ML080940442
| ML080940442 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/31/2008 |
| From: | Constellation Energy Group |
| To: | NRC Region 1 |
| Hansell S | |
| Shared Package | |
| ML073040288 | List: |
| References | |
| Download: ML080940442 (92) | |
Text
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE:
Title:
Determination of Technical Specification Actions when in Single Loop Operation and MCPR is exceeded.
Revision: NRC 2008 Task Number:
341 -032-03-03-2: Evaluate Plant Systems performance and coordinate appropriate actions per Tec,hnical Specifications, as required.
Approvals:
I General Supervisor Date Operations Training (Designee)
General Supervisor Date Operations (Designee)
NA EXAMINATION SECURITY
/
Configuration Control Date TrainedEvaluator :
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA Expected Completion Time:
15 min.
Time Critical Task:
No Alternate Path Task: No Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments :
Evaluators Signature:
Date:
NRC EXAM Admin SRO/JPM Conduct of Ops#l 1
March 2008
Recommended Start Location: (Completion time based on the start location)
Any appropriate location with the required Reference Material.
Simulator Set-up:
None Directions to the Instructor/Evaluator:
To be performed as an administrative JPM.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the Reactor Engineer, Work Control or other on shift personnel. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independendpeer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as PasdFail. All steps are sequenced critical unless denoted by a e.
- 2. During Evaluated JPM:
0
- 3. During Training JPM:
0 0
Self verification shall be demonstrated.
Self verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. Plant Technical Specifications
- 2. N2-SOP-29
- 3. N2-OP-29
- 4. NUREG K/A General Knowledges and Abilities 2.1.12(4.0)
Tools and Equipment:
- 1. 3D Monicore Periodic Log indicating MCPR is above 1.O Task Standard:
Given current plant status and Thermal Limit information, determine the actions required by Technical Specifications.
NRC EXAM Admin SRO/JPM Conduct of Ops#l 2
March 2008
Initial Conditions:
I Performance Steps I Standard
- 1. The Reactor was operating at 100% power when ONE Reactor Recirc Pump tripped due to high motor vibration.
- 2. N2-SOP-29 has been completed through step 5.7.
Initiating Cues:
(Operators name), determine the actions required by Technical Specifications for single loop operation and verify Unit 2 is in compliance.
Grade Comments
- 1. Provide repeat back of initiating Proper communications used for repeat SaWnsat cue. Evaluator Acknowledge repeat back providing correction if necessary back (GAP-OPS-0 VOperations Manual)
RECORD START TIME
- 2. Obtain a copy of the Technical Obtains a copy of Technical Specifications and reviewhtilize Specifications.
the correct section.
Refers to Reactor Coolant System (RCS) Section.
SatLJnsat NRC EXAM Admin SRO/JPM Conduct of Ops#l 3
March 2008
I Performance Stew I Standard I
Grade
- 3. Enters T.S. - 3.4.1, Recirculation Enters T.S. - 3.4.1 and determines Pass/Fail Loops Operating.
Single Loop operation is allowable as long as the specified LCOs are met.
CUE:
Tell the candidate the Steps listed as c. and d.
were accomplished by I&C.
- a. LCO 3.2.1, Average Planar Linear Heat Generation Rate.
- b. LCO 3.2.2, Minimum Critical Power Ratio.
- c. LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation.
o Reset APRM Biased Thermal Power-Upscale for Single Loop.
- d. LCO 3.3.2.1, Control Rod Block Instrumentation.
o Reset RBM - Upscale for Single Loop.
CUE: As the Reactor Engineer, Review 3D Monicore Periodic Log and determine MFLCPR is greater than 1.O.
Determines MFLCPR limit is NOT met.
provide the candidate with a copy of 3D Monicore Periodic Log.
- 4. Determines Technical Refers to T.S. LCO 3.2.2 and Specification LCO requirements. determines:
0 A - The MCPR(s) must be restored to within limits within two (2) hours.
B - IF Required Action A. 1 is not met, power must be below 25% RTP in four (4) hours.
Pass/Fail PassEail I
Pass/Fail Comments NRC EXAM Admin SRO/JPM Conduct of Ops#l 4
March 2008
CUE:
If asked as the Reactor Engineer, tell the Candidate that you are investigating Rod patterns that will lower the affected MCPR.
End of JPM TERMINATING CUE: Appropriate Technical Specifications have been entered and LCOs identified.
RECORD STOP TIME NRC EXAM Admin SRO/JPM Conduct of Ops#l 5
March 2008
Initial Conditions:
- 1. The Reactor was operating at 100% power when ONE Reactor Recirc Pump tripped due to high motor vibration.
- 2. N2-SOP-29 has been completed through step 5.7.
Initiating Cues:
(Operators name), determine the actions required by Technical Specifications for single loop operation and verify Unit 2 is in compliance.
NRC EXAM Admin SRO/JPM Conduct of Ops#l 6
March 2008
~ 1 -
Reference Data - JPM A1A 1-18-08.txt
)
~ 1 -
Reference Data - s i n g l e LOOP Operation.
CORE PARAMETERS 3DM/P11 PREDICTOR LOG POWER MWT 2048.9 FLOW MLB/HR 71.225 CALC RESULTS FPAPDR 0.897 SUBC BTU/LB 27.39 K e f f 0.9992 PR PsIa 1015.41 XE WORTH %
-2.22 CORE MWD/ST 25193.5 XE/RATED 0.950 CYCLE MWD/ST 9225.6 AVE VF 0.481 MCPR 1.116 D EXP MWD/ST 0.0 CORRECTION FACTORS: MFLCPR= 0.958 MFLPD= 1.000 OPTION:
ARTS 1 LOOPS ON MANUAL FLOW PAGE 1
TODAY-2008 14:08 CALCULATED TODAY-2008 14:lO PRINTED CASE I D FSNF1070621140836 RESTART FMLD1070525075507 NONADAPTIVE - FULL CORE LOAD L I N E
SUMMARY
CORE POWER 59.1%
CORE FLOW 65.6%
LOAD L I N E 111.9%
MAPRAT=
1.000 MCPRLIM= 1.190 MFLCPR 1.038 1.030 1.008
- 1. 04 0.984 0.982 0.980 0.978 0.974 0.973 59 5 5 5 1 47 43 39 3 5 3 1 27 23 19 1 5 11 07 03 L
L L
L L
L L
MOST L I M I T I N G LOCATIONS (NON-SYMMETRIC)
LOC MFLPD LOC MAPRAT LOC PCRAT 29-14 0.763 23 4 0.664 21 3 N/A 27-12 0.763 25 4 0.658 13 4 N/A 29-18 0.760 13 4 0.650 23 4 N/A 37-50 0.753 21 4 0.643 35 3 N/A 37-18 0.751 21 4 0.640 23 4 N/A 31-52 0.750 23 4 0.639 13 4 N/A 25-14 0.749 11 4 0.638 13 4 N/A 39-38 0.747 15 4 0.634 15 4 N/A 37-36 0.740 19 4 0.633 11 4 N/A 27-16 0.736 39 4 0.631 23 4 N/A 00 00 L
C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT M
00 36 36 00 40 00 00 40 00 00 00 40 00 00 40 00 00 36C 36 00 46D L
L L
L L
L 02 06-10 14-18 22 26 30 34 38 42 46 50 54 58
- =MULTIPLE CORE AVE AXIAL NOTCH REL PW LOC 0.112 25 00 0.239 24 02 0.456 23 04 0.580 22 06 0.675 2 1 08 0.746 20 10 0.806 19 1 2 0.859 18 14 0.907 17 16 0.938 16 18 0.978 1 5 20 1.081 14 22 1.125 1 3 24 1.174 12 26 1. 2 2 1 11 28 1.268 10 30 1.309 09 32 1.364 08 34 1.424 07 36 1.478 06 38 1.536 05 40 1.565 04 42 1. 5 1 2 03 44 1. 2 3 1 02 46 0.417 0 1 CORE AVERAGE RADIAL POWER DISTRIBUTION RING #
1 2
3 4
5 6
7 8
REL PW 1.067 1.288 1.173 1. 2 5 1 1.300 1.170 1.040 0.460 Page 1
Reci rcul at i on Loops Operat i ng 3. 4. 1 3. 4 REACTOR COOLANT SYSTEM (RCS) 3. 4. 1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation,
I OR following limits applied when the associated LCO is appl i cab1 e:
One recirculation loop shall be in operation with the I
- a.
- b.
C.
- d.
LCO 3. 2. 1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR), ' I single loop operation limits specified in the COLR; LCO 3. 2. 2, "MINIMUM CRITICAL POWER RATIO (MCPR)," single loop operation limits specified in the COLR; LCO 3. 3. 1. 1, "Reactor Protection System (RPS)
Instrumentation," Function 2.b (Average Power Range Monitors F1 ow Biased Simul ated Thermal Power-Upscale),
Allowable Value o f Table 3.3.1.1-1 is reset for single loop operation; and LCO 3. 3. 2. 1, "Control Rod Block Instrumentation,"
Function 1.a (Rod Block Monitor-Upscale), Allowable Value of Table 3.3.2.1-1 is reset for single loop operation.
APPLICABILITY:
MODES 1 and 2.
NMP2 3.4.1-1 Amendment 9 7, 92
MCPR 3.2.2 CONDITION A.
Any MCPR not w i t h i n 1 i m i t s.
3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)
REQUIRED ACTION COMPLETION TIME A. 1 Restore MCPR(s) t o 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> w i t h i n l i m i t s.
LCO 3.2.2 A l l MCPRs s h a l l be greater than or equal t o t h e MCPR operating l i m i t s specified i n t h e COLR.
B.
Required Action and associated Completion Time not met.
APPLICABILITY:
THERMAL POWER 2 25% RTP.
B. 1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> t o < 25% RTP.
~~~
~~
~~
SURVE I L LANC E REOU I REMENTS SURVEILLANCE
~~
I FREQUENCY SR 3.2.2.1 V e r i f y a l l MCPRs are greater than o r equal t o t h e l i m i t s specified i n the COLR.
Once w i t h i n 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> a f t e r 2 25% RTP 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> t h e r e a f t e r (continued)
NMP2 3.2.2-1 Amendment 91
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Review Daily Checks Log IAW N2-OSP-LOG-DO0 1 Revision: NRC 2008 Task Number:
Approvals:
General Supervisor Date General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Trainer/Evaluator :
Evaluation Method: PERF'ORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED LOCATION Expected Completion Time: 25 minutes Time Critical Task: NO Alternate Path Task NO Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments :
Evaluator Signature:
Date:
NRC EXAM Admin SRO/JPM Conduct of Ops#2 1
March 2008
Recommended Start Location: (Completion time based on the start location)
Any appropriate location with the required Reference Material.
Simulator S e t-up :
None Directions to the Instructor/Evaluator:
To be performed as an administrative JPM.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.
Notes to Instructor / Evaluator:
- 1.
- 2.
During Evaluated JPM:
- 3.
During Training JPM:
Critical steps are identified as PasdFail. All steps are sequenced critical unless denoted by a 0, 0
Self-verification shall be demonstrated.
0 Self-verification shall be demonstrated.
0 No other verification shall be demonstrated.
References:
- 1. N2-OSP-LOG-DO0 1, Daily Checks Log
- 2. K/A 2.1.18(3.O) Ability to make accurate, clear and concise logs, records, status boards, and reports.
Tools and Equipment:
- 1. Calculator Task Standard:
N2-OSP-LOG-DOOl, Attachment 2 review completed and designated errors documented in the Remarks Section of N2-OSP-LOG-DOOl.
NRC EXAM Admin SRO/JPM Conduct of Ops#2 2
March 2008
Initial Conditions:
- 1. The plant is operating at 100% power.
- 2. N2-OSP-LOG-DO01 for the daily checks log has been completed and submitted for CRS/SM review.
3. Ask the operator for any questions.
Initiating cue:
(Operators name), Perform a review of N2-OSP-LOG-DOO1, Attachment 2 and document any unsatisfactory results in the Remarks Section on page 10 of N2-OSP-LOG-DO0 1.
- 1. Provide repeat back of initiating Proper communications used for repeat Satmnsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary I
EVALUATOR to provide copy of N2-OSP-LOG-DO01 to candidate for review.
RECORD START TIME
- 2..Obtain a copy of the reference N2-OSP-LOG-DO0 1 obtained.
Sat/Unsat procedure and reviewhtilize the
- referenced.
correct section.
NRC EXAM Admin SRO/JPM Conduct of Ops#2 3
March 2008
- 3..Reviews Daily Checks Log and determines the following are outside of their limits.
0 CUE: If asked what Suppression Pool level indication was used, state CMSLA02 and that that this level was confirmed on other indications.
CUE: If asked if the Reactor Building Differential Pressure was confirmed on other instrument, state YES.
0 0
0 CUE: If asked if the Reactor Building is in Summer Reversal, state NO.
Sheet 1 of 18 - sodium pentaborate solution is below TS limit.
Sheet 6 of 18 - Supp Pool Lvl is below TS limit.
Sheet 7 of 18 - RX BLDG Diff Press is below its TS limit.
Sheet 12 of 18 - CST Lvl is below its USAR limit.
Sheet 14 of 18 - Max difference between APRM averages exceeds 2% (may also identify APRM #1 as being more than 2% out of TS limit.
Sheet 17 of 18 - Computer Point SWPLA06 is below the TS limit.
Pass/Fail
- 4. Documents any unsatisfactory Results documented in Results Section.
SaNnsat results in the Remarks Section of N2-OSP-LOG-DO0 1.
End of JPM TERMINATING CUE: N2-OSP-LOG-DO0 1 review completed and results documented in Remarks Section.
RECORD STOP TIME NRC EXAM Admin SRO/JPM Conduct of Ops#2 4
March 2008
Initial Conditions:
- 1. The plant is operating at 100% power.
- 2. N2-OSP-LOG-DO01 for the daily checks log has been completed and submitted for CRS/SM review.
- 3. Ask the operator for any questions.
Initiating Cue:
(Operators name), Perform a review of N2-OSP-LOG-DOOl, Attachment 2 and document any unsatisfactory results in the Remarks Section on page 10 of N2-OSP-LOG-DOOl."
NRC EXAM Admin SRO/JPM Conduct of Ops#2 5
March 2008
10.1.12 Attachment 12, Single Control Rod Withdrawal - Hot Shutdown, was performed as required by ITS 3.10.3.
Sat 1-1 Unsat [-I NIA [-I was performed as required by ITS 3.10.4.
10.1.13 Attachment 13, Single Control Rod Withdrawal - Cold Shutdown, Sat [-I Unsat [-I NIA [-I Satisfactory. No corrective action required... [-I explanation AND ACR number in Remarks...... [-I explanation AND ACR number in Remarks...... [-I 10.1.14 ASSS/SSS Review Satisfactory. Corrective action required. Record Unsatisfactory. Immediately notify Manager Operations - Unit 2 OR his Designee. Record
/ L Person Notified Date Time Remarks :
/
ASSS/SSS Signature Date 10.2 Second Review
/
STA/SRO Signature Date Page 10 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2: DAILY CHECKS LOG ITEM Sheet 1 of 18 OPER DESCRIPTION NOTES COND LIMIT VALUE INITIALS 2
2SLS-TIC101 (Local)
Tank Temperature ITS SR 3.1.7.2
[a1 bl C4 1 - R6 0 1 STORAGE TK LEVEL ITS SR 3.1.7.1
( 2 CEC
- PNL6 0 1
)
2HTS*PNL001, C1 1 II I ITS SR 3.1.7.3 2HTS*PNL001, C1 3
[cl 2HTS*PNL003, C1 1
[dl ITS SR 3.1.7.3 2HTS*PNL003, C1 3 ITS SR 3.1.7.3 System 1
2
~
ALL H
[a1 Verify SLS tank volume using Figure 2-1 (ITS Figure 3.1.7-1)
[bl
[cl
[dl IF normal SLS Storage Tank Level indication is inoperable, obtain SLS Tank Volume as follows:
- 1)
Measure SLS Tank Level by dipping (sounding) the tank.
- 2)
Using Table 2-1, convert the Level reading obtained in 1) to a
- 3)
Record the converted Level reading as SLS Tank Volume in Item 2 Volume reading.
- 4)
Enter an explanation that this method was used to obtain SLS Tank This is Mode 1 and 2 requirement, but will be done in all Modes to ensure suction piping temperature continuously remains 2 70°F to avoid having to perform unnecessary surveillances per ITS SR 3.1.7.9.
SLS pump suction piping temperatures may be taken using a pyrometer (M&TE Issue), take temperatures directly on the piping. Enter the M&TE number AND the Cal Due Date in the Remarks Section.
Volume AND why in the Remarks Section.
Page 12 N2-OSP-LOG-DO01 Rev 11
~
T T
~
~
~
~
E N
~
2 (Cont)
DAILY CHECKS LOG CY 0 of, f
0 0
0 LTJ 4288 4418 4558.6 481 5 501 3 Net Volume (Gallans)
Page 13 N2 - OSP-LOG - 0001 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG TABLE 2-1 Gross Tank Depth (Inches) 120 12 1 122 123 124 125 126 12 7 128 12 9 Sheet 3 of 18 2 SLS*TKl Net Tank Volume Gross Tank Depth Net Tank Volume (Gal lons )
(Inches)
(Gallons) 4378 13 0 4775 4418 131 4815 4458 132 4854 4497 133 4894 4537 134 4934 4577 135 4973 4616 136 5013 4656 137 5053 4696 138 5092 4735 13 9 5132 STANDBY LIQUID CONTROL STORAGE TANK GROSS DEPTH TO NET VOLUME CORRELATION Page 14 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG Sheet 4 of 18 This page deleted Page 15 N2-OSP-LOG-DO01 R e v 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT Sheet 5 of 18 VALUE INITIALS
[gl Rad Liquid Waste Tank Level ODCM DSR 3.3.1.1-4 13 14
[hl 15 16 17 18 I
I ERF Computer Point LWSFA006 W DIS FLO TO LAKE HI RNG ODCM DSR 3.3.1.2-3.a ERF Computer Point LWSFA007 I I
I W DIS FLO TO LAKE LO RNG ODCM DSR 3.3.1.2-3.a 2SWP*FI523 LOOP B HDR FLOW TO LAKE ODCM DSR 3.3.1.2-3.c 2SWP*FI567 LOOP A HDR FLOW TO LAKE ODCM DSR 3.3.1.2-3.b 2CWS-FI147 COOLING TOWER BLOWDOWN FLOW ODCM DSR 3.3.1.2-3.d
[f 1
Indication H of Flow Periods of j5.a Release I b.0 I
[f 1 During releases via this pathway
[gl Tanks included in the specification are those outdoor tanks that:
Are NOT surrounded by liners, dikes, OR walls capable of holding the tank's contents Do NOT have tank overflows AND surrounding area drains connected to the Liquid Radwaste System For example temporary tanks.
[hl During liquid addition to the associated tank. See footnote [g].
Page 16 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT VALUE Computer Point CMSLAO2, SUPPRESSION POOL LEVEL, OR 2199.5 SP NARROW RNG LVL LTllB
[I I 1,2,3
~ 2 0 1 ITS SR 3.6.2.2.1 ERF Computer Point CMSTUlOO ITS SR 3.6.2.1.1 19 ERF Computer Point CMSLA103, 1200.1 \\q8.7 7 4 270°F
[k]
All 190°F 20 AVG SUPPR POOL WTR TEMP Sheet 6 of 18 INITIALS
[il If both computer points CMSLA02 AND CMSLA103 are inoperable OR unavailable, Suppression Pool Level may be obtained from one of the sources listed below as long as the source used is determined to be OPERABLE AND the source used is recorded in the Remarks Section.
0 2CMS*LI11A, SUPPR POOL A LEVEL 0
2CMS*LI11B, SUPPR POOL B LEVEL 0
2CMS*LI9A, SUPPR POOL WIDE RANGE LVL
[j 1
[kl The Suppression Pool Water Level range of 2199.5 to 1200.1 is provided as a normal operational band due to the HPCS suction transfer setpoint of 200.58. Operations above pool level 200.1 but less than the Technical Specification upper limit of 201 is allowable provided actions, as required, are initi.ated to restore level to the normal operational limit.
- 1)
IF ERF Computer Point CMSTUlOO is unavailable, complete.
- 2)
Suppression P o o l Water Temperature should be maintained t70°F because of Nil Ductility Transition Temperature (NDTT) considerations for the carbon steel Primary Containment Penetrations.
- 3)
The 70°F Minimum Suppression Pool Water Temperature is applicable in ALL Operational Conditions.
- 4)
The 90°F Maximum Suppression Pool Water Temperature is only applicable in Modes 1, 2 AND 3 per ITS 3.6.2.1.
Page 17 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM 21 Sheet 7 of 18 OPER DESCRIPTION NOTES COND LIMIT VALUE INITIALS AP2 A P ~ -O.&
Apt
-0.25"WG Computer Point GTSPAOl 1
-0.35"WG 2
3
[ e1 RX BLDG DIFF PRESS ITS SR 3.6.4.1.1
[ml
-0.47"WG
[ e l
- 1)
The Technical Specification limit is -0.25"WG. -0.35"WG is the Operational Limit during Non-Summer Reversal Conditions to assure that the actual AP is maintained greater than the TS limit at the highest elevation in the Reactor Building including instrument inaccuracies.
[ml
- 2)
IF Computer Point GTSPAOl is inoperable, Reactor Building AP may be obtained from one of the sources listed below as long as the source used is determined to be OPERABLE AND source used is recorded in the Remarks Section:
Computer Point GTSPAO2 0
2GTS*PDI5A, RB INSIDE/OUTSIDE DP A, on 2CEC*PNL601 2GTS*PDI5B, RB INSIDE/OUTSIDE DP B, on 2CEC*PNL601
- 3)
The Technical Specification Limit is -0.25IlWG. The -0.47"WG is the Operational Limit to assure that the actual AP is maintained throughout the Reactor Building greater than the Technical Specification Limit during Summer Reversal Conditions (Outside Air temperature greater than Reactor Bldg Bulk Weighted Average Temperature, N2-OSP-LOG-SOOl/S@ALL). If the Summer Reversal Conditions do NOT exist THEN the -0.47"WG limit is NOT applicable. (Ref. S.E.96-066 Rev 0)
During movement of recently irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, OR during Operations with a Potential for Draining the Reactor Vessel (OPDRVs). See N2-FHP-3 for OPDRV definition.
Page 18 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT 22 AVG DRYWELL TEMP CH A&B
[n]
1,2,3 1127.8OF Computer Point CMSTU05 210O0F ITS SR 3.6.1.5.1 1150°F Reactor Pressure Vessel (RPV)
[o]
222 3" 23 Water Level - Irradiated Fuel
[PI 5[rI Above Top of RPV ITS SR 3.9.6.1
[ql Flange Reactor Pressure Vessel (RPV)
Water Level - New Fuel or Control Rods ITS SR 3.9.7.1 222 3 "
Irradiated Fuel In RPV 5 [ti a o v e TOP of Lo1
[PI
[SI 24 VALUE INITIALS ro?.
8 N
&T
- 2)
IF average drywell temperature is >127.8OF, notify Engineering to evaluate current conditions of the drywell, and effects on MSIV actuators.
- 3)
Average drywell temperature must be maintained 2 100°F in Mode 1.
The lOOOF lower limit is not a Mode restraint, however, the drywell air temperature should be at least lOOOF within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into Mode 1.
[OI Enter YES OR NO in VALUE column.
[PI Perform Reactor Pressure Vessel Water Level check prior to the start of, AND at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the handling of Fuel Assemblies OR Control Rods within the Reactor Pressure Vessel.
[ql
- 1)
Technical Specification requirement is satisfied by visually
- 2) 22 '-3" above the Rx. flange is equivalent to El 352 -3 7/811.
verifying water overflowing the Reactor cavity weirs.
[rl During movement of irradiated fuel assemblies within the RPV.
[SI 22 -3" above the top of irradiated fuel seated in the RPV is equivalent to:
2 266" on Shutdown Range - 2ISC*LI105.
2 288" on Upset Range - 2ISC*LR1608.
[tl During movement of new fuel assemblies or handling of control rods within the RPV when irradiated fuel assemblies are seated within the RPV.
Page 19 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont
)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT VALUE INITIALS 25 -
26 27 28
[UI
[VI
[wl Meteorological Monitoi 2MMS-UR102 (2CEC*PNL882)
Trace A MAIN TOWER 200FT LEVEL WIND SPEED/DIRECTION TRM TRSR 3.3.10.1-1.b 2MMS -URlO 2 Trace B MAIN TOWER 200FT LEVEL WIND
( 2 CEC
- PNL 8 8 2 )
SPEED/DIRECTION TRM TRSR 3.3.10.1-2.b 2 MMS - UR10 4 Trace A MAIN TOWER 30/100 FT LEVEL WIND SPEED/DIRECTION TRM TRSR 3.3.10.1-1.a
( 2 CEC
- PNL 8 8 2 )
2MMS-UR104 (2CEC*PNL882)
Trace B MAIN TOWER 30/100 FT LEVEL WIND SPEED/DIRECTION TRM TRSR 3.3.10.1-2.a 2MMS -URlO 5 Trace C MAIN/JAF TOWER DELTA TEMPS SIGMA THETA 30 ' / 2 0 0 ' AT TRM TRSR 3.3.10.1-3
( 2 CEC* PNL8 8 2 )
ng In
[ul
[VI
[wl
- rumen At ALL Times ition N/A
- r.2 For 2MMS-UR102:
Trace A is Wind Speed in MPH (0 MPH to 100 MPH).
Trace B is Wind Direction in degrees ( O o to 360O).
(Digital readout goes from O o to 540O. For directions greater than 360°, subtract 360 from the reading to obtain Wind Direction.
)
- 1)
Verify 100 FT/30 FT switch is in the 30 FT position.
- 2)
For 2MMS-UR104:
Trace A is Wind Speed in MPH (0 MPH to 100 MPH).
Trace B is Wind Direction in degrees ( O o to 360O).
(Digital readout goes from O o to 540O. For directions greater than 360°, subtract 360 from the reading to obtain Wind Direction.
)
For 2MMS-UR105, Trace C is 30' to 200' Differential Temperature (AT) in OF (-8OF to 20OF).
Page 20 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG 30 31 32 Shee Control Rod Position Indication ITS SR 3.1.3.1 Verify all OPERABLE Control Rods comply with BPWS ITS SR 3.1.6.1 New Fuel Storage Vault (NFSV)
Covers TS License Item 2.c.3 ITEM I DESCRIPTION laal
[ab]
Lac1 See See Att 3 Att 3 1
2 3
NOTES
[OI
[XI
[OI
[Yl
[OI
[zl OPER COND ALL LIMIT ALL Rods Indicate Position Compliance with BPWS ALL Covers In Place VALUE
\\)e&
srE OD-7 Complete Attachment 3 Primary Containment AC Circuit Check 0
Enter YES OR NO in VALUE col
[XI
[Yl
[zl
[aal
[ab]
Lac1 Lmn.
10 of 1 IN IT I AL S Perform one of the following:
0 Obtain Control Rod Position Printout AND attach to this procedure.
Verify control rod position indication for all control rods using the Rod Select Matrix and verifying position indication via the 4 Rod Display.
- 1)
Not required with thermal power >lo% RTP.
- 2)
Compliance with Banked Position Withdrawal Sequence (BPWS) is satisfied with completion of N2-RESP-cZ001, Sub-section 8.5, within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 1)
Not required with NO new fuel assemblies in NFSV.
- 2)
One NFSV cover may be removed at a time such that NO more than Record switch, breaker, OR valve position(s).
TRM TRSR 3.8.2.1.2 permits 31 day verification of AC circuits inside primary containment that are de-energized by locked, sealed or otherwise secured circuit breakers in the tripped condition. Current plant configuration control does not include any circuit breakers in this configuration. Therefore TRM TRSR 3.8.2.1.2 is currently not applicable and not required to be performed at NMP2.
- 1)
Opening breaker 2WPS-PNL200-20 also opens breakers 2WPS-PNL200-22
- 2)
Opening breaker 2WPS-PNL200-26 also opens breakers 2WPS-PNL200-28 ten New Fuel Assemblies are uncovered at one time.
AND 2WPS-PNL200-24, which are the other two phases of the three phase breaker.
AND 2WPS-PNL200-30, which are the other two phases of the three phase breaker.
Page 21 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG Sheet 11 of 18 THIS PAGE INTENTIONALLY LEFT BLANK FOR ATTACHING THE PRINTOUT OF CONTROL ROD POSITIONS. (IF AVAILABLE)
Page 22 N2-OSP-LOG-DO01 R e v 11
OD-7. CONTROL ROD NOTCH POSITIONS, NEW SCAN 01/17/08 1409 NINE-MILE-2 59 48 48 48 48 48 48 48 55 48 48 48 48 48 48 48 48 48 51 48 48 48 48 48 48 48 48 48 48 48 47 48 48 48 00 48 36 48 36 48 00 48 48 48 43 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 39 48 48 00 48 40 48 00 48 00 48 40 48 00 48 48 35 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 31 48 48 48 48 00 48 48 48 48 48 00 48 48 48 48 27 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 23 48 48 00 48 40 48 00 48 00 48 40 48 00 48 48 19 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 15 48 48 48 00 48 36 48 36 48 00 48 48 48 11 48 48 48 48 48 48 48 48 48 48 48 07 48 48 48 48 48 48 48 48 48 03 48 48 48 48 48 48 48 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Page 1
ATTACHMENT 2 (Cont
)
DAILY CHECKS LOG ITEM DESCRIPTION Complete Attachment 4 34 Single Control Rod Removal Checks ITS LCO 3.10.5 Complete Attachment 5 Checks ITS LCO 3.10.6 Complete Attachment 8 ITS SR 3.4.1.1 Complete Attachment 1 0 OR 11 Verification ITS SR 3.4.3.1 35 Multiple Control Rod Removal 36 Jet Pump Loop Flow Mismatch 37 Jet Pump Operability 38 Condensate Storage TKlA Level 2CNS-LI8A OR CNSLAOl USAR 8.3.1.5.2 OPER NOTES COND LIMIT VALUE INITIALS See See Att 4 Att 4
[ad]
5 See See Att 5 Att 5 1
See See Att 8 Att 8
[ael See See
[afl 2
>33 feet 9a 1 Lag1 2
3
>3?? K 3\\.5
[ad]
Required prior to Control Rod removal per ITS SR 3.0.4.
[ael Per ITS SR 3.4.1.1, NOT required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after
[af 1
Per ITS SR 3.4.3.1, NOT required to be performed until:
both recirculation loops are in operation.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the associated recirculation loop is in operation.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after >25% RTP.
maintaining Condensate Storage Tank level to support RCIC operation during SBO event. Engineering recommendation of >33 feet is based upon the minimum required reserve capacity of 135,000 gallons plus approximately 176,000 gallons to account for NPSH requirements, level setpoint for RCIC suction swap over to suppression pool, operator response time and other factors. The 33 feet setpoint is an Alarm only and is one foot above the minimum required level of 32 feet.
This level is related to CST volume requirements specified in the USAR for CSH, ICs and SBO. If CST level falls to less than 32 feet, Engineering will determine if actual USAR required reserve capacity limits were exceeded.
[ag]
This is a Mode 1, 2, 3 requirercent based upon NMP2 SBO commitment for Page 23 N2-OSP-LOG-DOOl Rev 11
[TEM OPER DESCRIPTION NOTES COND LIMIT 39 VALUE INITIALS 40
[ f 1 41 Value
< ALERT
& Status Good 2LWS-RE206 [LWS206 1 (#8)]
Radwaste Effluent Value AND Status ODCM DSR 3.3.1.1-1 2CWS-RE157 [CWS157 1 ( # 7 0 ) 1 Cooling Tower Blowdown Value AND Status ODCM DSR 3.3.1.1-2.c 2SWP*RE146A [SW146A 1 (#82) I Service Water Effluent Value AND Status 42
[ah]
[ail
[aj 1
Service Water Effluent Value AND Status ODCM DSR 3.3.1.1-2.b
[ah]
[ a j 1
~ODCM DSR 3.3.1.1-2.a I2SWP*RE146B [SW146B 1 (#91)
]
[f 1
During releases via this pathway.
[ah]
IF the ALERT value has been exceeded OR an Equipment Failure is indicated, contact Radiation Protection AND record disposition in Remarks Section.
[ail IF the process system does NOT have flow, it is normal for the Equipment Failure to be in.
[aj]
Obtain Radiation Monitor readings from the DRMS computer. IF the DRMS computer is unavailable, readings may be obtained from the LICs (Local) OR, for Safety Related Rad Monitors, the RICs on 2CEC*PNL880.
Page 24 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT VALUE APRM Neutron Flux Level 1.2 INITIALS Mode 1:
1118%
43 APRM 1 FLUX (2CEC*PNL608)
( 2 CEC* PNLG 0 8 )
[akl (2CEC*PNL6 0 8
( 2 CEC* PNLG 0 8 )
ITS SR 3.3.1.1.2-2.a
& 2.C &
USAR 7.5.3 46 APRM 4 FLUX 47 Max Difference Items 43-46; Mode 2:
115%
( 2 CEC* PNLG 0 8 )
( 2 CEC* PNL6 0 8 )
( 2 CEC* PNLG 0 8 )
( 2 CEC* PNL6 0 8 )
52 Max Difference Items 48-51; ITS SR 3.3.1.1.2-2.b USAR 7.5.3
[akl
- 1)
During Mode 1, when thermal power is greater than or equal to 25%
of Rated Thermal Power, the APRM Flow-Biased Simulated Thermal Power Upscale Trip setpoint shall be I (0.58(W-Aw) + 59%)T, with a maximum of 1113.5% of Rated Thermal Power. Where:
T = the Ratio: Fraction of Rated Thermal Power divided by the core maximum fraction of limiting power density (CMFLPD). T is applied only if 11.0 W = the actual Recirc Loop Drive Flow ( % of rated)
AW = 0% (for two loop operation), OR AW = 5% (for single loop operation).
the recorded value should be the average between the highest AND lowest indications.
- 2)
Due to the normal oscillations which exist in APRM indications, 9$.
1 79-L 3. 5 0
See Note
[akl Within 2% b.
Page 25 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont
)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT Sheet 15 of 10 VALUE Verify APRM 1-4 indicate OK AND OPERATE ITS Table 3.3.1.1-1.2 Verify LPRM 1-4 indicate OK AND OPERATE ITS Table 3.3.1.1-1.2 APRM 1-4 receiving the Reactor Mode Switch Verify APRM 1-4 Self-Test Running ITS Table 3.3.1.1-1.2 Verify LPRM 1-4 Self-Test Running ITS Table 3.3.1.1-1.2 correct mode input from 53 54 55 (C2) 56 (C3 1
5 7 (C3 1
E01
[OI
[a01 IN IT I AL S APRM 1-4 I indicate OK-I y r s OPERATE LPRM 1-4 I indicate OK OPERATE Self -Test Running Self -Test indicates Running IF the Reactor Mode switch is in RUN, THEN, at 2CEC*PNL608, verify the following on APRM 1-4:
- 1)
RUN MODE is displayed
- 2)
The double upward pointing triangles on the FLUX bargraph are aligned to approximately 110%
IF the Reactor Mode switch is NOT in RUN, THEN, at 2CEC*PNL608, verify the following on APRM 1-4:
- 1)
SETDOWN is displayed
- 2)
The double upward pointing triangles on the FLUX bargraph are aligned to approximately :L5%
Page 26 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND Sheet 16 of 18 LIMIT VALUE INITIALS sa Verify 2/4 Logic Module 1-4 status ITS SR 3.3.1.1.2-2.f 5 9 60 Verify OPRM 1-4 appropriately enabled ITS SR 3.3.1.1.2-2.e Verify OPRM 1-4 operating cells are 221 ITS B3.3.1.1.2.e
[OI Operating cells 221 OPRM 1
[OI Enter YES OR NO in VALUE column.
[am]
Verify at each 2/4 Logic Module the 1-4 green ONLINE 1ight.s lit AND all red lights extinguished.
[an] -
APRM 1 ( 2 - 4 ) FLOW is <60%, THEN verify :
- 1)
OPRM (in inverse video) is indicated on the APRM 1 (2-4) upper-display section,
- 2)
Annunciator 603218 "OPRM TRIP ENABLED" is in alarm.
APRM 1 (2-4) FLOW is 260%, THEN verify:
- 1)
OPRM (in inverse video) is NOT indicated on the APRM 1 ( 2 - 4 )
upper-display section.
Page 27 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2
( COnt )
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT Sheet 17 of 18 VALUE INITIALS 61 62 63 64 65 Service Water System (2CEC*PNL601)
Number of operable SWP Pumps in service ITS SR 3.7.1.4
~
Computer Point SWPPA07 (SWPPA08) - PMP DISCH HDR A(B) PRESS PSIG, 2SWP*PI2A(B),
SUPPLY HEADER PRESS A(B)
(N2-OP-11 Subsection F.12.0)
~~
Computer Point SWPLA06 OR ITS SR 3.7.1.2 OR TRM TRSR 3.7.1.2 2SWP - LI 5 0 2 ( 2 CEC*PNL6 01)
Computer Point SWPTAOl OR 2SWP*TI3 1A (2CEC*PNL6 01)
ITS SR 3.7.1.3 OR TRM TRSR 3.7.1.3 Computer Point SWPTA02 OR 2 SWP* T I3 1B ITS SR 3.7.1.3 OR TRM TRSR 3.7.1.3
( 2 CEC
- PNL 6 0 1 )
Enter YES OR NO in VALUE column.
[OI 1
2 3
4 5
[a01 1
2 3
4 5
[a01
[as]
At least 4 operable SWP Pumps in service 2 63.5 psig (Applies only when < 4 operable SWP pumps in service) 2 233.1 ft.
During movement of recently irradiated fuel assemblies in the secondary containment.
- 1)
IF SWP Supply Header Discharge Water Temperature exceeds 65OF, refer to N2-OP-52, ATT. 6 for required actions if any ECCS Room Unit Coolers are inoperable.
- 2)
IF SWP Supply Header Discharge Water Temperature exceeds 75OF or 79OF, refer to N2-OP-11 Section F.14.0 for required actions AND notify SSS immediately.
- 3)
Due to readability, 2SWP*TI31A/B should not be used above 75OF. The associated computer points SWPTAO1/02 direct reading of the associated temperature elements 2SWP*TT31A/B using 4 should be used when Service Water temperature is >75OF. The 82"F/84"F value in Tech Specs 3.7.1 OR TRM 3.7.1 is the design basis analytical limit (AL), which contains no instrument uncertainty allowance. See table below for uncertainty values and maximum allowable readings. The dual Max. Allowable Readings stated below apply when Tech Spec 3.7.1 Action G is applied. TS 3.7.1 Action G requiremer-ts are applied to N2-OP-11 Section F.14.0 as directed in note 2 above. Since the other temperature limits listed in Tech Specs are not analytical limits they do not require having the instrument uncertainty applied. Note that the maximum Service Water temperature of 80.93°F/82.930F only applies during non-accident conditions. This limit SHALL NOT be used under accident conditions/post-accident conditions.
Page 28 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2
( COnt DAILY CHECKS LOG Indicators 2SWP*TI31A/B Comp. Pts. SWPTA01/02 2SWP*TT31A/B Sheet 17a of 18 k 2. 81°F 77.5OF 80.37OF k1.63OF kl. 07OF 80.93OF
- 4)
IF the Max. Allowable Readings from the table below are exceeded under any conditions, confirm maximum Service Water System discharge bay water temperature <llO°F AND Service Water Intake/Discharge delta temp is <30°F as indicated by 2SWP-FR602 These limits are specified in the NMP SPDES permit and Environmental shall be notified any time these limits are exceeded.
(located in computer room).
[as]
2HVR*UC408B performance was determined to be degraded on 6/21/2007. Until this problem is corrected (See ESL 2007-234), Unit Cooler Operability is conditinal. If SWP Supply Header Discharge Temperature is >83.6"F, declare 2HVR*UC408B Inoperable.
I Function I
OF Calculated Uncertainty I Max. Allowable Reading II
[aql IF actual temperature is below the instrumenzation downscale limit of 3S°F OR the applicant instrumentation is inoperable OR if additional instrument accuracy is required, perform Attachment 14, SWP Supply Header Discharge Water Temperature.
Carl IF SWP Supply Header Discharge Water Temperazure is 274OF. refer to N2-OP-58 for limitations on Service Water Pump Room Unit Cooler operation.
Page 28a N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT VALUE Narrow Range Level Indication (2CEC*PNL603)
INITIALS 225% RTP 66 67 68 69 Narrow Range A Narrow Range B Narrow Range C Max Difference Items 66-68 ITS SR 3.3.2.2.1 C33 -R606A C33-R606B C33 -R6 06C
[OI Enter YES OR NO in VALUE column.
[as]
- 1)
To prevent fouling of heat exchanger tubing due to settling of organisms and minerals from lake water, the heat exchanger service water side must be layed up with demineralized water if the heat exchanger is not to be used within a 14 day period.
- 2)
Determine if the heat exchanger has been operated (flow on SWP side) in the last 14 days. IF the SWP tubing has not had flow through it in the last 1 4 days, flush the SWP side of the heat exchangers per N2-OP-11.
70 2RHS"ElA SWP Tubing 71 2RHS*ElB SWP Tubing (C4)
Lo1 ALL
[as]
(C4)
Page 29 OPERATED WITH IN PAST 14 DAYS N2-OSP-LOG-DO01 Rev 11
OPER ITEM Description NOTES COND LIMIT ECCS Pump and Heat Exchanger Room Average Temperature Verification I
I IN1 TI ALS VALUE 72 Record CSL Pump Room Temperature 73 Record RHS A Pump Room Temperature Verify ECCS Room Average TemDeratUre t 7OoF 74 81 Enter higher value of Items 64 OR 65 (SWP Discharge Header TemDeratUre)
Record RHS A Heat Exchanger Room Temperature
[at1 Verify ECCS Room Avera e Tern erature > SWP Discgar e Heaser Temperature (Item 379 >
Independently verify calculation performed in item
- 79 7 5 76 77 78 79 I
7s I
Record CSH Pump Room Temperature Record RHS C Pump Room Temperature Record RHS B Pump Room Temperature Record RHS B Heat Exchanger Room Temperature Calculate AND Record Average of ECCS Room TemDeratures 1
2 3
[avl RHS A HX ROOM RHS B HX ROOM LPCS PUMP ROOM 2HVR*TIS116 2HVR*TIS115 2HVR*TIS22A 2HVR*TIS22B I
I 7a.s I HPCS PUMP ROOH RHS A PUMP RHS B PUMP RHS C PUMP ROOM ROOM ROOM 2HVR*TIS24A 2HVR*TIS23A 2HVR*TIS23C 2HVRfTIS23B 2HVR*TIS24B 2HVR*TIS23D 2HVR*TIS23F 2HRV*TIS23E E31-N608A E31-N608C (2RHS*TS1608A) (2RHS*TS1608C)
E31-N608B E31-NC08D (2RHS*TS1608B) (2RHS*TS1608D) 7 s 77.5 I w I Lo1 Enter YES OR NO in VALUE column.
Page 29a N2-OSP-LOG-DO01 Rev 11
10.1.12 10.1.13 10.1.14 10.2 2, Single Control Rod was performed as required by ITS 3.10.3 Sat [-I Unsat [-I N/A [-I 3, Single Control Rod With was performed as required by ITS 3.10.
Sat [-I Unsat [-I N/A [-I Satisfactory. No corrective ASSS/SSS Review Hot Shutdown, Cold Shutdown,
!d.
[-I Satisfactory. Corrective action required. Record Unsatisfactory. Immediately notify Manager explanation AND ACR number in Remarks......
[-I explanation AND ACR number in Remarks...... 1-1 Operations - Unit 2 OR his Designee. Record
/
/
Person Notified Date Time
/
ASSS/SSS Signature Date Second Review STA/SRO Signature Date
/
Page 10 N2 - 0 S P - IJOG-DO 01 Rev 11
ATTACHMENT 2: _DAILY CHECKS LOG I
Sheet 1 of 18 OPER DESCRIPTION NOTES COND LIMIT VALUE INITIALS I
1 1
2 3
4 5
6 C4 1 - R6 0 1 ( 2 CEC* PNL 6 0 1
)
STORAGE TK LEVEL ITS SR 3.1.7.1 2HTS*PNL001, C1 1 ITS SR 3.1.7.3 2HTS*PNL001, C1 3 ITS SR 3.1.7.3 2HTS*PNL003, C1. 1 ITS SR 3.1.7.3 2HTS*PNL003, C1 3 ITS SR 3.1.7.3 Standby Liquid Control Svstem I
I
[a3
[bl
[cl
[dl 2SLS-TIC101 (Local)
I ALL Tank Temperature ITS SR 3.1.7.2 I
270°F 2
I I
I 1
2 27 c S
Fig - I H El I
Verify SLS tank volume using Figure 2-1 (ITS Figure 3.1.7-1).
IF normal SLS Storage Tank Leve.1 indication is inoperable, obtain SLS Tank Volume as follows:
- 1)
Measure SLS Tank Level by dipping (sounding) the tank.
- 2)
Using Table 2-1, convert the Level reading obtained in 1) to a
- 3)
Record the converted Level reading as SLS Tank Volume in Item 2.
- 4)
Enter an explanation that this method was used to obtain SLS Tank This is Mode 1 and 2 requirement, but will be done in all Modes to ensure suction piping temperature continuously remains 2 70°F to avoid having to perform unnecessary surveillances per ITS SR 3.1.7.9.
SLS pump suction piping temperatures may be taken using a pyrometer (M&TE Issue), take temperatures directly on the piping. Enter the M&TE number AND the Cal Due Date in the Remarks Section.
Volume reading.
Volume AND why in the Remarks Section.
Page 12 N2-OSP-LOG-DO01 Rev 11
ATTACHMfNT 2 (Cant)
DAILY CHECKS LOG 0
0 0
FIGURE 2-1 Sheet 2 o f 18 SOBIUM-PENTABQRATF TANK VOLUME \\IS CONCENTRATION REQUIREMENTS i
i i
I I
1 i i 1
I I I
I I
i
/
I 1 -
I 0
O1 Zl 0
c3 0
Q 2
T? I g!
p T-I 4268 4418 4558.6 481 5 5Oi 3 Net Volume (Gallons)
Page 13 N2-OSP-LOG-0001 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG TABLE 2-1 S h e e t 3 of 18 STANDBY LIQUID CONTROL STORAGE TANK GROSS DEPTH TO NET VOLUME CORRELATION I
Page 14 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2
( C o n t )
DAILY C H ~ C K S LOG Sheet 4 of 18 This page deleted.
I
\\
Page 15 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHZCKS LOG CTEM Sheet 5 of 18 OPER DESCRIPTION NOTES COND LIMIT VALUE INITIALS Rad Liquid Waste Tank Level I
r -.l 13 r,- 1 14 -
15 1531 ODCM DSR 3.3.1.1-4 16 tni 17 -
18 -
[fl
[gl
[hl ERF Computer Point LWSFAOO6 ODCM DSR 3.3.1.2-3.a ERF Computer Point LWSFA007 W DIS FLO TO LAKE LO RNG ODCM DSR 3.3.1.2-3.a 2SWP*FI523 LOOP B HDR FLOW TO LAKE ODCM DSR 3.3.1.2-3.c W DIS FLO TO LAKE HI RNG 2SWP*FI567 LOOP A HDR FLOW TO LAKE ODCM DSR 3.3.1.2-3.b 2CWS-FI147 COOLING TOWER BLOWDOWN FLOW
[f 1
I O-O I Indication of Flow During Periods of Release I
I During releases via this pathway.
Tanks included in the specification are those outdoor tanks that:
Are NOT surrounded by liners, dikes, OR walls capable of holding the tank's contents Do NOT have tank overflows AND surrounding area drains connected to the Liquid Radwaste System For example temporary tanks.
During liquid addition to the associated tank. See footnote [g].
Page 16 N2-OSP-LOG-DOOl Rev 11
I ATTACHMENT 2 (Cont)
DAILY CHECKS LOG Sheet 6 of 18 11 ITEM I I
I OPER I I
I Computer Point CMSLA02, SUPPRESSION POOL LEVEL, OR 1
[i] 1 1,2,3 1 :i:::5' II SP NARROW RNG LVL LTllB
[i 1 1201 u
~ N O T E S ~
COND I LIMIT II A
I nno Crl T n m T n ITS SR 3.6.2.2.1 I
270°F [ 7 ERF Computer Point CMSTUlOO II 20 I AVG SUPPR POOL WTR TEMP If both computer points CMSLA02 AND CMSLA103 are inoperable OR unavailable, Suppression Pool Level may be obtained from one of the sources listed below as long as the source used is determined to be OPERABLE AND the source used is recorded in the Remarks Section.
0 2CMSfL111A, SUPPR POOL A LEVEL 0
2CMS*LI11B, SUPPR POOL B LEVEL 0
2CMS*LI9A, SUPPR POOL WIDE RANGE LVL The Suppression Pool Water Level. range of 2199.5 to 1200.1 is provided as a normal operational band due to the HPCS suction transfer setpoint of 200.58.
Operations above pool level 200.1' but less than the Technical Specification upper limit of 201 is allowable provided actions, as required, are initiated to restore level to the normal operational limit.
- 1)
IF ERF Computer Point CMSTUlOO is unavailable, complete.
- 2)
Suppression Pool Water Temperature should be maintained 270°F because of Nil Ductility Transition Temperature (NDTT) considerations for the carbon steel Primary Containment Penetrations.
- 3)
The 70°F Minimum Suppression Pool Water Temperature is applicable
- 4)
The 90°F Maximum Suppression Pool Water Temperature is only in ALL Operational Conditions.
applicable in Modes 1, 2 AND 3 per ITS 3.6.2.1.
Page 17 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG AP2 AP2 Computer Point GTSPAOl 1
-0.351f[
3
[ C I 21 RX BLDG DIFF PRESS ITS SR 3.6.4.1.1
[ml 0
4 7
W w
[ e 1
- 1)
The Technical Specification limit is -0.25"WG. -0.35"WG is the Operational Limit during Non-Summer Reversal Conditions to assure that the actual AP is maintained greater than the TS limit at the highest elevation in the Reactor Building including instrument inaccuracies.
- 2)
IF Computer Point GTSPAOl Is inoperable, Reactor Building AP may be obtained from one of the sources listed below as long as the source used is determined to be OPERABLE AND source used is recorded in the Remarks Section:
Computer Point GTSPA02 0
2GTS*PDI5A, RB INSIDE/OUTSIDE DP A, on 2CEC*PNL601
[ml 0
2GTS*PDI5B, RB INSIDE/OUTSIDE DP B, on 2CEC*PNL601
- 3)
The Technical Specification Limit is -0.25"WG. The -0.47"WG is the Operational Limit to assure that the actual AP is maintained throughout the Reactor Building greater than the Technical Specification Limit during Summer Reversal Conditions (Outside Air temperature greater than Reactor Bldg Bulk Weighted Average Temperature, N2-OSP-LOG-SOOl/S@ALL). If the Summer Reversal Conditions do NOT exist THEN the -0.47"WG limit is NOT applicable. (Ref. S.E.96-066 Rev 0)
During movement of recently irradiated fuel assembl.ies in the secondary containment, during CORE ALTERATIONS, OR during Operations with a Potential for Draining the Reactor Vessel (OPDRVs). See N2-FHP-3 for OPDRV definition.
Page 18 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont
)
DAILY CHECKS LOG ITEM 22 23 24 DESCRIPTION Computer Point CMSTU05 AVG DRYWELL TEMP CH A&B ITS SR 3.6.1.5.1 Reactor Pressure Vessel (RPV)
Water Level - Irradiated Fuel ITS SR 3.9.6.1 Reactor Pressure Vessel (RPV)
Water Level - New Fuel or Control Rods ITS SR 3.9.7.1 NOTES1 COND I LIMIT 2100OF 515O0F 222,311 of RPV Flange Sheet 8 of 1 I
VALUE ]INITIALS I
1
[nl
- 1)
IF Computer Point CMSTU05 IS unavailable, complete Attachment 7.
- 2)
IF average drywell temperature is >127.8OF, notify Engineering to evaluate current conditions of the drywell, and effects on MSIV actuators.
[OI
[PI
[rl
[SI
[tl
- 3)
Average drywell temperature must be maintained 2 lOOOF in Mode 1.
The lOOOF lower limit is not a Mode restraint, however, the drywell air temperature should be at least lOOOF within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entry into Mode 1.
Enter YES OR NO in VALUE column, Perform Reactor Pressure Vessel Water Level check prior to the start of, AND at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the handling of Fuel Assemblies OR Control Rods within the Reactor Pressure Vessel.
- 1)
Technical Specification requirement is satisfied by visually
- 2) 22 -3" above the Rx. flange is equivalent to El 352 -3 7/8" During movement of irradiated fuel assemblies within the RPV.
22 -3" above the top of irradiated fuel seated in the RPV.is equivalent to:
verifying water overflowing the Reactor cavity weirs.
a 2 266" on Shutdown Range - 2ISC*LI105.
0 2 288" on Upset Range - 2ISC*LR1608.
During movement of new fuel assemblies or handling of control rods within the RPV when irradiated fuel assemblies are seated within the RPV.
Page 19 N2 -0SP - LOG-DO 0 1 Rev 11
ATTACHMENT 2 (Cont
)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT VALUE 25 -
26 Meteorological Monitoring 2MMS-UR102 (2CEC*PNL882)
Trace A MAIN TOWER 200FT LEVEL WIND SPEED/DIRECTION TRM TRSR 3.3.10.1-1.b 2MMS -URlO 2 ( 2 CEC* PNL8 8 2 )
Trace B MAIN TOWER 200FT LEVEL WIND SPEED/DIRECTION TRM TRSR 3.3.10.1-2.b 2MMS-UR104 (2CEC*PNL882)
Trace A MAIN TOWER 30/100 FT LEVEL WIND SPEED/DIRECTION TRM TRSR 3.3.10.1-1.a 2 MMS - UR10 4 Trace B MAIN TOWER 30/100 FT LEVEL WIND SPEED/DIRECTION TRM TRSR 3.3.10.1-2.a
( 2 CE C
- PNL 8 8 2 )
2MMS-UR105 (2CEC*PNL882)
Trace C MAIN/JAF TOWER DELTA TEMPS SIGMA THETA 30'/200 AT TRM TRSR 3.3.10.1-3 27 In CUI
[VI
[wl 28 -
29
[ul
[VI
[wl
- rumen At ALL Times ntion N/A
\\5 3c15 a o 355 t 9 of 18 INITIALS Trace A is Wind Speed in MPH (0 MPH to 100 MPH).
Trace B is Wind Direction in degrees (0' to 360O).
(Digital readout goes from 0' to 540'.
For directions greater than 360°, subtract 360 from the reading to obtain Wind Direction. )
- 1)
Verify 100 FT/30 FT switch is in the 30 FT position.
- 2)
For 2MMS-UR104:
Trace A is Wind Speed in MPH ( 0 MPH to 100 MPH).
Trace B is Wind Direction in degrees (0' to 360').
(Digital readout goes from 0' to 540'. For directions greater than 360°, subtract 360 from the reading to obtain Wind Direction.)
For 2MMS-UR105, Trace C is 30' to 200' Differential Temperature (AT) in OF (-8OF to 20'F).
N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CH3CKS LOG NOTES 33 7==
OPER COND LIMIT
[XI
[Yl
[ZI
[aal
[ab]
tacl DESCRIPTION Control Rod Position Indication ITS SR 3.1.3.1 Verify all OPERABLE Control Rods comply with BPWS ITS SR 3.1.6.1 New Fuel Storage Vault (NFSV)
Covers TS License Item 2.c.3 Complete Attachment 3 Primary Containment AC Circuit Check TRM TRSR 3.8.2.1.1 Enter YES OR NO in VALUE co Compliance
[OI w i t h BPWS ALL Covers
[01 1 ALL 1 In Place
[zl Sheet 10 of 1 I
VALUE (INITIALS I
See Att 3 I Perform one of the following:
Obtain Control Rod Position Printout AND attach to this procedure.
Verify control rod position indication for all control rods using the Rod Select Matrix and verifying position indication via the 4 Rod Display.
0 R
- 1)
Not required with thermal power >lo% RTP.
- 2)
Compliance with Banked Position Withdrawal Sequence (BPWS) is satisfied with completion of N2-RESP-@001, Sub-section 8.5, within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 1)
Not required with NO new fuel assemblies in NFSV.
- 2)
One NFSV cover may be removed at a time such that NO more than Record switch, breaker, OR valve position ( s ).
TRM TRSR 3.8.2.1.2 permits 31 day verification of AC circuits inside primary containment that are de-energized by locked, sealed or otherwise secured circuit breakers in the tripped condition. Current plant configuration control does not include any circuit breakers in this configuration. Therefore TRM TRSR 3.8.2.1.2 is currently not applicable and not required to be performed at NMP2.
- 1)
Opening breaker 2WPS-PNL200-20 also opens breakers 2WPS-PNL200-22
- 2)
Opening breaker 2WPS-PNL20C-26 also opens breakers 2WPS-PNL200-28 ten New Fuel Assemblies are uncovered at one time.
AND 2WPS-PNL200-24, which are the other two phases of the three phase breaker.
AND 2WPS-PNL200-30, which are the other two phases of the three phase breaker.
Page 21 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG Sheet 11 of 1 8 THIS PAGE INTENTIONALLY LEFT BLANK FOR ATTACHING THE PRINTOUT OF CONTROL ROD POSITIONS. (IF AVAILABLE)
Page 22 N2-CSP-LOG-DO01 Rev 11
OD-7. CONTROL ROD NOTCH POSITIONS, NEW SCAN 01/17/08 1409 NINE-MILE-2 59 48 48 48 48 48 48 48 5 5 48 48 48 48 48 48 48 48 48 5 1 48 48 48 48 48 48 48 48 48 48 48 47 48 48 48 00 48 36 48 36 48 00 48 48 48 43 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 39 48 48 00 48 40 48 00 48 00 48 40 48 00 48 48 35 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 3 1 48 48 48 48 00 48 48 48 48 48 00 48 48 48 48 27 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 23 48 48 00 48 40 48 00 48 00 48 40 48 00 48 48 19 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 1 5 48 48 48 00 48 36 48 36 48 00 48 48 48 11 48 48 48 48 48 48 48 48 48 48 48 07 48 48 48 48 48 48 48 48 48 03 48 48 48 48 48 48 48 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 Page 1
DESCRIPTION Complete Attachment 4 Single Control Rod Removal Checks ITS LCO 3.10.5 Complete Attachment 5 Multiple Control Rod Removal Checks ITS LCO 3.10.6 Complete Attachment 8 Jet Pump Loop Flow Mismatch ITS SR 3.4.1.1 Complete Attachment 10 OR 11 Jet Pump Operability Verification ITS SR 3.4.3.1 Condensate Storage TKlA Level 2CNS-LI8A OR CNSLAOl USAR 8.3.1.5.2 ATTACHMENT 2 (Cont
)
DAILY CHECKS LOG NOTES COND
[ad1 5
1 2
1
[ae]
[afl 1
2 Lag1 3
[ad1
[ael
[afl
[agl LIMIT See Att 4 See Att 5 See Att 8 See Att 10 OR 11
>33 fe -xJ[
Sheet 12 of 1
-GJLzL Att 4
____I See 1
Att 5 See I Att 10 3 Required prior to Control Rod removal per ITS SR 3.0.4.
Per ITS SR 3.4.1.1, NOT required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after both recirculation loops are in operation.
Per ITS SR 3.4.3.1, NOT required to be performed until:
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the associated recirculation loop is in operation.
0 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after >25% RTP.
This is a Mode 1, 2, 3 requirement based upon NMP2 SBO commitment for maintaining Condensate Storage Tank level to support RCIC operation during SBO event. Engineering recommendation of >33 feet is based upon the minimum required reserve capacity of 135,000 gallons plus approximately 176,000 gallons to account for NPSH requirements, level setpoint for RCIC suction swap over to suppression pool, operator response time and other factors. The 33 feet setpoint is an Alarm only and is one foot above the minimum required level of 32 feet.
This level is related to CST volume requirements specified in the USAR for CSH, ICs and SBO.
If CST level falls to less than 32 feet, Engineering will determine if actual USAR required reserve capacity limits were exceeded.
Page 23 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHZCKS LOG OPER COND LIMIT VALUE INITIALS 39 C TEM I
Radiation 2LWS-RE206 [LWS206 1 ( # a 1 1 DESCRIPTION Radwaste Effluent Value AND Status 40 41 -
42 -
[fl
[ah3
[ail
[aj 1
ODCM DSR 3.3.1.1-1 2CWS-RE157 [CWS157 1 ( # 7 0 ) I Cooling Tower Blowdown Value AND Status 2SWP*RE146A [SW146A 1 (#82)
I Service Water Effluent Value AND Status ODCM DSR 3.3.1.1-2.c ODCM DSR 3.3.1.1-2.a 2SWP*RE146B [SW146B 1 (#91) 1 Service Water Effluent Value AND Status ODCM DSR 3.3.1.1-2.b gOTES
)nit01
[ah1
[ail
[aj 1
[ah]
[aj I
[f 1
c Value ALERT r{
& Status Good G.3$ \\&
During releases via this pathway.
IF the ALERT value has been exceeded OR an Equipment Failure is indicated, contact Radiation Protection AND record disposition in Remarks Section.
IF the process system does NOT have flow, it is normal for the Equipment Failure to be in.
Obtain Radiation Monitor readings from the DRMS computer. IF the DRMS computer is unavailable, readings may be obtained from the LICs (Local) OR, for Safety Related Rad Monitors, the RICs on 2CECXPNL880.
Page 24 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT VALUE INITIALS APRM 3 STP I1 49 I ( 2 CEC* PNL6 0 8 )
43 44 45 46 47 APRM 1 FLUX
( 2 CEC*PNL6 0 8 )
APRM 3 FLUX
( 2 CEC* PNL6 0 8 )
APRM 2 FLUX
[akl (2
CEC*PNL6 0 8 )
1,2 APRM 4 FLUX
( 2 CEC* PNL 6 0 8 )
Max Difference Items 43-46; ITS SR 3.3.1.1.2-2.a
& 2.c &
USAR 7.5.3
( 2 CEC* PNL6 0 8 )
Mode 1:
1118%
( 2 CEC* PNL6 0 8 )
( 2 CEC* PNL6 08 )
Max Difference Items 48-51; ITS SR 3.3.1.1.2-2.b &
USAR 7.5.3 Within 2%
[akl
- 1)
During Mode 1, when thermal power is greater than or equal to 25%
of Rated Thermal Power, the APRM Flow-Biased Simulated Thermal Power Upscale Trip setpoint shall be I (0.58(W-AW) + 59%)T, with a maximum of 5113.5% of Rated Thermal Power. Where:
T = the Ratio: Fraction of Rated Thermal Power divided by the core maximum fraction of 1j.miting power density (CMFLPD). T is applied only if 11.0 W = the actual Recirc Loop Drive Flow ( % of rated)
AW = 0% (for two loop operation),
AW = 5% (for single loop operation).
Due to the normal oscillations which exist in APRM indications, the recorded value should be the average between the highest AND lowest indications.
- 2)
N2 - OSP - LOG - DO 0 1 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM DESCRIPTION Sheet 15 of 18 OPER NOTES COND LIMIT VALUE 53 5 4 55 (C2) 56
( C 3 )
57
( C 3 )
[OI
[at1 Verify APRM 1-4 indicate OK E
OPERATE ITS Table 3.3.1.1-1.2 Verify LPRM 1-4 indicate OK E
OPERATE ITS Table 3.3.1.1-1.2 APRM 1-4 receiving the correct mode input from Reactor Mode Switch Verify APRM 1-4 Self-Test Running ITS Table 3.3.1.1-1.2 Verify LPRM 1-4 Self-Test Running ITS Table 3.3.1.1-1.2
[ol APRM 1-4 indicate OK a OPERATE indicate OPERATE SEE NOTE
[a01 Self -Test.
indicates Running Self -Test indicates Running LPRM 1-4 OK IN I TIALS Enter YES OR NO in VALUE column.
IF the Reactor Mode switch is in RUN, THEN, at 2CEC*PNL608, verify the following on APRM 1-4:
- 1)
RUN MODE is displayed
- 2)
The double upward pointing triangles on the FLUX bargraph are aligned to approximately 118%
IF the Reactor Mode switch is NOT in RUN, THEN, at 2CEC*PNL608, verify the following on APRM 1-4:
- 1)
SETDOWN is displayed
- 2)
The double upward pointing triangles on the FLUX bargraph are aligned to approximately 15%
Page 26 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT VALUE INITIALS
[OI Enter YES OR NO in VALUE column.
[am]
Verify at each 2/4 Logic Module the 1-4 green ONLINE lights lit AND all red lights extinguished.
[an] -
APRM 1 (2-4) FLOW is <60%, THEN verify:
- 1)
OPRM (in inverse video) is indicated on the APRM 1 (2-4) upper-
- 2)
Annunciator 603218 "OPRM TRIP ENABLED" is in alarm.
APRM 1 (2-4) FLOW is 260%, THEN verify:
- 1)
OPRM (in inverse video) is NOT indicated on the APRM 1 (2-4) display section, =
upper-display section.
58 5 9 60 Page 27 Verify 2/4 Logic Module 1-4 status See Note 1,2
[am1 w
Y fA ITS SR 3.3.1.1.2-2.f Verify OPRM 1-4 appropriate 1 y See Note enabled
[OI
[an]
ITS SR 3.3.1.1.2-2.e Verify OPRM 1-4 Operating operating cells cells 221 are 221 for each y e ITS B3.3.1.1.2.e OPRM 1
N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER DESCRIPTION NOTES COND LIMIT VALUE Service Water System (2CEC*PNL601) 61 6 2 63 6 4 6 5 Number of operable SWP Pumps in service ITS SR 3.7.1.4 Computer Point SWPPAO7 (SWPPA08) - PMP DISCH HDR A(B) PRESS PSIG, 2SWP*PI2A(B),
SUPPLY HEADER PRESS A (B)
(N2-OP-11 Subsection F. 12.0)
Computer Point SWPLAO6 OR ITS SR 3.7.1.2 OR TRM TRSR 3.7.1.2 2 SW P - LI 5 0 2 ( 2 CEC
- PNLG 0 1
)
Computer Point SWPTAOl OR 2SWP*TI3 1A (2CEC*PNL6 01 )
ITS SR 3.7.1.3 OR TRM TRSR 3.7.1.3 Computer Point SWPTA02 OR 2 SWP*TI 3 1B ITS SR 3.7.1.3 OR TRM TRSR 3.7.1.3
( 2 CEC* PNLG 0 1 )
[OI 1
2 3
4 5
[a01 1
2 3
4 5
[a01
[as1 At least 4 operable SWP Pumps in servicc 2 63.5 psig (Applies only when < 4 operable SWP pumps in service) 165OF c740F c 7 5 O F 577.50F c79OF 580.37OF 182OF 583.6OF 580.930~
60.8
?t 17 of IN1 T I ALS 8
Enter YES OR NO in VALUE column.
During movement of recently irradiated fuel assemblies in the secondary containment.
- 1)
IF SWP Supply Header Discharge Water Temperature exceeds 6SoF, refer to N2-OP-52, A T T. 6 or required actions if any ECCS Room Unit (Coolers are inoperable.
- 2)
IF SWP Supply Header Discharge Water Temperature exceeds 75OF or 79OF, refer to N2-O?-11 Section F.14.0 for required actions AND notify SSS immediately.
31 Due to readability, 2SW?*TI31A/B should not be used above 75OF. The associated computer points SW?TAO1/02 direct reading of the associated temperature elements 2SWP*TT31A/B using Attachment. 14 should be used when Service Water temperature is >75OF. The 82OF/84'F value in Tech Specs 3.7.1 OR TRM 3.7.1 is the design basis analytical limit (AL), which contains no instrument uncertainty allowance. See table below for uncertainty values and maximum allowable readings. The dual Max. Allowable Readings stated below apply when Tech Spec 3.7.1 Action G is applied. TS 3.7.1 Action G requirements are applied to N2-OP-11 Section F.14.0 as directed in note 2 above. Since the other temperature limits listed in Tech Specs are not analytical limits they do not require having the instrument uncertainty applied. Note that the maximum Service Water temperature of 80.93°F/82.930F only applies during non-accident conditions. This limit SHALL NOT be used under accident condit:Lons/post-accident conditions.
Page 28 N2-OSP-LOG-DO01 Rev 11
ATTACHMENT 2 (Cont)
DAILY CH:ECKS LOG Indicators 2SWP*TI31A/B Comp. Pts. SWPTA01/02 2SWP*TT31A/B Sheet 17a of 18 5 2. 81°F 77.5OF
+1.63OF 80.37OF
+1. 07OF 80.93OF
- 4)
IF the Max. Allowable Readings from the table below are exceeded under any conditions, confirm maximum Service Water System discharge bay water temperature < l l O " F AND Service Water Intake/Discharge delta temp is S 3 0 ° F as indicated by 2SWP-FR602 (located i n computer room).
These limits are specified in the NMP SPDES permit and Environmental shal.1 be notified any time these limits are exceeded.
[as1 2HVRtUC408B performance was determined to be (degraded on 6/21/2007. Until this problem is corrected (See ESL 2007-234), Unit Cooler Operability i.; conditinal. If SWP Supply Header Discharge Temperature is >83.6"F, declare 2HVR*UC408B Inoperable.
II Function I
OF Calculated Uncertainty I Max. Allowable Reading 11 Page 28a N2-OSP-LOG-DO01 Rev 11
ATTACHNENT 2 (Cont)
DAILY CHECKS LOG ITEM OPER VALUE INITIALS DESCRIPTION NOTES COND LIMIT C33-R606A C33 -R606B 70
((24) 71 (C4) 68 Narrow Range C C3 3 -R6 06C I
2RHS*ElA SWP Tubing 7
[OI ALL OPERATED WITHIN vH
[as]
PAST 14 DAYS 2RHS*ElB SWP Tubing Max Difference Items 66-68 69 I ITS SR 3.3.2.2.1 I -1 2 2 5 % RTP 52 02.3 I
Within 4" RHS Heat Exchanser Tubesi.de LavuD Status
[ O I Enter YES OR NO in VALUE column.
[as]
- 1)
To prevent fouling of heat exchanger tubing due to settling of organisms and minerals from lake water, the heat exchanger service water side must be layed up with demineralized water if the heat exchanger is not to be used within a 14 day period.
- 2)
Determine if the heat exchanger has been operated (flow on SWP side) in the last 14 days. IF the SWP tubing has not had flow through it in the last 14 days, flush the SWP side of the heat exchangers per N2-OP-11.
Page 29 N2-OSP-LOG-DO01 Rev 11
RHS A HX ROOM 2HVR*TIS116 N2-OSP-LOG-DO01 Rev 11 RHS B HX ROOM LPCS PUMP ROOM HPCS PUMP ROOM RHS A PUMP RHS B PUMP RHS C PUMP ROOM ROOM ROOM 2HVR'TISlIS 2HVRtTIS22A 2HVR*TIS24A 2HVR*TIS23A 2HVR*TIS23C 2HVR*TIS23B 2HVR*TIS22B ZHVR'TIS24B 2HVR*TIS23D 2HVR*TIS23F 2HRV*TIS23E E31-N608A E31-N6C8C (2RHS*TS1608A) (2RHS*TS1608C)
E31-N608B E31-N6C8D (2RHS*TS1608B) (2RHS*TS1608D)
Constellation Energy Group OPERATOR JOB PEWORMANCE MEASURE
Title:
Clearance Section Review Revision: NRC 2008 Task Number:
Approvals :
General Supervisor Date General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer:
(SRO)
TrainedEvaluator :
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA Expected Completion Time: 30 minutes Time Critical Task: NO Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:-
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments :
Evaluator Signature:
Date:
NRC EXAM Admin SRO/JPM Equip Control 1
March 2008
Recommended Start Location: (Completion time based on the start location)
Any appropriate location with the required Reference Material.
Simulator Set-up:
None Directions to the Instructor/Evaluator:
To be performed as an administrative JPM.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.
Notes to Instructor / Evaluator:
- 1.
- 2.
During Evaluated JPM:
- 3.
During Training JPM:
Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted by a *.
Self-verification shall be demonstrated.
0 Self-verification shall be demonstrated.
0 No other verification shall be demonstrated.
References:
- 1. GAP-OPS-02, Control Of Hazardous Energy, Clearance, and Tagging
- 2. Drawings: EE-lQ, EE-lAU, P&IDs 31C, 31F and 32A
- 3. General Knowledges and Ability 2.2.13(3.8) 2.2.15(2.9)
Tools and Equipment:
- 1.
None Task Standard:
Clearance section review is completed and designated errors are identified and documented.
NRC EXAM Admin SRO/JPM Equip Control 2
March 2008
Initial Conditions:
I Performance Steps I Standard
- 1. The plant is operating at 100% power.
- 2. Maintenance has requested a clearance section to replace the pump seals for 2RHS*PlA.
- 3. A manual clearance section has been generated and is ready for review.
- 4. Ask the operator for any questions.
Grade I Comments Initiating cue:
(Operators name), Perform a review of the clearance section for 2RHS*PlA and document on the clearance request any changes required.
- 1. Provide repeat back of initiating Proper communications used for repeat SaWnsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary.
CUE: If asked how to document state they should RECORD START TIME -
.Obtain a copy of clearance section for review. Evaluator to provide Candidate a copy of clearance section and referenced drawings.
Clearance section is obtained and referenced.
NRC EXAM Admin SRO/JPM Equip Control 3
March 2008
- 2. Review the clearance request.
Reviews clearance request and identifies the following errors:
. Tags #4 and 5 are out of order (should be last)
. Tag #5 is on the wrong pump (2RHS*P 1B)
. Tag #13 is in wrong position (correct position is closed)
. Clearance does not include tags on normal suction path to pump (2RHS*MOVlA - valve and power
. Keep fill is NOT isolated and tagged supply)
(RHS*V265)
- 3. Errors identified and noted on the clearance section.
clearance section.
All identified errors documented on the Pass/Fail End of JPM TERMINATING CUE: The clearance section has been reviewed and designated errors identified and documented.
RECORD STOP TIME I
Satfl-Jnsat 1
NRC EXAM Admin SRO/JPM Equip Control 4
March 2008
Initial Conditions:
- 1. The plant is operating at 100% power.
- 2. Maintenance has requested a clearance section to replace the pump seals for 2RHSPlA.
- 3. A manual clearance section has been generated and is ready for review.
- 4. Ask the operator for any questions.
Initiating Cue:
(Operators name), Perform a review of the clearance section for 2RHS*PlA and document on the clearance request any changes required.
NRC EXAM Admin SRO/JPM Equip Control 5
March 2008
ATTACHMENT 5: CLEARANCE REQUEST FORM CLEARANCE REQUEST FORM Unit 2
Date of Request T
O b
Type of Clearance
! Danger
! Operating Permit
! Caution Equipment and System to be Worked:
Work Controlling Document No./Description of Work: R e p l a c e Pump seals 2RHS*P1 A Suggested Clearance Tagging Points (May Not Be Required):
Hazards Associated with the Work to be Performed:
Potential Adverse Effects:
Rotatinn eauiDment & floodinn Other Systems Affected:
Grounds Required:
YES ! a Starting Time Date Duration Reference Drawings(s) EE-IQ, EE-IAU, P&ID 31C, P&ID 31F, P&ID 32A Clearance to be held by: Joe Bearing 21 21 Name($
Phone(@
Name Phone RequesterlPlanner:
Jim Mechanic 2334 Recommended Clearance Boundary:
Operations Review:
Erns Livin Today Name Date Assigned by E-L.
Today Initial Date
ATTACHMENT 6: CLEARANCE SHEET CLEARANCE SHEET CLEARANCE NO.
Page of WORK ORDERS and ACRs:
PREPARED BY Joe Bearing REVIEWED BY Erns Livin APPROVED BY ISSUED BY RELEASE MODIFIED GROUNDS AND GROUND DANGER TAGS REMOVED RELEASE REVIEWED & APPROVED PLACEMENT INSTRUCTIONS:
2ENS*SWG101-3 BKR TO BE OPEN & RACKED OUT DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
CAUTION TAG INFORMATION:
RELEASED RELEASE INSTRUCTIONS:
DATE:
TIME:
SEAL REPLACEMENT COMPLETE.
2ENS*SWG101-3 BKR TO BE RACKED IN & OPEN.
CLEARANCE SHEET Component to be Worked:
Equipment ID EauiDment DescriDtion Page 1 of 2 CLEARANCE NO.
2RHS007 Place.
I Place. I Place. I Rest.
Tag Serial No.
001 Place.
Seq.
1 Notes SYSTEM SYSTEM Config Config.
1 st 2nd Seq.
Verifier Verifier 3
Config.
1 st 2nd Seq.
Verifier Verifier 3
Equipment Location 2RHS"PlA CONTROL SWITCH REFERENCE CONT. RM. PNL 601 REFERENCE AN601431 CONT. RM. PNL 601 HANDLE PWR TO 2RHS*PlA CONT. BLDG. 261' 2RHS*V312 SUCT. STR. DRAIN PRHS*PIA ROOM 175' 2RHS*V420B 2RHS*P1 B VENT.
2ENS*SWGIOI-3 ELEVATE 002 1
BREAKER OPEN &
RACKED IN CLOSED &
CAPPED OPEN &
RACKED OUT UNCAPPED 003 DANGER 1
DANGER 004 2
t DANGER CLOSED I 2
005 006 2RHS*PlB ROOM 175' 2RHS*MOV2A CONT. SW.
I DANGER CLOSED 1 3
CONT. SW. FOR SRHS*MOVZA CONT. RM. PNL 601 2RHS*MOV4A CONT. SW.
2RHS*PIA MIN. FLOW VLV.
CONT RM. PNL 601 PWR TO 2RHS*MOV4A CONT. BLDG. 261' PWR TO SRHS*MOVZA ZEHS*MCC103-20C ZEHS*MCC103-20B I
DANGER OPEN I
007 3
-I-T 008 DANGER ON I
3 I
+I CLOSED ON I
3 DANGER DANGER 009 01 0 CONT. BLDG. 261' ZRHS*MOVZA I
SUCT TO 2RHS*PlA 2RHS*PlA ROOM 175' CLOSED I 3
I Page 3 GAP-OPS-02 Rev 25
ATTACHMENT 7: TAG LIST CLEARANCE SHEET CLEARANCE NO.
2RHS007 Page 2 of 2 Component to be Worked:
Equipment ID Equipment Description Equipment Location 2CSL*HCV119 SUCT TO 2CSL*P1 2CSL*P1 ROOM 175 2RHS*MOV4A 2RHS*PlA MIN. FLOW 2RHS*PlA ROOM 175 2RHS*V4 2RHS*PlA DISCH. VLV.
2RHS*PlA ROOM 175 2RHS*V39 2RHS*PlA SUCT HDR DRAIN TO RADWASTE 2RHS*PlA ROOM 175 Tag Serial No.
01 I Place.
Config.
DANGER 1 3 I CLOSED 01 2 DANGER 1 3
1 CLOSED 013 1 DANGER I 3
1 OPEN Place.
1 st Verifier Place 2nd Verifil
~
Rest.
Seq.
2 2
2 -
2 Rest.
Config CLOSED OPEN LOCKED OPEN LOCKED CLOSED Rest.
1 st Verifier Rest.
2nd Verifier Tag Notes Page 4 GAP-OPS-02 Rev 25
ATTACHMENT 5: CLEARANCE REQUEST FORM CLEARANCE REQUEST FORM Unit 2
Date of Request T
O b
Type of Clearance
! Danger
! Operating Permit
! Caution Equipment and System to be Worked:
Work Controlling Document No./Description of Work: -Replace Pump seals 2RHS*P1 A Suggested Clearance Tagging Points (May Not Be Required):
Hazards Associated with the Work to be Performed:
Potential Adverse Effects:
Rotatinn eUuiDment floodinn Other Systems Affected:
Grounds Required:
YES !
Starting Time Date Duration Reference Drawings(s) EE-IQ, EE-IAU, P&ID 31C, P&ID 31F, P&ID 32A Clearance to be held by: Joe Bearing 21 21 Name(s)
Phone($
RequesterlPlanner:
Jim Mechanic 2334 Name Phone Recommended Clearance Boundary:
Operations Review:
Erns Livin Today Clearance No.
2RHS007 Assigned by E-L-Today Initial Date Name Date
I CLEARANCE SHEET ATTACHMENT 6: CLEARANCE SHEET
~
CLEARANCE NO.
Page of PREPARED BY Joe Bearina REVIEWED BY Erns Livin APPROVED BY ISSUED BY RELEASE MODIFIED GROUNDS AND GROUND DANGER TAGS REMOVED RELEASE REVIEWED & APPROVED RELEASED WORK ORDERS and ACRs:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
DATE:
TIME:
I PLACEMENT INSTRUCTIONS:
2ENS*SWG101-3 BKR CAUTION TAG INFORMATION:
RELEASE INSTRUCTIONS:
SEAL REPLACEMENT COMPLETE.
2ENS*SWG101-3 BKR TO BE RACKED IN & OPEN.
CLEARANCE SHEET Component to be Worked:
Equipment ID Equipment Description CLEARANCE NO.
2RHS007 Equipment Location 2RHS*PIA CONTROL SWITCH Place.
Place.
Place.
Place.
Rest.
Rest.
Rest.
Seq.
Config.
1 st 2nd Seq.
Config 1 st Verifier Verifier Verifier CONT. RM. PNL 601 AN601431 CONT. RM. PNL 601 HANDLE PWR TO 2RHS*PIA 2ENS*SWG101-3 ELEVATE Rest.
Tag 2nd Notes Verifier RHR CON3 BLDG. 261' 2RHS*V312 7
1 SUCT. STR. DRAIN 2RHS*PIA ROOM 175' SYSTEM INOP RHR 3
m s "
1 CONT. SW. FOR SRHS*MOVZA CONT. RM. PNL 601 2RHS*MOV4A CONT. SW.
2RHS*PlA MIN. FLOW VLV.
SYSTEM INOP 3
BREAKER OPEN &
OPEN &
RACKEDOUT RACKEDIN BREAKER CONT RM. PNL 601 SEHS*MCC103-20C 3,d PWR TO 2RHS*MOV4A CONT. BLDG. 261' PWR TO ZRHS*MOVZA CONT. BLDG. 261' 2RHS* MOV2A SUCT TO 2RHS*PlA 2RHS*PlA ROOM 175' SEHS*MCC103-20B
~~~
OPEN &
L'tOStU &
UNCAPPED 1
CAPPED Tag Serial No.
001 002 003 -
004 005 -
006 007 008 009 01 0 REFERENCE REFERENCE DANGER -
DANGER DANGER DANGER DANGER DANGER DANGER DANGER Page 1 of 2 I
I 1
CLOSED 1
2 1
CLOSED 1
I I
I I
I I
I I
I wp' 1
CLOSED 1
I 2
1 OPEN I
CLOSED Page 3 GAP-OPS-02 Rev 25
ATTACHMENT 7: TAG LIST c
CLEARANCE SHEET Page 2 of 2 CLEARANCE NO.
2RHS007
- omDonent to be Worked:
iquipment ID fquipment Description fquipment Location 2CSL*HCV119 SUCT TO 2CSL*P1 2CSL*P1 ROOM 175' 2RHS*MOV4A PRHS*PIA MIN. FLOW 2RHS*PIA ROOM 17-2RHS*V4 ZRHS*PIA DISCH. VLV.
ZRHS*PIA ROOM 175' ZRHS*PIA SUCT HDR DRAIN TO RADWASTE ZRHS*PIA ROOM 175' 2RHS"V39 a rr6SSt-u m s a uscut Place. I Place.
I Place. I Place.
Seq.
Config.
1 st 2nd Verifier Verifier LOCKED 1
CLOSED 1 Page 4 Rest.
Rest.
Config 2
LOCKED CLOSED I
I I
I I
I I
I t I
GAP-OPS-02 Rev 25 Tag Notes
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE;,
Title:
Task Number: 3439100303 Generate and approve an Emergency Exposure Authorization Revision: NRC 2008 Approvals:
General Supervisor Date General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer:
(SRO)
TrainedEvaluator :
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA Expected Completion Time: 20 minutesTime Critical Task: NO Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:-
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:
Date:
NRC EXAM Admin SRO/JPM Rad Control 1
March 2008
Recommended Start Location: (Completion time based on the start location)
Any appropriate location with the required Reference Material.
Simulator Set-up:
None Directions to the Instructor/Evaluator:
To be performed as an administrative JPM. A calculator should be available or be provided.
Directions to Operators:
Read Before Even, JPM Performance:
For the performance of this JPM, I will function as the Radiation Protection, the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.
Notes to Instructor / Evaluator:
- 1.
- 2.
During evaluated JPM:
- 3.
During training JPM:
Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted by a ".".
Self-verification shall be demonstrated.
0 Self-verification shall be demonstrated.
0 No other verification shall be demonstrated.
References:
- 1. EPIP-EPP-15
- 2. WA 2.3.4 (3.1), Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Tools and Equipment:
- 1. Calculator Task Standard:
Generate and approve an Emergency Exposure Authorization Form and estimate exposure.
NRC EXAM Admin SRO/JPM Rad Control 2
March 2008
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
- 5.
You have assumed the responsibilities of the Shift ManagedEmergency Director.
Entry to the reactor building is required to manually close ICS*MOV121 (time to complete the task will be approximately 12 minutes).
A RCIC steam leak into the Reactor Building can not be isolated without manually shutting ICS*MOV121.
Radiation levels at the valve are as high as 27 R/hr.
Three (3) individuals are available to perform the task.
Worker A is a volunteer that has previously received a planned special exposure at another facility (TLD #1, Employee # - 00001, SSN: 11 1-1 1-1 1 11).
Worker B is a volunteer who is an experienced Licensed Reactor Operator and is a declared pregnant worker (TLD #2, Employee # - 00002, SSN: 222-Worker C is a volunteer who is an experienced Licensed Reactor Operator that has received a dose of 1500 mR this year (TLD #3, Employee # 00003, 22-2222).
Ask the operator for any questions.
SSN: 3 3 3-3 3 -3 333).
- 6.
Initiating Cue:
(Operators name), choose an individual to close ICS*MOV12 1, estimate the expected radiation exposure and document your authorization for an Emergency Exposure.
- 1. Provide repeat back of initiating Proper communications used for repeat SatAJnsat cue. Evaluator Acknowledge back (GAP-OPS-01).
repeat back providing correction if necessary RECORD START TIME -
- 2..Obtain a copy of the reference EPP-EPP-15 is obtained and SatAJnsat procedure and reviewhtilize the correct section.
Attachments 1 and 1-1 are referenced.
NRC EXAM Admin SRO/JPM Rad Control 3
March 2008
I
- 3..Determines the expected exposure for the task
- 4..Selects the best worker to perform the task.
- 5..Determines workers exposure limit.
EXAMINER NOTE: The authorized Exposure limit may be 25 R or less based on whether the candidate limits the volunteers exposure to the anticipated stay time (12 min) or a recommendation from RP.
CUE: If asked, inform the candidate that RP recommends limiting the exposure to 24 minutes.
Calculates that a 12 minute exposure in a 27 R/hr field will cause a dose of 5.4 R.
0 Since the action is required to limit dose to the public, 25 R is the limit.
5.4 R is well within the 25 R limit.
0 Determines the best worker for the task Worker A has previously received a planned special exposure Worker B is a declared pregnant worker Worker C is an experienced Licensed Reactor Operator 0
Worker C is assigned to close the valve.
NRC EXAM Admin SRO/JPM Rad Control The absolute exposure limit for the job is 25 R. If the recommendation of RP is used the limit is 10.8 R. If the limit is based on a stay time of 12 minutes the exposure limit is 5.4 R.
Pass/Fail Passmail SaWnsat 4
March 2008
CUE: The Candidate may choose to brief the worker on Radiological conditions, potential for steam leakage in the area, planned task, applicable ALARA measures, and contingency measures, CUE: The Candidate may ask for an RWP to be generated.
- 6..Generates an Emergency Exposure Authorization form.
CUE: Roleplay as Worker C and acknowledge the briefing.
CUE: Role play as RP and state that an R WP has been generated.
0 0
Candidate completes Section A.
Candidate obtains a copy of EPIP-EPP-15 Attachment 1-1.
Pas s/Fail End of JPM TERMINATING CUE: When the Candidate completes the Emergency Exposure Authorization Form.
RECORD STOP TIME NRC EXAM Admin SRO/JPM Rad Control 5
March 2008
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
- 5.
You have assumed the responsibilities of the Shift ManagedEmergency Director.
Entry to the reactor building is required to manually close ICS*MOV121 (time to complete the task will be approximately 12 minutes).
A RCIC steam leak into the Reactor Building can not be isolated without manually shutting ICS*MOV121.
Radiation levels at the valve are as high as 27 Whr.
Three (3) individuals are available to perform the task.
0 Worker A is a volunteer that has previously received a planned special exposure at another facility (TLD #1, Employee # - 00001, SSN: 11 1-1 1-1 11 1).
Worker B is a volunteer who is an experienced Licensed Reactor Operator and is a declared pregnant worker (TLD #2, Employee # - 00002, SSN: 222-22-2222).
Worker C is a volunteer who is an experienced Licensed Reactor Operator that has received a dose of 1500 mR this year (TLD #3, Employee # 00003, SSN: 333-33-3333).
0 0
Ask the operator for any questions.
- 6.
Initiating Cue:
(Operators name), choose an individual to close ICS*MOV121, estimate the expected radiation exposure and document your authorization for an Emergency Exposure.
NRC EXAM Admin SRO/JPM Rad Control 6
March 2008
I
1 Page 9
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Event Classification, Notifications and Reclassification Revision: NRC 2008 Task Number:
Approvals:
General Supervisor Date General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer:
( S W Trainer/Evaluator :
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA Expected Completion Time: 45 minutesTime Critical Task: YES Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:-
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments :
Evaluator Signature:
Date:
NRC EXAM Admin SRO/JPM Emergency PrPlan 1
March 2008
I Recommended Start Location: (Completion time based on the start location)
Unit 2 Control Room or Simulator t Simulator S e t-up :
None Directions to the Instructor/Evaluator:
To be performed as an administrative JPM. Ideally this JPM should be performed in the Control Room or Simulator to provide adequate procedural resources. If this JPM cannot be performed in one of these locations, then the complete SM/ED Checklist Package must be provided to the Candidate.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the Unit 1 SM, Security Supervisor, Communication Aid, and other personnel as necessary. Prior to providing direction to perfonn this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Trainina JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted by a 0.
- 2. During Evaluated JPM:
Self-verification shall be demonstrated.
- 3. During Training JPM:
0 Self-verification shall be demonstrated.
0 No other verification shall be demonstrated.
References :
- 1. EPIP-EPP-02, Classification Of Emergency Conditions at Unit 2
- 2. EPIP-EPP-18, Attachment 1 SM/ED Checklist
- 3. EPIP-EPP-20, Emergency Notifications
- 4. K/A 2.4.29(4.0), Knowledge of the Emergency Plan.
Tools and Equipment:
2.0 SM/ED Checklist Package 1.O EPIP-EPP-02, ATTACHMENT 2, UNIT 2 E.4L FLOWCHART NRC EXAM Admin SRO/JPM Emergency Pr/Plan 2
March 2008
Task Standard:
Classify the event within 15 minutes of the time that indications are available in the Control Room that an EAL has been exceeded and make all appropriate notifications within 15 minutes of the time the event is classified.
NRC EXAM Admin SRO/JPM Emergency PrPlan 3
March 2008
Initial Conditions:
- 2. Unit 11 had been operating at 100% power.
- 3. The time is 0100 (AM) and the following conditions exist:
- 4. Unit 1 tripped at 0045 (AM) and has not declared an emergency.
- 5. Ask the operator for any questions.
A Tornado hit the site causing a Station Blackout fifteen minutes ago and has moved out of the area.
The Division 1,2 and 3 Emergency Diesels tripped immediately after starting and can NOT be restarted.
The Systems Operating Center (Load Dispatcher) expects power restoration within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Drywell Pressure is 1.1 psig and slowly rising.
RCIC is operating and maintaining Reactor Water Level in the normal band.
Reactor Building pressure is positive.
Initiating Cue:
(Operators name), Based on the above conditions determine the event classifications per EPIP-EPP-02 and complete steps 1 through 7.b of EPIP-EPP-18, Attachment 1, SM/ED Checklist.
This is time critical.
After this event is classified and the notifications identified, the plant conditions will change as stated below and a reclassification will be required.
Initial Conditions #2:
- 1. The Division 3 Diesel Generator has been restored and has been started but NOT connected to any bus.
- 2. Reactor Level is normal.
- 3. Drywell Pressure is 1.1 psig and stable.
- 4. The Security Supervisor notified the Control Room that four armed intruders have taken control of the Division 1,2, and 3 Switchgear Rooms.
Initiating Cue:
(Operators name), Based upon the above changes in the conditions, determine how would this effect your previous EPIP-EPP-02 classification.
This is time critical.
NRC EXAM Admin SRO/JPM Emergency PrPlan 4
March 2008
I Performance Steps I Standard
- 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME -
- 2.
- 3.
.Obtain a copy of EPP-EPP-02 and reviewhtilize the correct section.
.Reviews the given conditions and determines that a Site Area Emergency declaration is required.
CUE: If asked, cue that Unit 1 is not in any EAL.
- 4..Enters EPP-EPP-18,, SM/ED Checklist and completes Steps 1 through 7.b. Completes applicable portions of EPP-EPP-20, Attachments 1A and 4.
Proper communications used for repeat back (GAP-OPS-01)
EPIP-EPP-02 is obtained.
Declares a Site Area Emergency withm fifteen minutes of the JPM in accordance with EAL 6.1.3.
Completes Attachment 1A and correctly.
CUE: When asked for meteorological data state:
Wind Speed @ 30' = 4 mph Wind Speed @ 200' = 6 mph Wind Dir @ 30' = 45" NRC EXAM Admin SRO/JPM Emergency Pr/Plan Sat/Unsat Satmnsat Pass/Fail PasdFail 5
EXAMINER NOTE:
Time of Declaration:
EXAMINER NOTE:
Time Attachment 4 is completed through step 4:
March 2008
Wind Dir @ 200' = 45" Stability Class D EXAMINER NOTE:
Once Attachment 1, CAN Notification Form is completed and prior to it being faxed, provide the Candidate with Initial Conditions #2.
CUE: If contacted as Security or state police for road access state that road access is normal.
NOTE: This is also Time Critical.
- 5..Reviews the given conditions and determine that a General Emergency declaration is required per EAL 8.1.10.
Time of notification of status change:
Declares General Emergency withm 15 minutes per EAL 8.1.10.
NRC EXAM Admin SRO/JPM Emergency Pr/Plan 6
1 Time of Declaration:
End of JPM TERMINATING CUE: The event has been classified and re-classified and all appropriate notifications initiated.
RECORD STOP TIME March 2008
Initial Conditions:
- 2. Unit 11 had been operating at 100% power.
- 3. The time is 0 100 (AM) and the following conditions exist:
A Tornado hit the site causing a Station Blackout fifteen minutes ago and has moved out of the area.
The Division 12 and 3 Emergency Diesels tripped immediately after starting and can NOT be restarted.
The Systems Operating Center (Load Dispatcher) expects power restoration within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Drywell Pressure is 1.1 psig and slowly rising.
RCIC is operating and maintaining Reactor Water Level in the normal band.
Reactor Building pressure is positive.
- 4. Unit 1 tripped at 0045 (AM) and has not declared an emergency.
- 5. Ask the operator for any questions.
Initiating Cue:
(Operators name), Based on the above conditions determine the event classifications per EPIP-EPP-02, and complete steps 1 through 7.b of EPIP-EPP-18, Attachment 1, SM/ED Checklist.
This is time critical.
NRC EXAM Admin SRO/JPM Emergency Pr/Plan 7
March 2008
Initial Conditions #2
- 1. The Division 3 Diesel Generator has been restored and has been started but NOT connected to any bus.
- 2. Reactor Level is normal.
- 3. Drywell Pressure is 1.1 psig and stable.
- 4. The Security Supervisor notified the Control Room that four armed intruders have taken control of the Division 1, 2, and 3 Switchgear Rooms.
Initiating Cue:
(Operators name), Based upon the above changes in the conditions, determine how would this effect your previous EPP-EPP-02 classification.
This is time critical.
NRC EXAM Admin SRO/JPM Emergency PrPlan 8
March 2008
ATTACWUIENT IA:
NINE MILE POINT NUCLEAR STATION NOTIFICATION FACT SHEET - PART 1 (Do not say items in italics)
Sheet I of 5 New York State 0 Oswego County 0 JA Fitzpatrick Warning Point Warning Point Power Plant (not reqd in 15 min)
Unaffected NMP Notification #
Unit (not reqd in 15 min)
Step Changed UNIT EAL #
1
~~
UNIT EAL#
ASK: I Brief event description and other significant Information:
( if necessary. Do not repeat EAL description)
~
Step
- 1.
Check those involved in verification roll call
- 2.
- 3. -
0 New York State 0 Oswego County 0 JA Fitzpatrick
[I Unaffected NMP Unit Warning Point Warning Point Power Plant
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
I O.
- 11.
- 12.
~
)es
{B. )Shutdown(
1 at 00 A s/hr B. Ground wind speed at 200 ft miles/hr at 30 ft.
A. Elevated wind direction (from) 9 s degrees B. Ground wind direction (from) 4 5 at 200 ft.
rc-degrees at 30 ft.
Stability Class:
A B
C F
G Reported by:
(Communicator name) at Tel. No. (315)
Iswego County or New York State need further clarification on any information?
ATTACHMENT 1: SMlED CHECKLIST Page 1 of4 Unit I C 2
- 2.
- 3.
A log documenting activities should be maintained.
Completed Use NIA or NlR if appropriate.
- 1.
This is a drilllthi is an actua emergency (circle one)........................................................................
E 0
- 2.
........... o o t z f n o a
Classify the emergency per EPIP-EPP-01 or EPIP-EPP-02 (within 15 minutes of indications available in control room)
- 3.
Using Attachment 1, Figure 1 flowchart determine the appropriate evacuation and accountability.. 0 0 0 0
- 4.
Announce to Control Room staff you are now assuming SMlED position and duties, and you are now declaring (state emergency classification NOTE:
level), and provide reason for classificationldeclarationlupgrade.
0 0 d o 0 IF: the announcement for a ground attack has been made as required by EPIP-EPP-10, THEN: DO NOT make further announcements until safety is assured, coordinate as necessary with security.
- 5.
Direct the appropriate announcement to be made using Attachment 2 of this procedure................. 0 0 a 0 0 NOTE:
Inform unaffected unit SM of forthcoming CAN notification fax and request Communications Aide call CAN in accordance with faxed attachment (only need to call out the ERO one time)......... 0 0 a Complete the following in accordance with EPIP-EPP-20:
- a.
If reclassifying and ERO has not been notified, repeat step 7.
- 6.
- 7.
Part 1 Notification Fact Sheet (provide to Comm Aide) Include information from other unit as applicable....................................................................................................................
0 0 0 0 NOTE:
Assure the safety of the ERO before making CAN Notifications. Consider directing ERO response to Alternate Emergency Duty Location.
- b.
CAN Notification Form
- 1) Fax completed form to unaffected unit Control Room, verify received (UI-2996, U2-1207).......................................................................................................... 0 o m
- c.
NRC Notification Worksheets (provide to Comm Aide)..........................................................
0 0 0 0 0 NOTE:
For events affecting both units, direct other Unit SM to complete NRC notification worksheet and notify the NRC
- 8.
Verify appropriate Site Emergency Procedures implementation per Attachment 8.......................... 0 0 0 0 0
- 9.
Implement emergency exposure controls in accordance with Implement Protective Actions as needed per EPIP-EPP-08, Attachment 1......................................................
CONTINUOUS EPIP-EPP-15 (Including issuing KI as required)...............................................................................
0 0 0 0 0
- 10.
Page 5 EPIP-EPP-18 Rev 16
/----
1 ATTACHMENT 2: EMERGENCY A NNOUNCEMENT
- DATE, NSTRUCTIONS: (check boxes to select appropriate announcement, consider crossing out rows not used)
PLACE GAlTRONlCS IN MERGE.
SOUND THE APPROPRIATE ALARM:
0 6 Evacuation Alarm for 10 seconds. (When an^ evacuation is being ordered)
ANNOUNCE ONLY THOSE ITEMS CHECKED: (Provide short description of the reason for classification, not the whole EAL)
Station alarm for 10 seconds.
- 1.
7
- a.
7
- b.
'Ittention. Attention all personnel. This is Nine Mile Point 0 a drill actual emergency 0 U ' 1 is experiencing:
2 is experiencing:
I1 0 "An Unusual Event due to I1 0 "An Alert emergency condition due to I,
E d
Site Area Emergency due to
~
S S
4 e L\\
Rc =Lds-h-.
n 0 "A General Emergency due to I,
If this is the first announcement for an Alert or higher, then always add "All Emergency Response Organization personnel are to report to their Emergency Response Facilities and card in. "
I. FOR A CREDIBLE I NSlDER SECURl TY THREAT, A 7
- a.
- i.
7
- a.
"An evacuation of Secure all n o n - e s s e n t w t h e two person line of sight vital area access rules are now in effect.
FOR A LOCAL AREA EVACUATI ON, ADD is being ordered due to:
All personnel are to leave the (
(area) staying clear of andreportto,
- i.
FOR ACCOUNTABILITY WITHOUT EVACUATION, ADD ( o n i p w G -
ith 4 above g if evacuation unsafe and only do step 6
/
once.)
7
- a.
"Accountability is b
!J FOR A PROTECTED &A EVACUATION, ADD (Only do step 7 once)
Protected Area. All personnel shall report to an onsite assembly area, card in anc remain in the area 3
d
'All personnel not assigned emergency response duties shall evacuate the Protected Area and report to the P-Building.
and remain at this location until further notice".
CONTINUED NEXT PAGE---
Page 10 EPIP-EPP-18 Rev 16
ATTACHMENT 2 (Cont)
EMERGENCYANNOUNC k
./
- 1. FOR AN EXCLUSION A R h EVACUATION, ADD (Only do step 8 once) 7 a.
OR OR 7 b.
response duties shall evacuate on Howard Road in Volney, Area immediately security as you exit. "
0 2.
e other location as appropriate) 0 3.
"Home" IF NECESSARY ADD :
(If radioactive release is i 0 Personnel are to lea 0 Personnel are to lea ch and check appropriate box below) 0
\\\\
IF APPROPRIAfk, ADD: (Only do step 9 once) a/a.
"Personnel in protective clothing should" (select appropriate):
d;. "Leave the area removing PCs as indicated at the step off pad."
0 2.
"Leave the area immediately and obtain Radiation Protection assistance at the access control point
- 0.
APPROPRIATE, ADD:
yd "There is no eating, drinking, or smoking within the protected area until further notice. "
0
- b. (Only done if "10a" has been done) Eating, drinking, smoking are now permitted within the Protected Area.
Y 9 L W A Y S ADD:
repeat this is a drill. 'I "I repeat this is an actual emergency. I'
- 2.
Repeat the alarm and entire announcement so that all specified steps of the specific announcement are made 2 (two) times.
Leave GAltronics in merge mode for the duration of the event.
Upon completion return this attachment to the EP Dept.
- 3.
- 4.
Page 11 EPIP-EPP-18 Rev 16