Sources Surveillance, SAT. (MILLS, WILLIAM R - CO Reviewed and Accepted 2619G-001, T/S 3.8.1.1 Action a. - One Offsite Circuit Inoperable, SAT. (WOOLEY, WAYNE - MISC)
Diverted Letdown to Clean Waste to lower VCT level from 86.7% and 23.7 psig to SPO)
-~
~
~
78.7% and 15.0 psig. (HARROD, ANDREW B - CO PPO) __-
Completed Unit: 2 type: TS Section: 3.8.1.1 Action Statement: a (0), Perform Surveillance Requirement 4.8.1.I.
Processed 176.9 gallons from the PDT to Clean Waste. (HARROD, ANDREW B - CO PPO) 212105 0155 2-P-2343 02-0009 (WOOLEY, WAYNE - MISC) 2/29/05 01:57
--- 2/21105
-~
01:58 - Completed alignment of Bus 24E to Bus 24D. (MILLS, WILLIAM R - CO SPO) 2/21105 02:09 Exited Unit: 2 type: TRM Section: 2TRM-7.1.20 Action Statement: a (I), Transferring bus 24E Supply from Bus 24C to Bus 24D, is restored and operable.
Exited Unit: 2 type: TRM Section: 2TRM-7.120 Action Statement. b l (2), Transferring bus 24E Supply from Bus 24C to Bus 24D, is restored and operable.
Exited Unit: 2 type: TRM Section: 2TRM-7.1.20 Action Statement: b2 (3), Transferring bus 24E Supply from Bus 24C to Bus 24D, is restored and operable
_ _ _ _ ~ _ _
2-P-2343 02-0009 (WOOLEY, WAYNE - MISC) 2/21/05 02109 2-P-2343 02-0009 (WOOLEY, WAYNE - MISC)
~-
2/21/05 O*:O9 2-P-2343 02-0009 (WOOLEY. WAYNE - MISC)
Page 3 of 5
Unit 2 Control Room OPS Monday February 21, 2005 TRAINING ONLY Night Shift MM-14 GDLOOZ Exited Unit: 2 type: TS Section: 3.8.1.1 Action Statement: a (0), Transferring bus 24E Supply from Bus 24C to Bus 24D, is restored and operable.
Established augmented sampling of RBCCW sump on a daily basis-while aligned to LIS for B RBCCW HX scheduled work (SP 2617A-007). Sump will be sampled for activity and required NPDES parameters, as required by OP 2336C. Next sample is required on 2/22/05 at 0000. Chemistry has been notified. (SEAMAN, EDWARD R -
2-P-2343 02-0009 (WOOLEY, WAYNE - MISC)
~ _ _ _ _ _
WC SRO)
Diluted 35.0 gallons of PMW to the VCT to maintain reactor power. (HARROD, ANDREW B - CO PPO) 2/21\\05 0 3 3 1 Reviewed and Accepted 2343A-002, Component Alignment for Shifting Bus 24E to
- - - ~
~
BUS 24D. (WOOLEY, WAYNE - MISC)
-~
2/21/05 03:33 Reviewed and Accepted 2619C-001, Control Room Weekly Checks, SAT (WOOLEY,
~~
~~
WAYNE - MISC) 2\\21/05 04106 Reviewed and Accepted 2601 D-001, Power Range Safety and Channel Delta T Power
~
Channel Calibration, SAT. (WOOLEY, WAYNE - MISC)
Completed 00-06 portion of SP 261 9A-1, Control Room-Daily Surveillance.
Acceptance Criteria satisfied. (HARROD, ANDREW B - CO PPO)
Latest CTMT grab sample results from 02/19/0718 are :
CVR8123A: 4639 cprn, CVR8123B: 2275 cpm CVR8262A: 3339 cpm, CVR8262B: 21 05 cpm Current CTMT RM readings are:
CVR8123A: 4521 cpm, CVR8123B: 2270 cpm CVR8262A: 3378 cpm, CVT8262B: 2132 cpm.
Per 23148, no grab sample is required to vent Containment. (MILLS, WILLIAM R -
- 2/27/05 -
04110 NRC phone check - SAT. (HARROD, ANDREW B - CO PPO)
-~
2/21/05 04:24
~~~
~~
2/21/05 04:24 co SPO)
~-
2/21/05 04:30 B RBCCW HX has completed draining. Aligned RBCCW Sump discharge filter, L-2/21/05 04:34 774, in service for hydrolazing HX. (SEAMAN, EDWARD R - WC SRO)
Shift Manager Reviewed and Accepted Ops Form 261 9A-001, Control Room Daily Surveillanc& Modes 1 & 2, (00-06)(PAIN] MICHAEL P - SM)
Added 10 cu ft H2 to VCT. (HARROD. ANDREW B - CO PPO) 2/21/05 0 4 3 2/21105 04:37 Stopped F23, EB Purge Supply Fan and F34C, Main Exhaust Fan; enclosure building
~
~
purge is secured. (MILLS, WILLIAM R - CO SPO)
_ _ _ ~ _ _ _
notified. (MILLS, WILLIAM R - CO SPO)
- -~
2/27105
_- 0 4 3 9 2/21/05 04.40 2/21~05 04:53 Started F25A, A EBFS Fan. Run hours = 15.58 (MILLS, WILLIAM R - CO SPO)
Commenced venting Containment, initial pressure 20 H20 and Chemistry has been Diverted Letdown to Clean Waste to lower VCT level from 80 5% and 22.6 psig to
_-__ 73.3% and 16.2psig. (HARROD, ANDREW B - CO PPO)
.~
z 2/20105 O5:02 Entered Unit: 2 type: TS Section: 3.7.4.1 Action Statement: -(O), Service Water swaps for backwashing C Circ Bay per OP-2325D. Started B SW Pump, Secured C SW Pump to PTL.
2-P-2326A 02-001 7
-~
-~ - -
(WOOLEY, WAYNE - MISC)
~-
z 21fcuiiG- 0 5 0 ~ - Started B Service Water pump, secured C Service Water (MILLS, WILLIAM R -
Page 4 of 5
Unit 2 Control Room OPS Monday February 21,2005 TRAINING ONLY Night Shift MM-14 GDLOOZ
~-
~
~~
~~
x
- ~+005 05104 Exited Unit: 2 type: TS Section: 3.7.4.1 Action Statement: -(O), Service Water swaps for backwashing C Circ Bay per OP-2325D. Started B SW Pump, Secured C SW Pump to PTL, is restored and operable.
Entered Unit: 2 type: TS Section: 3.5.2 Action Statement: a (0), Removed B LPSl Pump from service for preventative maintenance.
~~~
2-P-2326A 02-001 7 (WOOLEY, WAYNE - MISC)
~-
2/21/05 0522 2-P-2307 02-0001
~
(WOOLEY, WAYNE - MISC) 2/27/05 05:37 Reduced turbine load /2 of a minor division on Load Limit Pot. (HARROD, ANDREW
~ ~ _ _ _. _ _
~~~~
B - CO PPO)
~~
~~~~~~~~
Page 5 of 5
JOB PERFORMANCE MEASURE APPROVAL SHEET I
JPM Title.
SRO AWO Acceptance ID Number:
JPM-A2SRO II.
Initiated:
Developer I I I. Reviewed: 4 echnical Reviewer IV. Approved:
User Depahment Supervisor Revision:
0 -
1/28/05 Date
/A</-
Date Date Date
SUMMARY
OF CHANGES I-All 8 Date DESCRIPTION REWCHANGE I
o 11-30-2004 I Developed new JPM I
2
JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number:
JPM-A2SRO Rev.
0 Task
Title:
SRO AWO Acceptance System:
Equipment Control Time Critical Task: Yes No X
Validated Time (minutes):
20 Task No.(s):
NUTIMS # I 19-01-098 Applicable To:
SRO X
2.2.21 KIA Rating:
2.313.5 Method of Testing:
Simulated Performance:
X Actual Performance:
Location:
Classroom:
X Simulator:
In-Plant:
Task Standards:
At the completion of this JPM, the examinee will recommend the correct PMT, HPSI Pump IST (SP2604AO-001).
Required Materials MP-20-WP-GDL40 Pre and Post Maintenance Testing (procedures, equipment):
MP-20-WP-GDL30 Work Performance MP-20-WP-GDL20 Work Order Preparation Training AWO SP2604AO HPSI Pump lnservice Testing, 2 1,750 psia, Facility 1
Genera I
References:
MP-20-WP-GDL20, MP-20-WP-GDL40, MP-20-WP-GDL30 READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and 104 entries as if the evolution was actually being performed.
3
JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
JPM-A2SRO Rev.
0 Initiating Cues:
You are the WC-SRO, the AWO for "A" HPSl pump bearing replacement has been returned you, determine what must be accomplished to close out the AWO.
Inform the examiner of your completion of this JPM by discussing the conclusions of your evaluation of the work package and your recommendations.
Initial Conditions:
The "A" HPSl Pump bearing replacement was done as on line maintenance, with the plant at 100% power.
Tagging clearing and restoration activities are being done by other members of the crew.
Simulator Requirements:
None NOTES TO EXAMINER * *
- I
- 1.
Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, When examinee states what hidher simulated actiordobservation would be, read the appropriate "Cue".
If necessary, question examinee for details of simulated actions / observations (Le. "What are you looking at?" or "What are you observing?").
critical steps must be completed correctly.
- 2.
- 3.
- 4.
Under NO circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A2SRO TITLE: SRO AWO Acceptance START TIME:
STEP 1 Performance Steps: Review the AWO using guidance in GDL20, GDL30, and GDL40.
GRADE Standards:
The examinee reviews the AWO and requests the following references:
MP WP-GDL30 Work Performance MP-20-WP-GDL20 Work Order Preparation MP WP-GDL40 Pre and Post Maintenance Testing Cue: When requested, provide the examinee with the required documentation, including the enclosed GDL40, GDL30 and GDLZO.
Comments:
STEP 2 Performance Steps: PMT for replacing HPSl pump bearings requires Tech Spec surveillance and IST to be performed, per GDL40 Att. # 3.6.
GRADE -
__ Standards:
Examinee refers to GDL40, and SP 2604A0.
X Examinee determines that Tech Spec surveillance SP 2604A0-001 should be done in its entirety.
Cue:
Comments:
The examinee may also specify that the motor running and starting amperage be taken during the surveillance. (This would be the retest for disconnecting/reconnecting the motor) 5
PERFORMANCE INFORMATION JPM ID NUMBER:
JPM-A2SRO TITLE: SRO AWO Acceptance STEP 3 Performance Steps: Recommendation given to add Tech Spec surveillance SP2604AO "HPSI Pump lnservice Testing, 2 1,750 psia, Facility 1" GRADE X
Standards:
Examinee makes recommendation to add Tech Spec surveillance SP2604AO "HPSI Pump Insewice Testing, 3 7,750 psia, Facility 7" to the AWO.
(Examinee may add the motor current requirement, also.)
Cue:
Comments:
STOP TIME:
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VERIFICATION OF JPM COMPLETION Job Performance Measure No.
JPM-A2SRO Rev.
Date Performed:
Operator:
Eva I u a to r( s) :
0 For examinee to achieve a satisfactory grade, critical steps must be completed correctly If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task?
Yes No X
Validated Time (minutes):
Actual Time to Complete (minutes):
20 Result of JPM:
(Denote by an S for satisfactory or a for unsatisfactory)
Areas for Improvement:
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EXAMINEE HANDOUT JPM Number:
JPM-A2RO Rev.
0 Initiating Cues:
You are the WC-SRO, the AWO for A HPSl pump bearing replacement has been returned you, determine what must be accomplished to close out the AWO.
Inform the examiner of your completion of this JPM by discussing the conclusions of your evaluation of the work package and your recommendations.
Initial Conditions:
The A HPSl Pump bearing replacement was done as on line maintenance, with the plant at 100% power.
Tagging clearing and restoration activities are being done by other members of the crew.
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