ML082200212

March 05000400-08-301 Exam Final JPMs (Admin)

ML082200212
Person / Time
Site:	Harris
Issue date:	08/07/2008
From:	- No Known Affiliation
To:	NRC/RGN-II
References
50-400/08-301
Download: ML082200212 (86)

Text

Final Submittal (Blue Paper)

Final Submittal (Blue Paper)

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FINAL JPMS ADMINISTRATIVE JPMs

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.: 301144H601 Task

Title:

Determine the Cold, Xenon-free JPM No.: 2008. NRC JPM Boron Concentration Requirement RO/SRO A1-1 for a Natural Circulation Cooldown KIA

Reference:

2.1.25 (2.8/3.1)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator - - - Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

INITIAL

• The unit tripped due to a loss of off-site power. All control rods CONDITIONS: have inserted.

• The operating crew is performing EPP-005, NATURAL CIRCULATION COOLDOWN.

• The unit will be taken to Cold Shutdown.

• PowerTrax is not available.

• Current RCS Boron concentration is 1125 ppm.

• Core Burnup is 130 EFPD.

• RCS B-10 Atom Percent is 19.36

• Temperature is 140°F.

Task Standard: Calculations within specified range.

Required Materials: Calculator General

References:

• EPP-005, NATURAL CIRCULATION COOLDOWN

• OST-1036, SDM CALCULATION MODES 1-5

• Curve Book Handouts:

• EPP-005, Step 7

• OST-1036

• Curve Book (Ensure Curve A-X-22 is available and unmarked) 2008 HARRIS NRC RO-SRO A1-1 Rev 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: USCG has directed you to perform step 7.a of EPP-005, determine the corrected Xe-free cold shutdown boron concentration using OST-1036.

Record values on this cue sheet once it is determined if SDM requirements are met by the current boron concentration.

C RODS _

CCURVE _

C REQ, _

C RCS, _

CSDM _

MET / NOT MET (Circle one)

Time Critical Task: NO Validation Time: 15 minutes 2008 HARRIS NRC RO-SRO At-1 Rev 2 NUREG 1021, Revision 9

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ~)

Start Time: _

Performance Step: 1 Reviews EPP-005, Step 7.

Standard: Determines OST-1036 applies.

Evaluator Cue: Provide EPP-005, Step 7.

Comment:

Performance Step: 2 Locates/reviews OST -1036.

Standard: Determines OST-1036, Section 7.2 applies.

Evaluator Cue: Provide OST-1036.

Comment:

Performance Step: 3 Record the following:

• Core burn up from MCR Status board.

• Temperature for which this SDM calculation is taking credit.

• Latest available RCS boron sample.

Standard :;. From Initial Conditions, records:

• 130 EFPD

• 200°F, or less

• 1125 ppm Comment:

2008 HARRIS NRC RO-SRO A1-1 Rev 2 NUREG 1021, Revision 9

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Record the following:

• RCS B-10 ATOM percent from MCR Status Board OR RWST B-10 Atom percent, IF following Core Reload.

Standard: Records 19.36 Evaluator Cue: RCS 8-10 ATOM percent from cue sheet Comment:

Performance Step: 5 Check rod status as follows:

• If all rods are inserted, record CRODS = 0 in Step 7.2.2.a and N/A Step 7.2.2.b.

Standard: Records 0 in 7.2.2.a and N/A's 7.2.2.b.

Comment:

Performance Step: 6 Determine Xenon free SDM boron concentration, CSDM, as follows:

a. Record the following information:

• Boron addition to compensate for stuck rods from Attachment 1 or Step 7.2.2.a.

Standard: Enters O.

Comment:

2008 HARRIS NRC RO-SRO A1-1 Rev 2 NUREG 1021, Revision 9

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 7 Determine Xenon free SOM boron concentration, CSOM, as follows:

a. Record the following information:

• Uncorrected required SOM boron concentration from curve A-X-22 (Use action level line on curve.)

Standard: Reads 2020 to 2040 ppm Evaluator Cue:

Comment:

Performance Step: 8 Determine required Xenon free SOM uncorrected boron concentration CREQ:

CREQ ~ CROOS + CCURVE CREQ= _

Standard: CREQ = 2020 to 2040 ppm Comment:

~ Performance Step: 9 Determine Xenon free SOM corrected boron concentration, CSOM:

19.9/Arcs x CREQ Standard: Divides 19.9 by 19.36 and multiplies by CREQ:

19.9/19.36 (2020 to 2040 ppm) =

Records 2076 to 2097 ppm Comment:

2008 HARRIS NRC RO-SRO A1-1 Rev 2 NUREG 1021, Revision 9

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION

~ Performance Step: 10 Determine whether SDM requirements can be met by Xenon free SOM calculation:

Compare RCS boron concentration, CRCS, and Xenon free SOM corrected boron concentration, CSDM:

• CRCS RCS boron sample from Step 7.2.1.

• CSOM Xenon free SDM corrected boron concentration from Step 7.2.3.c.

If CRCS is less than or equal to CSDM, then continue with Step 7.2.5 to take credit for Xenon effects.

Standard: Determines current RCS boron concentration is <CSDM boron concentration.

Comment:

Terminating Cue: When the candidate proceeds to Step 7.2.5: This JPM is complete.

Stop Time: _

2008 HARRIS NRC RO-SRO A1-1 Rev 2 NUREG 1021, Revision 9

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION QF COMPLETION Job Performance Measure No.: 2008 NRC JPM RO/SRO A1-1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete: .

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2008 HARRIS NRC RO-SRO A1-1 Rev 2 NUREG 1021, Revision 9

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• The unit tripped due to a loss of off-site power. All control rods have inserted.

• The operating crew is performing EPP-005, NATURAL CIRCULATION COOLDOWN.

• The unit will be taken to Cold Shutdown.

• PowerTrax is not available.

• Current RCS Boron concentration is 1125 ppm.

• Core Burnup is 130 EFPD.

• RCS B-10 Atom Percent is 19.36

• Temperature is 140°F.

INITIATING CUE: USCO has directed you to perform step 7.a of EPP-005, determine the corrected Xe-free cold shutdown boron concentration using OST-1036.

Record values on this cue sheet once it is determined if SDM requirements are met by the current boron concentration.

C RODS _

CCURVE _

CREQ _

CRCS _

C SDM _

MET / NOT MET (Circle one) 2008 HARRIS NRC RO-SRO A1-1 Rev 2 NUREG 1021, Revision 9

Appendix C Page 8 of 8 JPM CUE SHEET INITIAL CONDITIONS:

• The unit tripped due to a toss of off-site power. All control rods have inserted.

• The operating crew is performing EPP-005 NATURAL 7 CIRCULATION COOLDOWN.

• The unit will be taken to Cold Shutdown.

• PowerTrax is not available.

• Current ReS Boron concentration is 1125 ppm.

• Core Burnup is 130 EFPD.

• ReS B-10 Atom Percent is 19.36

• Temperature is 140°F.

INITIATING CUE: usee has directed you to perform step 7.aof EPP-005~

determine the corrected Xe-free cold shutdown boron concentration using OST-1036.

Record values on this cue sheet once it is determined if 8DM requirements are met by the current boron concentration.

~:.

CRODS C"'}

..,./

("' ) () ..., /r"j . r; I ...~

CCURVE (1.(),~.}O l/7(j(;2o I~O Bo<.fq)

C REQ ~c\:3t) ( 9t)(~o,,\nc} (9c.)((())

eRCS \ l L.~)

CS DM f) b '7(~ t (c, (90'7& +~ deft 7)

MET I~~~V (Circle one) 2008 HARRIS NRC RO-SRO A1-1 Rev 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.: 005016H101 Task

Title:

Estimate Primary to Secondary JPM No.: 2008 NRC RO ADM Leak Rate JPM A1-2 KIA

Reference:

2.1.31 (4.2)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing: This JPM should be performed on a frozen simulator.

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. .

Initial Conditions:

• The plant is at 100% power.

• A steam generator tube leak is in progress.

• AOP-016 has been entered and actions are in progress.

• OSI-PI is not available.

• Chemistry sampling has not commenced.

• Motivating air is isolated.

Task Standard: Determines leak rate to be --25 gpd using Method 1 of AOP-016, Att. 1.

Required Materials: None General

References:

AOP-016, Excessive Primary Plant Leakage, Rev 37 Curve Book Handouts: AOP-016, Attachment 1 Initiating Cue: The USCG has directed you to perform AOP-016, Excessive Primary Plant Leakage, Attachment 1 step 3 to estimate primary to secondary leakage.

Time Critical Task: No Validation Time: 10 minutes HARRIS 2008 NRC RO A1-2 REVISION 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP IC-19 imf RMS079 (REM-1TV-3534 CVPETS) to 6.00 E-7 uCi/ml.

NOTE: Must go to RUN for the malfunction to show.

Leave simulator in FREEZE once malfunction has appeared.

HARRIS 2008 NRC RO A1-2 REVISION 2 NUREG 1021, Revision 9

Appendix C Page 3'of 6 Form ES-C-1 '

PERFORMANCE INFORMATION (Denote Critical Steps with a ~)

Start Time: _

Performance Step: 1 Obtain procedure.

Standard: Locates and reviews procedures.

Evaluator Cue: Provide Curve Book and AOP-016, Att. 1, step 3 after the procedure is located.

Comment:

~ Performance Step: 2 ESTIMATE Primary-To-Secondary leak rate using ONE of the methods listed (no preferred method):

Method 1: Use Condenser Vacuum Pump Rad Monitor REM-3534 (Grid 2), Curve H-X-15A, Curve H-X-15B, or H-X-15C (Depending on status of motivating air)

Standard: Determines that Method 1 is required.

Comment:

~ Performance Step: 3 Operates RM-11 to obtain reading for REM-1TV-3534 (Grid 2).

Standard: Reads REM-1TV-3534 as 6.00 E-7 ~Ci/ml.

Comment:

HARRIS 2008 NRC RO A1-2 REVISION 2 NUREG 1021, Revision 9

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION

~ Performance Step: 4 Determines which curve from Curve Book to use.

Standard: Uses Curve H-X-15C since motivating air is isolated.

Comment:

~ Performance Step: 5 Calculates Primary to Secondary leak rate.

Standard: Determines Primary to Secondary leak rate is between 22 gpd to 27 gpd).

Comment: +/- 2.5 gpd is margin of error based on reading data from graph Terminating Cue: When the primary to secondary leak rate has been determined and reported to the USCO: Evaluation on this JPM is complete.

Stop Time: _

HARRIS 2008 NRC RO A1-2 REVISION 2 NUREG 1021, Revision 9

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC RO ADM JPM A1-2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

HARRIS 2008 NRC RO A1-2 REVISION 2 NUREG 1021, Revision 9

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• The plant is at 100 % power.

• A steam generator tube leak is in progress.

• AOP-016 has been entered and actions are in progress.

• OSI-PI is not available.

• Chemistry sampling has not commenced.

• Motivating air is isolated.

INITIATING CUE: The USCO has directed you to perform AOP-016, Excessive Primary Plant Leakage, Attachment 1 step 3 to estimate primary to secondary leakage.

HARRIS 2008 NRC RO A1-2 REVISION 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.: 341010H302 Task

Title:

Perform Review of Daily JPM No.: 2008 NRC SRO A1-2 Surveillance Requirements Log KJA

Reference:

2.1.18 (3.0)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom X Simulator - - - Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

• The plant is in Mode 2, waiting for management approval to proceed to Mode 1.

• EDG "8" is synchronized to the grid for a post-maintenance test.

• The Daily Surveillance Logs (OST-1021 , Attachment 4) for 2100 have been completed.

• ERFIS Pressurizer Pressures are unavailable.

Task Standard: All errors and TS actions identified Required Materials: Perform in a location with TS or electronic access to TS available.

General

References:

• OST-1021 , DAILY SURVEILLANCE REQUIREMENTS, DAILY INTERVAL, MODE 1 AND 2

• Technical Specifications HARRIS 2008 NRC SRO A1-2 Rev 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Handouts:

• Copy of a completed OST-1021 , Attachment 4.

• Delete all notes.

• Substitute the following incorrect data:

• Modify log readings on p.19 of OST-1021 so that the 1500 reading of 457 and 456 are low and together average < 2205.

• Include 455 approximately 60 psig high so that the channel check is unsat.

• Condensate Storage Tank Level (both channels) progressively lowering from 85% to 60% throughout the day (TS).

• RCS Loop Flow Channel FI-424 progressively lowering from 100.21 to 98.13 throughout the day (TS).

• EDG Room Temperature channel TDG6903B @ 121°F (should be circled)

Initiating Cue: You are the USCG and have just completed an emergency watch relief due to illness of the scheduled person. Review the OST-1021 ,

Attachment 4 logs. At the conclusion of your review, discuss any findings with me.

Time Critical Task: No Validation Time: 20 minutes HARRIS 2008 NRC SRO A1-2 Rev 2 NUREG 1021, Revision 9

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ~)

Start Time: _

Performance Step: 1 Obtain completed log.

Standard: Reviews handout.

Evaluator Cue:

• Provide handout for NRC SRO A1-2 after the Initial Conditions are reviewed and the Initiating Cue is provided.

• If necessary, after the applicant discusses each finding:

What action, if any, is required relative to this reading?

Evaluator Note: Only the incorrect items in the logs are identified in the JPM Steps.

Comment:

-v Performance Step: 2 Review OST -1021, Attachment 4 for approval.

Standard:

• Identifies that Pressurizer Pressure Channel 455. fails it's channel check.

Comment:

HARRIS 2008 NRC SRO A1-2 Rev 2 NUREG 1021, Revision 9

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

'./ Performance Step: 3 Review OST-1021, Attachment 4 for approval.

Standard:

• Identifies that the Pressurizer Pressures should have the calculations completed.

• Pressurizer pressure should be identified low out of spec based on performing calculation with only Channels 456 and 457.

Evaluator Cue: SRO may send paperwork back to RO to do the calculations.

If so cue the SRO to perform the calculations.

Comment:

'./ Performance Step: 4 Review OST-1021, Attachment 4 for approval.

Standard:

• Identifies one RCS Loop "B" Flow Channel (Sheet 5) is below Acceptance Criteria.

• Reading should be circled. TS does not apply in Mode 2.

Comment:

'./ Performance Step: 5 Review OST-1021 , Attachment 4 for approval.

Standard:

• Condensate Storage Tank Level (Sheet 7) is below Acceptance Criteria.

• Reading should be circled and entry into TS 3.7.1.3 Action a -

restore to operable or be in HSB within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, is required.

Comment:

HARRIS 2008 NRC SRO A1-2 Rev 2 NUREG 1021, Revision 9

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION

-Y Performance Step: 6 Review OST-1021, Attachment 4 for approval.

Standard:

• Identifies Diesel Generator Room 261 temperature TDG6903B (Sheet 10) exceeds Acceptance Criteria.

• Reading should be circled and investigative/corrective actions implemented.

Evaluator Cue: If requested: EDG "B" has been running for 30 minutes.

Evaluator Note: Reading does not meet criteria for declaring equipment in the room inoperable. '

Comment:

Terminating Cue: After all findings have been reviewed: Evaluation on this JPM is complete.

Stop Time: _

HARRIS 2008 NRC SRO A1-2 Rev 2 NUREG 1021, Revision 9

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SRO A1-2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

HARRIS 2008 NRC SRO A1-2 Rev 2 NUREG 1021, Revision 9

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• The plant is in Mode 2, waiting for management approval to proceed to Mode 1.

• EDG "8" is synchronized to the grid tor.a post-maintenance test.

• The Daily Surveillance Logs (OST-1021 , Attachment 4) for 2100 have been completed.

• ERFIS Pressurizer Pressures are unavailable.

INITIATING CUE: You are the USCG and have just completed an emergency watch relief due to illness of the scheduled person. Review the OST-1021, Attachment 4 logs. At the conclusion of your review, discuss any findings with me.

HARRIS 2008 NRC SRO A1-2 Rev 2 NUREG 1021, Revision 9

Attachment 4 ... Daily Surveillance Requirements Log Sheet 1 of 15 TECH SPEC 4.5.1,1.a.1 1 a.z Eees ACCUMULATORS PARAMETER etA A PRESSURE CLA B PRESSURE CLA C PRESSURE INSTRUMENT PI- 921 PI- 923 PI-925 PI ..927 Pl-929 PI ... 931 ACCEPTANCE Between 585 and 665 psig OPEN CRITER!A MODE 1~ 2 AND 3 WITH ReS PRESSURE ABOVE 1000 PSIG 0300 0900 1500 210q TECH SPEC a.s. 1.1,8.1 14.5.1.1, b (partial)

ECCS A.CCUMULATORS PARAMETER CLA A LEVEL CLA B LEVEL CLA C LEVEL SampUng Not Sampling Not SampUng Not INSTRUMENT LI ..920 Lt ..922 Required per LI ~ 924 Ll- 926* Required per Ll ..928 U ~. 930 Required per AU6 Att 6 Aft 6 ACCEPTANCE between 66 and 96 ok Indicated level viith CRiTERIA less tha.~ 9(}k cumulative level increase(excludfng makeup from operable RWST) ~inye last satisfact() sample MODE 1 2 AND 3 WITH ReS PRESSUREABOVE 1000 PSIG 1

Previous Days Level 0300 0900 1500 2100 4.3.2.1.10 2c, Sa3 3b3~ 3c3~ 4c 1 1 1 TECH SPEC 4A.6,2,1.b 5c, Bd,6g; 4,3.3.6.1a; 4J3.1.4 CNMTSUMP SUMP PARAMETER CNMT SUMP LEVEL CONTAINMENT PRESSURE FLOW MONITORiNG LEAK RATE ALB 1 URE URE LeT LeT PI PI iNSTRUMENT ERF1S N/A 9001 9002 7161A 7161B 950 953 PROGRAM ACCEPTANCE NO CHECKS CHAN.

N/A NfA LESSTHAN 1.6 PSfG CRITERIA ALARM PER CHECK OP..163 MODE 0300 0900 1500 2100

[6ST-1021 Rev. 66 Page 17 of~O I

Attachment 4 - Daily Surveillance Requirements Log Sheet 2 of 15 TECH SPEC 4.1.2.6.a.2; 4.5.4.a.1; 4.3.2.1. 7b, se: 4.3.3.6.9 4.1.2.6.a.2~ a.3 PARAMETER RWST LEVEL BORIC ACID TANK INSTRUMENT L!..990 Ll...991 LI-992 LI..993 N/A LI-106 L1..161.158 TCS7240 GREATER THAN ACCEPTANCE GREATER THAN OR EQUAL TO 92°k>

CHANNEL GREATER THAN OR OR EQUAL TO CRITERJA CHECK EQUAL TO 74%> QF 65 MODE 1.2 13) and.4 1.2,3 and 4 0300 C,iP C1C-, (il.l 9,5 IC)-(~) 2? I gc:) Ci~?

~

0900 .:

'~

, .... /:

1500 2100 ;h(')

V TECH SPEC 4.5,2.a 4.4.9.3 PRZ PARAMETER ECCS VALVE ALIGNMENT SPRAY ~T INSTRUMENT 181..340 181-341 181-359 I 181-86 I 1$1-52 I 181-107 TJ-123 TI-454.1 OPEN AND PULLEDTO LESS THAN ACCEPTANCE SHUT AND PULLED TO LOCK WITH LOCK WiTH CONTROL OR EQUAL CRITERIA CONTROL POWER OFF POWER OFF TO 625°F DURINGAUX MODE 1 r 2, and 3 SPRAY OPS 0300 Ai) (\41 rtJ r\O (;~~J

", dl~) tJ /;~

0900 :b .~ th*

,~f~ .:~ ~~. ~ f.J If~

r~;U ~1:)

1500 r-~\)

. ~ ~ ~ If,JIA 2100 "k) ~O 'A-~O {h0 itO ihQ

) l "if (-)

~ lJ V V V TECH SPEC 4.4.3,1: 4.3.1.1.11: 4.3.3.6.5 PARAMETER PRESSURIZER LEVEL INSTRUMENT LI-460 LI-461.1 LI-459A.1 N/A ACCEPTANCE LESS THAN OR CHANNEL CRITERIA EQUAL TO 90% CHECK MODE 1} 2. and 3 1 0300 -(0 \ (~/O &; c !r<J

~l{~

0900 lor (t;;; C> 00 ,,-

1500 CbiJ (0(\ j (0 [) (';A 2100 (),rQ\. (0 (') &(~) {~~7 v

I 08T-1021 Rev. 66 Page 18 of 40 I

Attachment 4 -Daily Surveillance Requirements Log Sheet 3 of 15

~ .

TECH SPEC 4.2.5.1; 4.3,1.1.9, 10; 4.32.1,1d~ 3a3} 3c3, 5c t 6 d PARAMETER PRESSURIZER PRESSURE tNDEPENDENT CALCULATION VERIFICATION ACCEPTANCE N/A COMPLETED COMPLETED CRITERIA MET ACCEPTANCE N/A CHANNEL SEE BELOW N/A NiA C-RtTERIA CHECK MODE 0300 0900 1500 2100 INSTRUCTIONS NOTE: Calculations must be done with either the MCB Indicators OR ERFIS lndlcsuons, NOT a combination.

NOTE: If all operable channels ~re greater than or equal to the acceptance criteria, calculations are not required.

CALCULATIONS FOR PRESSURIZER PRESSURE 0300:

PRC0457"~'

+

~~P-RC~O-4-5 +

._.........,.....-~~

= ~ (# Operable PRC0455 Channels used PRESSURTzEFf>>~

PI--457 P\-456 PI~455 Normally 3) PRESSURE 0900: + +  ::: (# Operable PRC0457 PRC0456 PRC0455 Channels used PRESSURIZER PI~457 PI..456 PI-455 Normally 3) PRESSURE Q-1500: .~,.,,~:Q:;too .+ Wy :;l~05 + = (# Operable = ~6~.5 PRC0457 PRC0456 PRC0455 Channels used *"***P"RESSURIZER PI..457 PI-456 Pl...455 Normally 3) PRESSURE 2100: + + (#Operable  :=

PRC04~ PRC0456 PRC0455- Channels used PRESSURIZER PI-457 PI-456 Pl~455 Normally 3) PRESSURE ACCEPTANCEGRITER1A FOR PRESSURIZER PRESSURE (must meet one of the following):

1. Average of operable Mea indicator channels greater than or equal to 2205 psig.

2, Average of operable ERF1S points greater than or equal to 2202 psig.

3, If three MeB indicators are not available, then the lowest channel should be greater than or equal to 2220 psig+

4. If three ERFIS points are not available, then the lowest channel should be greater than or equal to 2211 pSlg, IOST~1021 Rev. 66 Page 19 of 40 I

Attachment 4 .. Daily Surveillance Requirements Log Sheet 4 of 15 TECH $PEC 4,2.5.1 PARAMETER Res LOOP TAVG INDEPENDENT INSTRUMENT TRC0412D TRC04220 TRC0432D CALCULATION VERIFICATION ACCEPTANCE (MeB OR ERFlS) TI~412D TI-422D TI..432D COMPLETED CRITERIA MET COMPLETED ACCEPTANCE SEE BELOW NIA NfA N/A CRtTERIA MODE 0300 0900 1500 2100 INSTRUCTIONS NOTE: Calculatlons must be done with either the Mea Indicators OR ERFIS lndicatlons, NOT a combination.

IfaU operable channels are less than or equal to the acceptance critena, calculations are not required..

CALCULATIONSF.OR ReS LOOP TAVG 0300: + + = (# Operable =

TRC0412D -~..-- H~'TRC0432D Channels used Res LOOP TI~412D TI~432D Normally 3) TAVG 0900: + + =: + (# Operable  ::::

~--

TRC0412.D TRC0422D TRC0432D Channels used ReS LOOP TI...412D Tt-422D TI...432D Normally 3) TAVG 1500: + +  :: (# Operable =

TRC0412D TRC0422D W""'r"R"C043W- Channels used RCSLOOP Tt-412D Ti-422D TI~432D Normally 3) TAVG 2100: + + = (# Operable  :: ~ _

TRC0412D TRC04226""~ TRC0432D --~- Channels used ReS LOOP 11-412D Tt w422D TI-432D Normally 3) TAVG ACCI;PT ANCE CRITERIA FOR ReS LOOpTAVG. (must meet one of the following):

1, Average of operable Mea indicator channels mustbe less than or equal to 592.5 QF.

2. Average of operable ERF1S points less than or equal to 593.1 "F.

3. If three Mea indicators are notavallable, then the highest channel should be less than or equal to 591,3>:>F.

4. If three ERFIS points are not available, then the highest channel should be less than or equal to 592,3 OF.

IOST~1021 Rev. 66 Page 20 of 40 I

Attachment4,. DailySurveillance Requirements Log Sheet 50f 15 TECH SPEC 4,3.2.1 4.4.6.2.1.e FLANGE PARAMETER Res PRESSURE LEAKOFF TEMP OTliT OPllT PROTECTIONllT Ttw412C}

Tl..-412B)

TJ... 412A* TJ..422At iNSTRUMENT PI-403.1 P1402,1 TI401 TI422C 2 TI..422B~

Tl-432A TI..432C TI-4328 ACCEPTANCE CHANNEL CHECK N/A CHANNELCHECK CRITERIA MODE 0300 0900 1500 2100 INSTRUCTION If ReS flow acceptance criteria is not met, perform EST-70B, RCSFlowDetermination.

TeCH SPEC PARAMETER INSTRUMENT FRC0414 FRC0434 FI..414 F(~434 ACCEPTANCE ~ 98.30/0 CRITER~A 0900 1500 2100 Tf?CH SPEC 4.4.6.2.1.d PARAMETER OST~1004 or INSTRUMENT OST~1204 COMPLETED ACCEPTANCE COMPLETED (Typically on Night Shift)

CRITER1A 1 above 15%

MODE 1~ 2~3~ and 4 Power 0300 rOST-1021 Rev. 56 I Page 210f 40 I

Attachment 4 Daily Surveillance Requirements Log M

Sheet 6 of 15 TECH SPEC 4.4.1.t 4.3.1.1.12 PARAMETER* Res LOOP FLOWS FRC0414 FRC0415 FRC0416 FRC0424 FRC0425 FRC0426 INSTRUMENT RCPA N/A Reps N/A FI-414 FI-415 F1..4 16 FI-424 Fl-425 FI-426 ACCEPTANCE POSITIVE INDICAT10N OF FLOW WITH CHANNEL POSITIVE INDICATION OF FLOW WITH CHANNEL CR1TERIA Rep RUNNING INDICATION CHECK Rep RUNNING lNDICATION CHECK MODE 1 12 1 1.2 1 0300 ~() { ,\(~)

.... k) A'O AD AtO y.. . . .

MJ (~0 (uD rIO 0900 ~b ~

~

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1500 (~\ ~~ ~ ~ll ~~ f~~ ("1. r,l\- (j. ~

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2100 ( J

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v TECH SPEC 4.4.1.1: 4.3.1.1.12 4.3.1.1.2a.2b. 5.6 POWER INTERMEDIATE SOURCE PARAMETER Res LOOP FLOWS RANGE RANGE RANGE FRC0434 FRC0435 FRC0436 Nt-41, Nl-42 Nl..35 Nl-31 INSTRUMENT RCPC N/A FI-434 FJ*435 FI-436 N143, NI-44 NI-36 NI-32 ACCEPTANCE POSITIVE INDICATION OF FLOW WITH CHANNEL CHANNEL CHECK CRITERIA Rep RUNNING iNDICATION CHECK MODE 1,2 1 1} 2 1 <<P-10). 2 2 <<P..6), 3.4.5 0300 (~() A6"') ~ ~iC) r\£) (~kL) ,'\1 //) rJ/A 0900 ~~ ~14 ~~ ~ ~~. ~ ' 1/'1 f\l~ fJ N li~

~~ (~) r~

(~....

1500 ~. J+.  ;~~ \J)

\. f\l if-\ j\J fA 2100 (~) r-b rK) ~/r\() 1-10 )to l~ Ifi t J 114-

'v v \J V V v 4.3.2.1.1e. 3a3. 3c3 1 4d, sc, 6d, 69 TECH SPEC 4.3.1.1.14 4.3.3.6.6 PARAMETER STEAM LINE PRESSURE Pl..474.1. PI-484.1 Pi-494 INSTRUMENT Pl..475. PI-476 PI..485. PI486 PI-495. PI-496.1 ACCEPTANCE CHANNEL CHECK CHANNEL CHECK CRITERIA MODE t, 2. 3 and 4 1,2 0300 0900 1500 2100 I OST~1021 Rev. 66 Page 22 of 40 I

Attachment 4 - Daily Surveillance Requirements Log Sheet 7 of 15 TECH SPEC 4,3,1.1,13;4.3.1> 1~ 14; 4.3.2.1 .se. ec, 10~t 4.3.3.6,7 4,7,1,3,1 PARAMETER SG LEVEL CST LEVEL Ll~483f LI..484 LI..493 LI-494 LI~901 081 l

INSTRUMENT LI-9010A.1 SA S8 LI~485~ L148j Lt:.,,495~ Lj...496 ACCEPTANCE GREATER THAN OR CHANNEL CHECK CRITERIA EQUAL-.TO 62%

MOPE 0300 0900 1500 2100 TECH SPEC 4.7.1.3.2 PARAMETER. ESWTOAFW 1SW..121 1SW++'124 18W..127 1SW...130 INSTRUMENT 1SW-123 1SW+M126 1SW-129 1SW-132 ACCEPTANCE OPEN (only when supplying CRITERIA AFW pumps)

MODE 1 2,- and3 t

0300 ~)rpr' .....*..............."'W.<<.>>;.;-;.,;.;,.;.X/Vo."",.,..NNA*I'.";.

0900 rJ If\" ~X>>m-:-:->Jo>>>;'>>>

1500 tJltPr

• • • )0

~~~/

., ;. " -", .,___K_

-<<-~

N>>>

':~;MYN>>~>>Y>>'

2100 ~0/A ~:-:<<~<N.~  ;;::>

IOST-1021 Rev. 66 ~age 23 of 40 I

Attachment 4 .. Daily Surveillance Requirements Log Sheet 8 of 15 INSTRUCTIONS

1. ERFIS is the preferred source for verifying CNTMT AVG TEMP.

2. VerIfy TCV97540 computer point quality code is acceptable. If acceptable, record the ERFlS value for CNTMT AVG TEMP and verify Jess than or equal to 120°F.

3. If computer point TCV97540 is not available, verify both MeB indicators for CNTMT AVG TEMP less than or equal to 120 0 F.

TECH SPEC PLP-114 4.6.1.5 N/A 4.6.1.4 PLP-114 A EDG ELEC B EDG ELEC CONTAINMENT CONTROL ROOM PARAMETER CNMT AVG TEMP ROOM 261 ROOM 261 PRESSURE ENVELOPE 305 TCV97540 TJ-7542 TI-7541 PDl*7680 PDI-7680 TI-7837 TI-7837 INSTRUMENT ALB 27/1..3 SA SB A SA B 58 A1SA B188 NO ALARM ~ 116 0 F) LOCAL ACCEPTANCE LESS THAN OR EQUAL TO GREATER THAN -1.0 LESS THAN OR TEMP IS NEEDED IF ALARM IS CRITERiA 120°F JNWG EQUAL TO 85 QF PRESENT WHENEVER THE WHENEVER THE EQUIPMENT EQUtPMENT IN AN IN AN AFFECTED AREA IS 1. 2. 3. and 4 AFFECTED AREA MODE R'EQU1RED TO BE OPERABLE IS REQUlRED TO BE OPERABLE 0300 (\UJ 'l f 0900 1500 2100

\/

TECH SPEC PLp ..114 ROD SA ELECT 5B ELECT STEAM 1A35SA.

PARAMETER FHB EMER EXH AREA CNTRL CAB PENET PENET TUNNEL 1B35SB 261 AREA 305 AREA 261 AREA 261 INSTRUMENT Tl ..6 537A1SA TI..6 5378158 ALB 23/3-5 ALB 23J2-11 ALB 2312-8 ALB 23/2..5 ACCEPTANCE LESS THAN OR EQUAL TO NO ALARM NO ALARM NO ALARM CRITERIA 104°F << 104°F) << 122°F) (LESS THAN OR EQUAL TO 104°F)

WHENEVER THE EQUIPMENT IN AN WHENEVER THE EQUIPMENT ,IN AN AFFECTED AREA IS REQUIRED TO BE MODE AFFECTED AREA IS OPERABLE (LOCAL TEMP MUST BE TAKEN IF ALARM IS PRESENT)

REQUIRED TO BE OPERABLE 0300 tv c( ro ~'?

.) ~6J kC) A-o rro rJp:)

(&

./

0900 {j-/d (~() I ~ ~ \tJ9.

cL "- (~

1500 &'-1 rv ~l '~. <~~,

t A '~J) ~~

(ro

. "",)

2100 (0"7 Cv cl (~O k~:) ~:> )}-6~)

\J 'J V \t

'J IOST-1021 Rev. 66 Page 24 of 40 I

Attachment 4 - Daily Surveillance Requirements Log Sheet 9 of 15 TECH SPEC PLp ...114 CHILLER AFW I CCW PUMPS A..SA B-S8 1C-SAB SW BSTR MECH & ELEC PARAMETER PIPE & VALVE & HX AFW CSIP ROOM CSI? ROOM C$1iP ROOM B-SB PUMP PENETAREA AREA 261 PUMPS 236 236 236 236 236 236 ALB 23/2-6 ALB 23/1*6 ALB 23/2..9 INSTRUMENT ALB 23/1 ..5 ALB 23/1-4 ALB 23/1-11 ALB 23/2...7 ALB 23/1-7 ALB 23/2-10 ACCEPTANCE NO ALARM (LESS THAN OR EQUAL TO 104¢F)

CRITERIA WHENEVERTHE EQUiPMENT IN AN AFFECTED AREA IS REQU1RED TO BE OPERABLE MODE LOCAL TEMP MUST BE TAKEN IF ALARM lS PRESENT 0300 0900 1500 2100 TECH SPEC I PLP ..114 4.9.1*1 COMMITMENT CSAT& WPB A*SA BwSB FUEL POOLS HVAC HVAC CS~ RHR 1 CS, RHR~

PARAMETER EQUIP RM EQUIPRM HVAC HVAC SPENT FP NEWFP SFPC SFP D 216 236 190 190 INSTRUMENT ALB 23/1-8 ALB 23/1 w9 ALB 23/1..10 ALB 23/4-17 ALB 23/5-17 ALB 23/4*18 ALB 23/5..18 ACCEPTANCE NO ALARM (LESS THAN OR EQUAL TO 104 OF) NO ALARM (GREATER THAN 23 FT)

CRITERIA WHENEVER THE EQUIPMENT IN AN AFFECTED AREA 18REQUIRED TO BE OPERABLE WHEN IRRADIATED FUEL IS IN THE POOL MODE (LOCAL TEMP MUST BE TAKEN IF ALARM IS (LOCAL LEVEL MUST BE TAKEN IF ALARM rs PRESENT)

PRESENT) 0300 d<) {~) ({O ~ ,.))

0900 '-~~ '~~

<.-. ')~ ~dJ- "-~J)~

~~ V~'} I/~

l~

' ...,;:. ~

.~

1500 .~

b .~- ..

2100 (kJ r!P )tto ko

~.J \/ v 'tJ I OST-1021 Rev. 56 Page 25 of 40 I

Attachment 4 ... Daily Surveillance Requirements Log Sheet 10 of 15 TECH SPEC I ESR 97..00272 ESR 95~00425 ESR 97-00272 COMMiTMENT SPENT FUEL POOL HIGH SPENTFUEL POOLHIGH NEW FUEL POOLHIGH PARAMETER TEMPERATURE ALARM TEMPERATURE ALARM TEMPERATUR~ALARM INSTRUMENT ALB 23/4..16 ALB 23/4...15 ALB 2315~15 ALB 23/5.. 16 ACCEPTANCE NO ALARM NO ALARM NO ALARM CRiTERIA MODE 0300 0900 1500 2100 TECH SPEC PLP-114 ESWELECEQUJP ROOM 261 ESW PUMP ROOM 261 EDG ROOM: 261 PARAMETER INSTRUMENT TEV6588A TEV658~~ TEV6592A TEV6592B TDG6903A TDG6903f.3 . .

ACCEPTANCE LESS THAN OR EQUAL LESS THAN OR EQUAL TO LESS THAN OR EQUAL TO CRITERIA TO 116$;)F122~F WHENEVER THE EQUIPfv1ENT IN AN AFFECTED AREA IS RE.QUIRED TO BE OPERABl.E 0900 1500 2100 IOST-1021 Rev. 66 Page 26 of 40 I

Attachment 4 .. Daily Surveillance Requirements Log Sheet 11 of 15 NOTE 1: If a reservoir level computer point is bad, manual reservoir level determination can be performed per OP w163.

NOTE 2: If a reservoir temperature computer point is bad, manual reservoir temperature readings can be performed per OP-163.

INSTRUCTION

1. Due to a 3°F instrument inaccuracy associated with the permanently installed reservoir TSWs, if TSW9114ITSW9115 'indicate 291 °F obtain local temperature J readings per OP-163.

4.1.2.6b TECH SPEC 4.5.4.b 4.7.5 RWST AUX RSVR PARAMETER TEMP AUX RSVR LEVEL TEMP MAIN RSVR LEVEL MAIN RSVR TEMP lNSTRUMENT TCT7110 LSC8752A LSC87528 TSW9114 LSC8750A LSC8750B TSW9115

~40°F GREATER THAN OR GREATER THAN OR EQUAL ACCEPTANCE AND EQUAL TO 250 FT  ::; 94°F TO 215 FT s 94°F CRITERlA < 125°F NOTE 1 NOTE 2 NOTE 1 NOTE 2 MODE 1 ~ 2) 3 and 4 0300 5~7. &.' (9-5Jl i: r?~S L ~S(} l{() t o.;.:; 9Jt\~;S  ;)17" (0 I 4&v6 0900 1500 t~~-7 ,5 ~SI\5 /)5~ j 5<1 L(~t3~ l)r9. Sec, J,j 15 ~ W l

J <7

-:l LJS... ...,....,{

..... ~...

~

2100 INSTRUCTION

1. The ECCS leakage outside RABEES reading is only required every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Perform on Sunday, WednesdaYt and Friday (mark as N/A on other days).

2. If any ECCS leakage outside RABEES is measured, record the cumulative leakrate on Attachment 7 along with the locations leaking.

t TECH SPEC PLP-114 PARAMETER ECCS leakage outside RABEES INSTRUMENT N/A ACCEPTANCE LESS THAN 2 GPH (125 cc/min) cumulative CRITERIA MODE 1,2,3 and 4 0300 0900 1500 VJ/t\

2100 IOST-1021 Rev. 66 Page 27 of 40 I

Attachment 4 - Daily Surveillance Requirements Log Sheet 12 of15 NOTE 1: Meteorological Channel check includes: (1) Initialing for a acceptable quality code if using ERFIS or verifying data quality is consistent with actual weather conditions if using a Personal Computer(PC) to access the meteorological tower, and (2)

Recording present values and verifying trend appears normal.

NOTE 1: During calm wind conditions (approximately 2 mph or less) it is normal to see disagreement between the upper and lower wind direction indicators. At times the vanes may actually rotate in opposite directions.

NOTE 1: The following shall be used for performing the daily channel check of the meteorological instrumentation channels:

• On ERFIS observe the points for wind speed, wind direction, and differential temperature.

• . Using a PC , access the meteoroloqical tower and observe upper and lower wind speed, upper and lower wind directlon. and differential temperature (or stability class).

The meteorological instrumentation should only be considered inoperable if both of the above methods are unavailable.

NOTE 2: MIMS Channel check should include, as a minimum, both a Self Test and an Audio Monitoring Test of all operable channels. Op 182 contains guidance for resetting the wo CPU FAILED light if lit.

(Reference 2.6.4)

TECH SPEC PLP-114 PLP-114 METEOROLOGICAL MIMS PARAMETER LOWER WIND UPPER WIND LOWER WIND UPPER WIND A1R SPEED SPEED DIRECTION D1RECTION llT ALL INSTRUMENT MMT1008 MMT1010 MMT1014 MMT1013 MMT1004 MMT1Q05 CHANNELS CHANNEL CHECK NOTE 1 CHANNEL ACCEPTANCE CHECK CRITERIA Value Init Value Init Value Init Value Init Value Init Value Init NOTE 2 MODE AT ALL TlMES 1,2 0300 C\t/& M;~) 'f) 7 1)

J. '.7~ S~f) 3~:;*21 Z-3 li J f1/31 rh-J \ L.~,,~ 1.(0 11..55" j,.-I,() A"0"f) i

~.'.. '

-s : 'J' 0900

.~

1500 ~'},J~ '~ll "11 jlL3<6 ~ ~{Z~ l2. l~

(,<1/l3 ~~ *-~Lgti 'J) -l,'7J '~J2

~'

2100 IOST-1021 I Page 28 of 40'1

Attachment 4 - Daily Surveillance Requirements Log Sheet 13 of 15 LOCAL TEMPERATURES TECH SPEC PLp..114 SFP PUMP & TANK AREA E-6 ROOMS 261 PARAMETER HX ROOM 236 A-SA B-SB lNSTRUMENT LOCAL THERMOMETER LESS THAN ACCEPTANCE OR EQUAL TO LESS THAN OR EQUAL TO 104.oF VERIFIED CRlTERIA 115.5 of WHENEVER THE EQUIPMENT iN AN AFECTED t*:,':.:,-.:.: *::.*\.:;>~~}~t~.: (;/}~:::::~:r.:::~*:**

MODE AT ALL TIMES AREA IS REQUIRED TO BE*OPERABLE  :::.:;.;.;: '::-:,:.:

0100-0400 1.--7 S

,) I 0:?G7 L{

t & v-1 ~ .:) &L/~ 7 )D la it, ~ Lf " c.( C:i r7~

1300..1600 ~51\"3 t9?? ~ (p &, .- l '/ C!..-/

TECH SPEC PLP-114 EDG HVAC ROOM 280 EDG HVAC ROOM 292 DFOST BLDG PARAMETER 242 A-SA B-58 A-SA B-SB lNSTRUMENT LOCAL THERMOMETER LESS THAN ACCEPTANCE LESS THAN OR EQUAL TO LESS THAN OR EQUAL TO OR EQUAL VERIFIED CRITERIA 118°F 122°F QF TO 122 WHEN THE EQUIPMENT iN THE AFFECTEDAREA 18 REQUlRED TO BE MODE OPERABLE 0100..0400 ~-?&( GI g::)

.... ~

D *'7t;5t '*'7 if If>3 <>>. <./ (~QJ 1300-1600 ~~7? \,~5' 71 L{td ' ") ~1 ~ "j 7l0~fo C:Ol , L( ~~Q ~.;}

I OST-1021 Rev. 66 Page 29 of 40 I

Attachment 4 .. Daily Surveillance Requirements Log Sheet 14 of 15 LOCAL TEMPERATURES INSTRUCTION

1. If battery room temperature is less than 71 of, perform Step 7.0.5.

TECH SPEC PLp..114 ELECT SW1TCHGEAR PENETRAT'ON SATIERY ROOM286 ACP 286 PARAMETER ROOM 286 AREA 286 A..SA BwSB A-SA B-S8 A..SA I B...SB INSTRUMENT LOCAL THERMOMETER ACCEPTANCE LESS THAN OR LESS THAN OR LESS THAN OR

~ 71°F AND ~ 85°F VERIF1ED CRITERIA EQUAL TO 104°F EQUAL TO gO°F EQUAL TO gO°F

'.. . :.:.:..>..: /':.':",::,

WHENEVER THE EQUIPMENT IN AN AFFECTED AREA IS REQUIRED TO BE O:':':':::::::',\,~: ':',::' .':':

MODE OPERABLE 0900-1200 &~;;)\ G.' '~7[{ (to y\, C:j '7~~1~ c1 ~*-?0. ~ "7ip ~ i? .-~] ~7 ~ '--7 l l"~J 2100-2400 (0:--Q ~ ci -7 L(J~. ~t\t _~3 ~7<l, , ':-7~S ~ t:t "7~J ~ C} "7'7. \ G <:1 :1;)

TECH SPEC PLp w114 AUX TRANSFER PANEL ROOM PIC ROOMS PARAMETER 286 286 A-SA B..SB 17 19 t 18 INSTRUMENT LOCAL THERMOMETER ACCEPTANCE LESS THAN OR EQUAL TO LESS THAN OR EQUAL TO CRITERJA 104°F 85°F WHENEVER THE EQUIPMENT iN AN AFFEOTED AREA IS VERiFIED MODE REQUIRED TO BE OPERABLE 0900...1200 --7~:) ~ ~~-'1 '~'7 ~1.

(... ~),

(-~ "'}~, c. "'7:5~ C) 2100 ...2400 "'7 2..-- ~ '~7 '-'7 2 '<2- ~~7

'(>,. ~ £2'J ~7 Lo( t ~l TECH SPEC PLP-114 ARPROOM AH-15 VENTILATION PARAMETER PIC ROOM 305 305 ROOM INSTRUMENT LOCAL THERMOMETER ACCEPTANCE LESS THAN OR EQUAL TO LESS THAN OR VERIF1ED CRITERIA 85°F EQUAL TO 104°F

':.'. :-:/. :-:::.,:.,'. ......' ....:

WHENEVER THE EQUIPMENT IN AN AFFECTED AREA IS MODE REQUIRED TO BE OPERABLE 0900-1200 ~7 t . 0 {(i{a , ~ 4,0 \ ( r0

~

2100-2400 ~7C) ~ ~6 (&~~ ~ '~7 &0 ~ (~) ~

1 OST-1021 Rev. 66 Page 30 of 40 I

Attachment 4 - Daily Surveillance Requirements Log Sheet 15 of 15 NOTE 1: These readings are only required on Sundays. These readings may be marked N/A on other days.

TECH SPEC 4.1.2.2.a BORJCACID BORIC ACID VCTVALVE BAT EMER BORATION PARAMETER XFER PUMP XFER PUMP GALLERY ROOM VALVE RM VALVE GALLERY ROOM INSTRUMENT LOCAL THERMOMETER ACCEPTANCE GREATER THAN OR EQUAL TO 65°F CR1TERIA MODE 1,2 and 3 1300-1600 (NOTE 1) rrJ lA- ....__..-......---...------Y'O"+i'---.M........-.-....................,.-.. ........---------- ---._~

TECH SPEC 4.1.2.2.a BAT TO CSt? SUCTION HEADER PfPE TEMPERATURE (IF ANY OF THESE INSTRUMENTS FAIL. INITIATE CORRECTIVE ACTION AND NOTE IN COMMENTS PARAMETER SECTION. USE SECONDARY INSTRUMENTS TO SATISFY THE SURVEILLANCE REQUfREMENT)

HT-18753C HT-18753C HT-18753B HT~18753B HT..18753B HT..18753B INSTRUMENT ACCEPTANCE C2-1 I C2-2 I C1-9 I C1-13 I C2..3 I C2-5 CRiTERIA GREATER THAN OR EQUAL TO 65°F MODE 1,2 and 3 1300..1600 (NOTE 1) N. I r. r~

.~. \_*. *---------1------- tI ~J I

1 I

--~~.-_"'-~

TECH SPEC 4.1.2.2.8 BAT TO CSIP SUCTION HEADER PlPE TEMPERATURE (THESE ARE SECONDARY INSTRUMENTS. THESE SHOULD BE USED WHEN PRIMARY INSTRUMENTS PARAMETER INSTRUMENT HT-18753CC C2-1 I HT..18753CC C2...2 I FAll. (N/A IF NOT BE1NG USED.)

HT-18753BB C1v9 I HT-18753BB C1-13 1 HT..187538B C2 ...3 I HT-18753BB C2-5 ACCEPTANCE CRITERIA GREATER THAN OR EQUAL TO 65°F MODE 1,2 and 3 1300-1600 (NOTE 1) f~1 f) 1---*-----.1- I i. 1I -.~----;.""i IOST-1021 Rev,66 Page 31 of 40 I

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.: 015004H201 Task

Title:

Perform the Quadrant Power Tilt JPM No.: 2008 NRC RO A2 Ratio Surveillance KIA

Reference:

2.2.12 (3.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method oftesting:

Simulated Performance: Actual Performance: x Classroom X Simulator - - - Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

• The plant has been stabilized at 100 % power following a dropped rod in Control Bank "B" (M-6).

• The crew is performing AOP-001, MALFUNCTION OF ROD CONTROL AND" INDICATION SYSTEM.

• No deficiency tags on PRNls.

Task Standard: Calculations within required band.

Required Materials: Calculator General

References:

OST-1039, CALCULATION OF QPTR, Revision 13 Handouts:

• OST-1039

• Curve Book (Ensure F-X-8 included and unmarked)

Initiating Cue: The USCO has directed you to perform a manual QPTR lAW OST-1039, CALCULATION OF QPTR. The Power Range NIS readings are provided in the table below.

For the purposes of the examination, there will be no independent verification of your work.

Time Critical Task: NO Validation Time: 12 minutes HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 2 of 10 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a ~)

Start Time: _

Performance Step: 1 Obtain procedure.

Standard: Reviews procedure.

Evaluator Cue: Provide OST-1039.

Evaluator Note: A KEY is provided for your use on JPM Page 7.

Comment:

Performance Step: 2 Completes Prerequisites section:

• Instrumentation needed for the performance of this test is free of deficiency tags that affect instrument indication.

• Verify the most recent Curve F-X-8 is used in the performance of this procedure.

• Verify all prerequisites are met, then obtain Unit SCO permission to perform this OST.

Standard:

• Logs F-X-8 revision number (NRC Exam)

• Initials/signs all blocks Evaluator Cue:

Comment:

HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 30f 10 Form ES-C-1 VERIFICATION OF COMPLETION Performance Step: 3

• If Quadrant Power Tilt Ratio Calculation Computer Program is used, perform Section 7.1, and N/A section 7.2.

• If manual calculation of the Quadrant Power Tilt Ratio is used, perform Section 7.2, and N/A section 7.1.

Standard:

• Marks Section 7.1 N/A

• Proceeds to Section 7.2 Comment:

Performance Step: 4 Prior to reading the value of detector current, ensure the meter range/rate switch is in the 400 J,lAlSLOW position.

Standard: Verifies meter range/rate switches were in the 400 J,lAlSLOW position when the readings were taken.

Evaluator Cue:

Comment:

Performance Step: 5 Record on Attachment 2, in Column A, the upper and lower detector currents from all operable power range channels as read on the Nuclear Instrumentation Cabinet.

Standard: Transposes readings from PRNIS Readings Table onto Attachment 2.

Comment:

HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 4 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Performance Step: 6 Record on Attachment 2, in Column B, the 100% power normalized current for each channel. (Refer to Curve F-X-8)

Standard: Transposes TOP and BOTTOM 100 % current values from the Curve Book provided.

Evaluator Cue:

Comment:

Performance Step: 7 Divide values in Column A by the respective normalized current in Column B and record the result in Column C as the Normalized Fraction.

Standard: Divides each Upper and Lower reading by the respective 100%

normalized current value and records in Column C.

Comment:

Performance Step: 8 Calculate the average value for the upper and the lower Normalized Fractions by adding the Normalized Fraction in each section of Column C and divide by the number of operable NI channels. Record in Column D of Attachment 2.

Standard: Adds all Normalized Fractions for the same plane, divides by four and records result in Column D.

Evaluator Note: On the KEY, this value is shown at the bottom of Column C.

Comment:

HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 5 of 10 Form ES-C-1 VERIFICATION OF COMPLETION

~ Performance Step: 9 Using the formula and values from Attachment 2 calculate the Upper and Lower Ratios.

Standard:

• Divides the Maximum Normalized Fraction by the Average Normalized Fraction on each plane.

• Determines both UPPER and LOWER ~ 1.029.

Evaluator Note: The applicant may inform the USCO as soon as any calculation is > 1.02. If so, acknowledge and direct applicant to complete.

Comment:

Performance Step: 10 Perform independent verification of all calculations made on Attachment 2.

Standard: Requests Independent Verifier.

Evaluator Cue: If necessary, repeat Initiating Cue: For the purpose of this examination, there will be no independent verification of your work.

Comment: Candidate may choose to check calculations.

~ Performance Step: 11 The upper ratio or the lower ratio, whichever is greater, is the quadrant power tilt ratio (QPTR). Record QPTR and verify QPTR is less than or equal to 1.02.

Standard: Records Maximum QPTR value 1.026 to 1.036 (N44 UPPER)

Comment: Acceptable band is +/- 50/0 (rounded to .005) around 1.031.

HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 6 of 10 Form ES-C-1 VERIFICATION OF COMPLETION

-v Performance Step: 12 Complete applicable sections of Attachment 3, Certifications and Reviews and inform the Unit SCO when this test is completed.

Standard:

• Check marks Periodic Surveillance or notes AOP-001 in Comments section

• Plant Condition: 100% Power (may note dropped rod)

• Mode 1

• Today's Date

• Current Time

• OST Completed By: Applicant's name

• Initials/Name

• Indicate in General Comments Section and/or informs USCG that the limit is exceeded (-V)

Evaluator Cue: Acknowledge any report.

Comment:

Terminating Cue: After the USCO has been notified: Evaluation on this JPM is complete.

HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 7 of 10 Form ES-C-1 VERIFICATION OF COMPLETION KEY A B C UPPER UPPER UPPER 100% POWER NORMALIZED UPPER DETECTOR NORMALIZED FRACTION DETECTOR CURRENT CURRENT (NOTE 1)

N-41 149.7 155.2 .965 N-42 177.9 175.6 1.013 N-43 202.0 200.0 1..010 N-44 165.5 159.5 1.038 SUM 4.026/4 =

1.0065 A B C LOWER LOWER LOWER 100% POWER NORMALIZED LOWER DETECTOR NORMALIZED FRACTION DETECTOR CURRENT CURRENT (NOTE 1)

N-41 169.2 176.1 .961 N-42 202.6 202.2 1.002 N-43 221.1 221.2 .9995 N-44 197.5 192.3 1.027 SUM 3.99/4 =

.9975 Highest Upper (N-44) 1.038/1.0065 = 1.031 Highest Lower (N-44) 1.027/.9975 = 1.0296 (1.03)

HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 8 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC RO A2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION HARRIS 2008 NRC RO JPM A2 Curve F-X-8 HANDOUT Revision Number: NRC Exam NIS Current Setpoint Table uA, 100 % power N41 155.2 176.1 N42 175.6 202.2 N43 200.0 221.2 N44 159.5 192.3 HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 10 of 10 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• The plant has been stabilized at 100% power following a dropped rod in Control Bank "B" (M-6).

• The crew is performing AOP-001, MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM.

• No deficiency tags on PRNls.

INITIATING CUE: The USCO has directed you to perform a manual QPTR lAW OST-1039, CALCULATION OF QPTR. The Power Range NIS readings are provided in the table below.

For the purposes of the examination, there will be no independent verification of your work.

PRNIS Readings N41 149.7 169.2 N42 177.9 202.6 N43 202.0 221.1 N44 165.5 197.5

• All values were taken, with the Range/Rate switch in 400 IJAiSlow position.

HARRIS 2008 NRC RO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.:

Task

Title:

Review the Completed OST for JPM No.: 2008 NRC SRO A2 Auxiliary Feedwater Pump 1A-SA KIA

Reference:

2.2.12 (3.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom X Simulator ---

Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

• The unit is in Mode 1 at 100% power

• All major controllers are in AUTO

• No TS Action Statements are in effect

• OST-1211, AUXILIARY FEEDWATER PUMP 1A-SA OPERABILITY TEST QUARTERLY INTERVAL MODES 1-4, has just been completed Task Standard: All errors (4) identified Required Materials: None General

References:

OST-1211, AUXILIARY FEEDWATER PUMP 1A-SA OPERABILITY TEST QUARTERLY INTERVAL MODES 1-4 Handout: Completed OST-1211 with the errors incorporated.

Initiating Cue: You are the USCO. Completely review the procedure and note any problems in the

GENERAL COMMENT

S section of Attachment 6 -

Certification and Review. Discuss your review with me at the conclusion.

HARRIS 2008 NRC SRO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 12 minutes HARRIS 2008 NRC SRO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A HARRIS 2008 NRC SRO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Review procedure Standard: Ensures proper conditions, signatures/initials, and may verify the current revision of the procedure Evaluator Cue:

• Provide the completed OST-1211.

Comment:

~ Performance Step: 2 Review the completed OST Standard: Attachment 1 (Page 16) - Identifies stopwatch is past calibration date Evaluator Note: This makes the OST invalid and/or any timed elements would have to be repeated.

Comment:

HARRIS 2008 NRC SRO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION

-v Performance Step: 3 Review the completed OST Standard:

• Attachment 2, Sheet 1 (Page 17) - wrong Specific Volume used to determine ilPcorr.

Evaluator Note: l\Pcorr still exceeds minimum requirement but is incorrect.

Comment:

-v Performance Step: 4 Review the completed OST Standard:

• Attachment 3 (Page 20) - Outboard Horizontal Vibration reading is in the ALERT range but there is no documentation in accordance with Instructions 1.a and 1.b.

Evaluator Note: The pump would still be operable but this could prevent corrective action or the required increase in surveillance frequency.

Comment:

-v Performance Step: 5 Review the completed OST Standard: Attachment 4 (Page 21) - 1AF-74 SHUT time exceeds CODE CRITERIA and, in accordance with Step 7.0.1, should have been retested immediately.

Comment:

HARRIS 2008 NRC SRO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Review the completed OST Standard: Returns the procedure unsigned or, if signed, with EXCEPTIONS circled and all errors identified in the

GENERAL COMMENT

S section.

Comment:

Terminating Cue: When the procedure is returned: Evaluation on this JPM is complete.

STOP TIME:

HARRIS 2008 NRC SRO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SRO A2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

HARRIS 2008 NRC SRO A2 Revision 2 NUREG 1021, Revision 9

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• The unit is in Mode 1 at 100 % power

• All major controllers are in AUTO

• No TS Action Statements are in effect

• OST -1211, AUXI LIARY FEEDWATER PUMP 1A-SA OPERABI LITY TEST QUARTERLY INTERVAL MODES 1-4,'

has just been completed INITIATING CUE: You are the USCO. Completely review the procedure and note any problems in the

GENERAL COMMENT

S section of Attachment 6 - Certification and Review. Discuss your review with me at the conclusion.

HARRIS 2008 NRC SRO A2 Revision 2 NUREG 1021, Revision 9

C CO*NTINUOUS USE HARRIS NUCLEAR PLANT PLANT OPERATING MAN UAl VOLUME 3 PART 9 QPERAT10NS SU*RVEllLANCE TEST NUMBER:

OST-1211 TITLE: A*U:XILIARY FEEDWATER PUMP 1A.-SA OPERABILITY TEST QUARTERLYI*NTERVAL MOD:ES 1 -4 NOTE: Thlsprccedure has been screened perPLP-1 00 Criteria and determined to be CASE Iii, :additionalmanagementinvolveme*nt is required.

.... . *1 I OST-1211 Rev, 16 Page 1 of 261

Attachment 1 -Calibration Data Sheet Sheet 1 of 1 Cal Due Date I o~ o c QT' 0 (JT" N.A

Rev. 16 Page 18 of 261

A'ttaehm.ent 2 ~ Performance Data Sheet 1 of*3 Auxiliary Peecwater Pump 1A..SA NOTE1:Caiculate DifferentiaiPressure as foltows:

lb{)() < (iSIS = J514~d, psid Step 7'. 1.21 Step 7~ 1.18 Step 7.1.23*

L!==========:,======= . ::=.:.. .=====;======~

NOTE* 2: Satisfactory Acceptance Criteria is .determlnedby u.sing the following

~.rH l~-HO and verifying the correcteodlfterenttatpressure ts \tifit.hinthe

.- :_- ~t;:t;. \i.~ Iltj'~: la:

tlP corr :::; Corrected DifferentIal Pressure APind  := tndlq.~ted Discharge Pressure minus Indicated sucuon Pressure Uf =: SpeCific Volume (ftslfbm) for saturated Iiquidwater (u,) for suction temperature recorded inStep7.. *1.22. This number can be determined from Sheet3 of this Attachment or Standard Steam Tabtes~

7.1.24 I0$1-1211 r w

Rev. 16 Page 11 of 26 ,

Attachm.ent 2 ~ Performance Data Sheet 2 of 3 INSTRUC*TIONS

1. If pump hydrauHcdatEfdoes not meet acceptance criteria:

a~ Declare the pump iNOPERABLE.,

b~ Inlti:ate a :CR.

ST*Ep***

NO.

7.1.3 7.1.18 Test Gauqe psig 2: 15 psig CE~42 . .V*2 7.1.20 Test G:8uge at1AF-11*HV.2 {CodD psig N/A ERFISPoint 7.1.22 TCE901 . *::or Suction Temperature N/A Har~dheld Porom~t~(*

Test Gauqe at 1AF-7 OifferentlalPressure Calculated per NOTE 1 Calculated per 7.1 ~26 Differenual Pressure NOTE 2 (C:orrected (liPcorr)

• Circle instrument used.

• • 50 to 54 inches water column is equivalent to 50 to 52 gpm IOST~1211 Rev. 16 Page 18 of 261

Attachm.ent 2* Performance Data Sheet 3 of 3 Specific Volume (ft 3/Ibm) For Saturated Liquid Water {ud Temperature Specific Volume Temperature l:s.. peciflc VO~.unne 59 0:.016034 80 I 0.016074 60 0.. =016035 81 0.016076 61 0.016036 82 0.016079 103 62 0.0160:38 83 0.016081 63 0.01603:9 84 105 64 as 66 (t016044 81 67 CL016046 88 109 6*8 0.01.60:48 89 0..0=16097 69 O~01'6050 111 0.0'16110 70 0.016052 11:2 0.016174 11 113 0.016177 7*2 0.016056' 73 0.01605$ 12 1 74 0.016060 95 OJJ*16.115 116 0.016189 75 0.016062 96 117 76 0.016064 1 77 0.016061 98 0.016125 119 0.016201 78 0.Ot6069 120 79 0.016011 tOO 0.016131 0.016209 I Rev. 16 Page 19 of 26 I

Attachment 3 ~ Vibration Data Sheet 1 of 1 IN'STRUCTIONS:

1. If pump vibration data is greater than the Acceptable Range but within the Alert Range:

a. Prepare enE-man or MenlO to the Surveillance Testing Scheduling Coordinator directing the test frequency of the pump to be doubled,

b. Attach a copy of the E-mail or Memo to the test package.

2. If pump vibration data meets the Required Action Criteria:

B. Declare the pump INOPERABLE.

b. Initiate a Condition Report (CR)v F s Vibration ACCEPTANCE :CRITERIA

.location IN/SEC Acceptable Range Alert Range Required Action Axial ~ *J.1Q :s.0.285  :> O~285 to ~ 0.68.4 > O~68*4 Outboard ~. 0.2325 > 0.232'5 to .s:O.558 > O~558 Horizontal l~Gt~3 ) *.. .,.".,.,:;">>,,.,~~, .*,.".~;-.,..

Outboard s O~2775 >ON2775 tos 0.666 > 0,666

/'0

............. ~

Vertical Inboard s O~265 *>O.2.i5Sto*s O~63.6  :> 0:.636 Hortzontat I Vertica' :

{DC( J s O~315 > 0.315 to s 0.70 >0.'70 Inboard

... ". '* . I~G /;1:0

\,

L~~::!~~.* ,_~_~~,_"_"__~~~ . .* . L _ _2~e ~o ~!~

Attachment 4 Valve Test Data M*.

Sheet 1 of 1

_um""''''''''''h -" .",.:,u......*.._.

~ .,. <_,,~. ____. ~. h_

PRETEST FAIL SAFE rosrrssr ALIGNMENT FULL

........ -.......... STROKE TEST

............. TEST ALIGNMENT ACCEPTANCE y",,131TERIA (SEC)

CODE CR.tTERI.A Verification Stroke Time LIMlT1NGVALUE ofT"ravel by (SEC) I OPEN SHUT

'Valve Pretest Ind Lights  : Fail Safe Position Pusttes!

Number Position I:Htt (lNIT) OPEN SHUT: Positlon Verified *Pos.iUon Pos lnit Vert loit Low High Low High OPEN SHUT 1AF-55 Open ffO !fJ l/Pt~fo 1&.1" NIA NtA Open }6=>. :u 14.25 19~28 14,34 19;40 25~15 23.00 1AF...74 Open Aio Aw bb61~~;P~ -e, :0' NlA NIA Open

~ :i) f5~48 20.94 14,84 20.07 27.31 23.00 Comments: .,..".,.....,.,.....- .<<ovm<_'<<"=_ .* " *****.*._.vwm.*..... wm"hwu.

...* *.*.* *.VII' * ...,..._ _*..a* *b*.*.* *.'.* ' ~ "A <<.:...:A.:.:..,_O'<< ".:*.*: ' .....:. b *:**v*.i( * *..**** * * *** ** **

....... ~  ;.;.; ; ;.: ,.; <N._ N .-"...; N .. ~_ _ J'.I'_.+-.-. _ _*_,.v.*.*..I'>............................................................ . . . - ._..-.-'w ~ .....-vvY.y.,..w. ~

~ ..

...-;~-...x<<<<o: -:<;;Xo<<~~ __. _~ cccccccee <.;..OC;"':O:':<_........-_<hV<hV<hV<hV h~AQ;y,;<<o;.y;;oc;.,.; .~.--"..No'N:N NN N~........:<< <<<<'i.<<-;-; ;.; ;*;..:*:.:*;.:.:-:<<.>>: :<< : : -'- <N ~" :.:.-.~.w.r.*.*.* * *** NU *"""""" ......:. ~~.; .."j /vu'**u.* u.*.*.*.*

L?ST~1211 I Rev. 16 I Page 21 0126 1

Attachment 5- Valve Retest Data S'heet Sheet 1 of 2 NOTE: This entire Attachment is N/A if no valve is retested due to exceeding the CodeCrttena.

Determine if the. stroke time exceeds the Limiting Value,

1. If the stroke time exceeds the limlting Value, declare the valve inoperable and initiat.e* aCR~ (NIAifstroke time is less than the LirnltlnqValue) 2.. lfthe stroke time is. less than the Limiting Value.but outside the Code Onteria limits, perform the foUovving :Steps:

8. If the cause is known to be mechanical failure~or if a retest cannot be performed expeditiously, declare the valve inoperable and inJUate a CR(Except PMTRs).

b. If retestlng the valve is desired perform the following:

N:OTE:. If necessary separate markedup sheets of this CST maybe used to document necessary manlpulatlons. sheets would this procedure and noted in the comments Section of Attachment 7.

(1) Determine wbich Ste:ps need to beperfcrrned up conditionstor testing the valve. Unit SeQ concurrence must be obtained and documented in the Comments section of Attachment 7>

(2) Perform the Steps determlned in the previous Ste'p anddocument stroke times/valve positioning on Sheet2.

(3) ~f retest results are still outside the Code Crlteria~declare the valve inoperable and initiate aCR (except Prv1T),

(4) 1f retest results-are Within the Code Criteria perform the .following:

y (a) Dec~are the valve operable.

(b) Inltl~.tea CR. identify1ng test findings for the first and second tests.

(c) Send test results to Responsible Engineer (1ST) for evaluation and docurnentanonon the CR.

IOST-1211 Page 22 of 26 I

Attachment 5 ~ V,alveRetest Data Sheet Sheet 2. of 2 (1) FUI out PRETEST ALIGNMENT POSTT;EST ALIGNMENT, and ACCEPTANCE CRITERIA values for the velvets) being t

tested using the values in the initIal test Attachment,

~~

~~::....;;..;.:.:y:w .':..->>...:***..:. ........ ,-

PRETEST ALIGNMENT (1) F.]J.~l. STROKETt=$T POSTIEST ALIGNMENT (1) ". <<-=<<-x-CO.9.E CRITERIA ACCEPTANCECRJTERIA (SEC) tt}

I I

J Time ~

(SE:C) OPf:N $HVT... LIMITfNG VALUE Pretest

• \l'a'dve i!'l:\JlnUf.:n

. Posmon tntt: OPEN SHUT Posttest Position Pes lnit Verflnif Low High Low High OPEN I i .StrUT

~

~

I i

~

~

~~11*. ,,_.........:MW ~

... . .... . , _=t Rev. 16 I Page 23 of ~61

Attachment 6*~ Certification and Review Sheet 1 of 2 T:hiS CST was performed as a: Periodic Surveillance Requirement: _~ __

Postmalrrtenance OperabHity Test: _

Redundant SUbsystem Test:

PlantConottlons: Mode:

--~~~~~----------_.............--

OST Compl.etedBy: - ..-..-< Date: ToDAt Time: tq~3(~)

OS.1 . P~.rfofrf1ed Bv:

Initials Name (Print) Initials Name (Print)

General Comments/Recomm:endation/Corrective ActionslExceptions:

I()$T-1211* L Rev. 16 m mJ Page 24 of 26 I

Attachment 6 ~ Certifications and Reviews Sheet 2 of 2-Step 7,1.11 1A..SA AF\'V Pump Inoperable Time: fJ10 t::.

~-~'~"oXA ~v;o;,o ;o;.~

'Tc)J:r-ti Date: :~"X'.xo;:<<  ;~_"_~-o;,"XX..;-

Step 7~1.32 1A-SA AFW Pump Operable- Time:_~__=l-L Date: ~:IJ:fDfft=_

Step 7.2.1.c 1A-SA and 1 B-S-B AFWPump Inoperable Time:tot5 __~ Date: ~Jilt Step 7~2~1,p 1A-SA-and 1B.. SBAFW Pump Operable Time: 1,~;~.,5"" . .- Date: ~JcJtfl~t,~,

Pa.ges Used: Atl~_~~_

CST Completed with NO EXCEPT10NS1EXCEPTIONS:

Reviewed By: Date:

Unit SeQ ResponsibieEngin"eer (1ST)

Reviewed By: Date:

ANn ----

After receiving the final review signature, this OS:T becomes a a-A RECORD and should be submitted to Document Servloes. .

IOST-1211 Revy16

R~.vtsion S~Jmmary General Revision 16 updates the procedure reference to the new 1ST Program Plan, Des9ription o.fChanges

• Page. Section Ghange Description Ail All Updated revision level.

3 1~O+2 Adde.d check valves 1AF-231 54 92, 11 O~and 73.

1 3 t~O.4 Deleted, 5 2~7.4 HNP-*lST-003, HNP 1ST Program Plan - 3rd tntervat, 8 6+0~1.e~(1 ) Changedacceptancecriterla per calc, (Also cbanqed on Atta'chme*nt2) 8 6~O.1.b Deleted "Parnat'strcke 8 6.Q.1.c Added check valves 1AF-23, 54$ 92 1 110~ and 73.

9 7.1.5 Added check valves 1AF~54,92~ and 73.

11 7+1.24 Added check va'hte1AF-23$110 17 Attachment 2 Added checkvalves 1AF*-23*~541 92, 110 , and 73~

Rev. 16 Page 26 of 26 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.:

Task

Title:

Given a Declared Emergency, JPM No.: 2008 NRC RO-SRO A3 Determine the Dose Rate, Dose Limit, and the Number of People to Perform a Task.

KJA

Reference:

2.3.4 (2.5/3.1)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant Perform in a location with the general references available or with electronic access to the references.

READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

• A large break LOCA has occurred.

• The ECCS is in cold leg recirculation.

• RHR Pump "8" is running. RHR Pump "A" showed evidence of gas binding and was stopped.

• A Site Area Emergency (SAE) is in effect.

• The Emergency Engineering Organization has determined that the RHR Pump "A" should be vented to ensure that a backup is available.

• The general radiation level in the area is 16 R/hour

• The OSC estimates that the total task will take. 75 man-hours.

• The Site Emergency Coordinator has specified that he/she will not authorize an extension to the site emergency workers dose limit for performance of this task.

Task Standard: Number of people and stay times calculated within specified limits.

Required Materials: Calculator HARRIS08 NRC RO-SRO A3 Revision 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet General

References:

• PEP-330, RADIOLOGICAL CONSEQUENCES

• NGGM-PM-0002, RADIATION CONTROL AND PROTECTION MANUAL Initiating Cue: The site emergency workers listed in the table below are available.

They will be utilized from lowest to highest accumulated TEDE dose.

Using the minimum number of workers possible, DETERMINE:

• the total number of workers required to perform the task and

• the maximum stay time for each individual who will be utilized.

Assume no dose in transit and round off to the nearest minute below the limit.

Time Critical Task: NO Validation Time:

HARRIS08 NRC RO-SRO A3 Revision 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A HARRIS08 NRC RO-SRO A3 Revision 2 NUREG 1021, Revision 9

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

Performance Step: 1 Determine total estimated dose for the task.

Standard: 16 R/hour x .75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> = 12 Rem Comment:

Performance Step: 2 Determine the dose limit for site emergency workers Standard: Per PEP-330 - Attachment 1: 5 Rem Comment:

~ Performance Step: 3 Determine the number of people required Standard: Workers A, B, and C would have to be used (~) to reach the 12 Rem total estimated dose (4700 + 4450 + 4300 = 13.45)

Comment:

HARRIS08 NRC RO-SRO A3 Revision 2 NUREG 1021, Revision 9

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION

~ Performance Step: 4 Stay Time for Workers Standard: A: 4.7/16 x 60 minutes = 17 minutes B: 4.55/16 x 60 minutes = 17 minutes C: 4.30/16 x 60 minutes = 16 minutes Comment:

Terminating Cue: After the maximum stay time for the workers to be used is calculated: Evaluation on this JPM is complete.

STOP TIME:

HARRIS08 NRC RO-SRO A3 Revision 2 NUREG 1021, Revision 9

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC RO-SRO A3 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

HARRIS08 NRC RO-SRO A3 Revision 2 NUREG 1021, Revision 9

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• A large break LOCA has occurred.

• The ECCS is in cold leg recirculation.

• RHR Pump "B" is running. RHR Pump "A" showed evidence of gas binding and was stopped.

• A Site Area Emergency (SAE) is in effect.

• The Emergency Engineering Organization has determined that the RHR Pump "A" should be vented to ensure that a backup is available.

• The general radiation level in the area is 16 R/hour

• The OSC estimates that the total task will take. 75 man-hours.

• The Site Emergency Coordinator has specified that he/she will not authorize an extension to the site emergency workers dose limit for performance of this task.

INITIATING CUE: The site emergency workers listed in the table below are available. They will be utilized from lowest to highest accumulated TEDE dose.

Using the minimum number of workers possible, DETERMINE:

• the total number of workers required to perform the task and

• the maximum stay time for each individual who will be utilized.

Assume no dose in transit and round off to the nearest minute below the limit.

Site Emergency Worker Accumulated TEDE Dose This Year A 300 mr B 450 mr C 700 mr D 800 mr E 850 mr F 1000 mr G 1050 mr H 1150 mr I 1200 mr J 1300 mr K 1500 mr L 1650 mr HARRIS08 NRC RO-SRO A3 Revision 2 NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: HARRIS Task No.: 345001H602 Task

Title:

Evaluate a Change in Conditions on JPM No.: 2008 NRC JPM SRO an Existing EAL A4 KIA

Reference:

2.4.41 (4.1)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing: This JPM can be performed in any setting with the required references available.

Simulated Performance: Actual Performance: x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: See Plant Conditions handout.

Task Standard: Upgrade EAL to GE and correct PAR within required time.

Required Materials: None General

References:

• PEP-110, EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS, Rev. 16

• PEP-230, CONTROL ROOM OPERATIONS, Rev.14

• PEP-310, NOTIFICATIONS AND COMMUNICATIONS, Rev. 21 Handouts:

• Attached Initial Conditions

• EAL Flowcharts

• PEP-110

• PEP-310

• EP/EAL Guidelines

• PEP-230, Attachment 1 - SITE EMERGENCY COORDINATOR Initiating Cue: You are the Site Emergency Coordinator. Review the plant conditions handout sheet and determine the current Emergency Action Level (EAL). This is a time critical JPM. The clock starts after you have reviewed the Plant Conditions sheet.

Time Critical Task: YES - 15 minutes to classify then 15 more minutes to make the PAR.

HARRIS 2008 NRC SRO A4 Revision 2 NUREG 1021, Revision

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 10 minutes to classify, 12 minutes for PAR/Emergency Notification Form.

HARRIS 2008 NRC SRO A4 Revision 2 NUREG 1021, Revision

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a ~)

Start Time: _

Performance Step: 1 Evaluate changing conditions.

Standard: Compares conditions against EAL Flowchart criteria.

Evaluator Cue:

• Provide Initial Conditions sheet (last page of JPM).

• Provide reference materials if not available in the JPM performance location.

. Comment: Classification Start Time _

-Y Performance Step: 2 Determine EAL.

Standard: Upgrade to GE (2-1-4) required:

• RCS Breached

• Fuel Breached - DEI sample> 300 uCi/cc

• CNMT Jeopardized - Pressure> 3 PSIG Evaluator Note:

• It may be necessary to cue the PAR performance. The facility normally splits the EAL and the PAR into two JPM's.

• If the applicant incorrectly classifies then skip to the Evaluator Cue in Performance Step 3.

Comment: Classification End Time/PAR Start Time _

HARRIS 2008 NRC SRO A4 Revision 2 NUREG 1021, Revision

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

~ Performance Step: 3 Determine PAR (PEP-230, Attachment 1, Step 10).

Standard: Refers to PEP-110, Attachment 3:

PROTECTIVE ACTION RECOMMENDATION:

• EVACUATE: 2 mile radius

• EVACUATE: Subzones A, B, L

• SHELTER: Subzones C, D, E, F, G, H, I, J, K, M, N Evaluator Cue: The computer program is not available. Hand write a paper copy of the Manual Notification Form in accordance with PEP-230, Attachment 1, Step 11.b.

Comment:

~ Performance Step: 4 Complete the ENF.

Standard: Critical Elements:

• Block 4: GE

• Block 4 EAL: 2-1-4

• Block 5 PAR: Evacuate 2 mile radius and Subzones A, B, L; Shelter Subzones C, D, E, F, G, H, I, J, K,M,N

• Block 6 Emergency Release: Is Occurring 0

• Block 9 Wind Direction from: 126

• Block 10: DECLARATION; Current TIME; Current DATE

• Block 17: Applicant signature/Title/Current Time/ Current Date

• Provide form to Communicator Evaluator Note: An ENF KEY is attached, Comment: PAR Notification End Time _

Terminating Cue: After the ENF is handed to the communicator: Evaluation on this JPM is complete.

HARRIS 2008 NRC SRO A4 Revision 2 NUREG 1021, Revision

Appendix C Page 5 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM SRO A4 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

HARRIS 2008 NRC SRO A4 Revision 2 NUREG 1021, Revision

Appendix C Page 6 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: See Plant Conditions handout.

INITIATING CUE: You are the Site Emergency Coordinator. Review the plant conditions handout sheet and determine the current Emergency Action Level (EAL). This is a time critical JPM. The clock starts after you have reviewed the Plant Conditions sheet.

HARRIS 2008 NRC SRO A4 Revision 2 NUREG 1021, Revision

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET 2008 NRC JPM SRO A4 Plant Conditions

• Increasing RCS leakage required a MANUAL Reactor Trip and Safety Injection

• The TDAFW Pump is cleared and tagged

• The RCS leak escalated to a large-break LOCA while the crew was performing PATH-1

• Containment Spray actuated

• There is a RED CSF on INTEGRITY

• The EAL Network was entered at Point X

• A Site Area Emergency (SAE) is in effect with the RCS breached (EAL 2-1-3) and Containment jeopardized

• Outside temperature is 62 of

• Thunderstorms are moving into the area

• The wind is blowing at 12 MPH from 126 degrees

• Since the SAE declaration, the following has occurred:

• Plant computers are down which will require any additional notifications to be done using a manual notification form

• Off-site power was lost and EDG 1B failed while starting

• ECCS cold leg recirculation alignment on Train "A" was just completed

• Containment Pressure is 3.8 PSIG, lowering slowly

• Containment Area Radiation Monitors are in HIGH alarm, rising slowly

• Contalnrnent High Range Monitors are rising but not in alarm

• Plant Vent Stack #1 Monitor is rising slowly but not in alarm

• Charging Pump "A" Room Monitor went into HIGH alarm after cold leg recirculation was initiated

• Chemistry has analyzed a sample and reports an Iodine Dose Equivalent RCS concentration of 410 uCilcc HARRIS 2008 NRC SRO A4 Revision 2 NUREG 1021, Revision

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Attachment 3 - PROTECTIVE ACTION RECOMMENDATION PROCESS Sheet 1 of 2 No No Fuel Breach)

No (Yes/ due to Res Breach) 2 MliileRadius :5 Miles Downwind Wiind IEvacuaie Shelter Wind Evacuat,e; She-Iter Direction Subzones :Subzooes rn recti 00 Subzones Subzone'S

~From {From 'tfj 34a~

- 010' AB,C,O;H,U<.L E.F~G,J,M.N -

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1251;1 1'91= A,H"L C.D,E"F.G,H,I,J,KM.N I 102(1 -, 124a AFB,C,D,r~l,U E"F"G,HJ.J,N 1920- 214.: A,B C,D,E.F"G,H,tJ,K.LM.N 125~ 14&- AB,C,D,KL,M.Nl E"F~G,HJ.J 215 Cl

-259=' A,B.e D,E"F.G,HJ.J,K.L,MJ~

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282c 3(14':' A,C,D B"E,f,G,.H"I"JJ<.LM,N 215 t , - zse- A.B,C,D,E"K,l f,G"HJ"J~M,N 305(1 - 328~ A,D B"C,,E,F,G.,H,,I,,J,,K,LM.N 237 t \ -, 2§9a A,,B,C,D,E.F,,K,l GI'H.tJ..M.N

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Attachment 3 - PROTECTIVE ACTION RECOMMENDATION PROCESS

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Sheet 2 of 2 Acceptable changes in initial PARS would include expanding evacuation but would not allow a change from evacuation of zones to sheltering of those zones.

1. Indications that substantial core damage is imminent or has occurred include:

a) Core damage> 1°A, melt.

b) Core Exit Thermocouple readings ~ 2300° F.

c) Core uncovered> 30 minutes.

2. Indications that a significant loss of reactor coolant is imminent or has occurred include:

a) Containment radiation reading> 10,000 RlHr without spray or> 4,000 R/Hr with spray.

b) Containment hydrogen gas concentration> 1o.k>.

c) Rapid vessel depressurization.

d) A large break loss of coolant accident.

3. Indications that containment failure (primary or S/G) is imminent or has occurred are indicated by:

a) A release of radioactivity greater than the projected dose of either:

• 1000 mRem TEDE at or beyond the site boundary.

5000 mRem Thyroid CDE at or beyond the site boundary.

Or a measured dose rate of either:

>1000 mRem/hr at or beyond the site boundary.

1-131 equivalent concentration> 3.9 E-6 IJCi/cc at or beyond the site boundary.

b) Primary containment pressure can not be maintained below design basis pressure of 45 psig.

c) Primary containment H2 gas concentration can not be maintained below combustible limit of 4%

by volume.

d) Faulted/Ruptured S/G with a relief valve open.

4. Accidents which result in a direct release pathway to the environment will most likely be thyroid dose limiting. For a faulted and ruptured S/G, water level must be below the tube bundles (S/G Narrow Range < 25% normal containment conditions or < 40% adverse containment conditions) with a relief valve open before it is considered a direct release pathway to the environment. For circumstances involving a direct release pathway to the environment:

a) Consider any Fuel Breach sufficient to warrant the determination that substantial core damage has occurred.

b) Consider any RCS Breach sufficient to warrant the determination that a significant loss of reactor coolant has occurred.

NOTE: A direct release is defined as a pathway from the containment to any environ-ment outside the containment when containment or system isolation is required due to a safety injection signal, containment pressure greater than 3 psig, or a valid containment ventilation isolation signal and the pathway cannot be isolated from the Main Control Room.

Containment monitors can provide indication of both core damage and RCS breach. Monitor readings used to quantify an amount of damage or coolant leakage should be complimented by other indications and engineering judgment.

If a release is in progress:

• Perform dose assessment as soon as possible to determine if PAGs are exceeded and if additional Subzones require evacuation.

• Add any Subzones requiring evacuation as determined by dose assessment to the plant-based PARs.

If no release is in progress:

• Perform dose projection on possible conditions as time permits to determine if PAGs could be exceeded. Consider adding any Subzones requiring "evacuation as determined by dose projection to the plant-based PARs.

I PEP-110 Rev. 16 Page 19 of 261

1. I Attachment 9 - NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM DRILL I§J ACTUAL EVENT rz!::Of MESSAGE #

1

~ N Today 2.1 INITIAL @JFOLLOW-UPNOTIFICATION:TIME ow DATE_ _/_ _/_ _ AUTHENTICATION # _

3. SITE: HNP Confirmation Phone # (_ _) _

4. EMERGENCY CLASSIFICATION:

~ UNUSUAL EVENT I§I ALERT 19 SITE AREA EMERGENCY

• GENERAL EMERGENCY BASED ON EAL # 2 4 EAL DESCRIPTION: 3 FPBs Breached/ Jeopardized

5. PROTECTIVE ACTION RECOMMENDATIONS: ~ NONE IEVACUATE 2 mile radius and Subzones A,B,L ISHELTER Subzones C,D,E,F,G,H,I,J,K,M,N IQI CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY.

I§ OTHER _

6. EMERGENCY RELEASE: ~None I Is Occurring 19 Has Occurred

7. RELEASE SIGNIFICANCE: ri\I Not applicable I!j B Within limits normal operating Above normal operating limits I Under evaluation

8. EVENT PROGNOSIS: ~ Improving I Stable 19 Degrading

9. METEOROLOGICAL DATA: Wind Direction* from 126 degrees Wind Speed* 12 mph

(*Not Requiredfor Initial Notifications) Precipitation* Stability Class* ~ I§J 19 (QJ I§ lEI I§I

10. I DECLARATION I§J TERMINATION Time Date / / _

(Enters Current Date and Time)

11. AFFECTED UNIT(S): * [J [I I6ill

12. UNIT STATUS: I U1 _0_0/0 Power Shutdown at Time Date _ /_ _/ _

(Unaffected Unit(s) Status Not Required for Initial Notifications) ~ U2 _ _% Power Shutdown at Time Date _ /_ _/ _

§ U3 _ _0/0 Power Shutdown at Time Date _ /_ _/ _

13. REMARKS: _

FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)

EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.

14. RELEASE CHARACTERIZATION: TYPE: ~ Elevated I§I Mixed 19 Ground UNITS: ~ Ci I§J Ci/sec 19 ~Ci/sec MAGNITUDE: Noble Gases: lodines: Particulates: Other: _

FORM: ~ Airborne Start Time _ _ _ _ Date _ /_ _/__Stop Time _ Date _ /_ _/__

I§J Liquid Start Time _ _ _ _ Date _ /_ _/__Stop Time _ Date _ /_ _/__

15. PROJECTION PARAMETERS: Projection period: Hours Estimated Release Duration Hours Projection performed: Time Date _ /_ _/__

16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem)

Site boundary 2 Miles 5 Miles 10 Miles

17. APPROVED BY: (Sign and Date) Title Time Date_/_ _/__

NOTIFIED RECEIVED BY: BY: Time Date / /

I PEP-310 I Rev. 21 Page 33 of 51 I