ML041070247

Feb-March 2004 Exam 50-280, 50-281, 2004-301 Draft JPMs and Outlines

ML041070247
Person / Time
Site:	Surry
Issue date:	02/19/2004
From:	NRC/RGN-II
To:
References
50-280/04-301, 50-281/04-301
Download: ML041070247 (138)

Text

Draft Submittal (Pink Paper)

SURRY EXAM 50-280, 50-281/2004-301 FEBRUARY 24 MARCH 2

& MARCH 4,2004 (WRITTEN)

Through

Surry 2004-301 Emergency Classification I

CLASSIFY A STATION EVENT IAW EQIP-1.01 (11).

5 Minutes G2.4.44 (2.1/4.Q)

Surry JPM b08-4 7 EPIP-I.01, Emergency Manager Controlling Procedure, Rev. 43 Applicant:

Petforrnance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 6

SUrW 2004-301 Emergency Classification Task is to be PERFORMED in the Main Control Room, Simulator Control Room, or Classroom.

s.wxix&

e "General Emergency" declared BAW EPIP-1.01.

You are to determine if the event should be classified IAW PEP-1 .Ol and if classification is required, make the classification IAW EPIP-1.01.

When you finish the actions necessary to accomplish this, please inform me of your findings and classification, if applicable olling Procedure, Rev. 43 None Page 2 of 6

Surly 2004-301 Emergency Classification 0 Task critical elements are denoted by an asterisk (*)' If substeps of a critical element also have an asterisk r),

then only those asteriskecl substeps are critical to performance of that task element.

e STARTTIME:

Step 1 OBTAIN EPBP-1.Of EMERGENCY MANAGER CONTRObblNG PROCEDURE

~

SAT Standard UNSAT a) Obtains SEM emergency package (or STA classification package).

b) Gets copy of EPIP-1.01, EAL Tabs.

Evaluator's Comments Step 2 DETERMINE EVENT CATEGORY. SAT Standard UNSAT a) Tums to EPIP-1.01, Attachment 1, page 1, EAL Table Index.

b) Determines event category to be a RADIOACTIVITY EVENT.

c) Turns to TAB E.

d) Evaluation of B and G TABS may also be made.

Evaluator's Comments

• step 3 CLASSIFY EVENT. -- SAT SkWKkWel UNSAT a) Determines that event is E-1, Release imminent or in progress and site boundary doses projected to exceed 1.0 Rem TEDE or 5.0 Rem Thyroid CDE.

b) Classifies event as a General Emergency.

STQP TIME:

Page 3 of 6

Surry 2804-301 Emergency Classification Page 4 of 6

Surry 2004-381 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Iaslr Task is to be PERFORMED in the Main Control Room, Simulator Control Room, or Classroom.

CLASSIFY A STATION EVENT IAW PIP-1.01 (1 1).

The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue.

Ensure you indicate to the evaluator when you understand your assigned task You are the Nuclear Shift Manager. A Design Basis Steam Generator Tube Rupture has occurred with the associated SG Safety Valve stuck open. Pressurizer level cannot be maintained with the SI system and HP reports projected doses at the Site Boundary are greater than 0.8 Rem TED and 6.0 Rem Thyroid CDE. The operating team has just entered E-3.

You are to determine if the event should be classified IAW PIP-1.Ql and if classification is required, make the classification IAW EPIP-1.01.

e When you finish the actions necessary to accomplish this, please inform me of your findings and classification, if applicable.

Surry 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT) ask e Task is to be PERFORMED in the Main Control Room, Simulator Control Room, or Classroom.

e CLASSIFY A STATION EVENT IAW EPIP-1.01 (11).

The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue.

Ensure you indicate to the evaluator when you understand YOUF assigned task e You are the Nudear Shift Manager. A Design Basis Steam Generator Tube Rupture has occurred with the associated SG Safety Valve stuck open. Pressurizer level cannot be maintained with the SI system and HP reports projected doses at the Site Boundaw are greater than 0.8 Rem TED and 6.0 Rem Thyroid CBE. The operating team has just entered E-3.

You are to determine if the event should be classified lAW PIP-1.81 and if classification is required, make the classification IAW PIP-I .04.

e When you finish the actiofls necessay to accomplish this, please inform me of your findings and classification, if applicable.

Surry 2804-301 Stay Time Calculation 16ask CALCULATE STAY TME Ai3umm RO/SRO 5 Minutes G2.3.1 (2.6/3.1)

G2.3.4 (2.5B.1)

Dominion Nuclear Employee Braining Manual Volume II BRWT RPB CST SCAT FWT, Revision f 1, January, 2003.

Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 5f 7

Surry 2004-301 Stay Time Calculation

. Task is to be PERFORMED in a classroom.

Standards e Stay times are correctly calculated.

e You are to answer two radiation control questions, placiflgl your responses on the paper containing the questions.

When you finish responding to the questions, inform an examiner.

s examiner that answers to both questions have been completed.

e Applicants may request various procedures.

a Calculators Page 2 of 7

Surry 2004-301 Stay Time Calculation Task critical elements are denoted by an asterisk (*) If substeps of a critical element also have an asterisk PI, then only those asterisked substeps are critical to performance of that task element.

STARTTIME:

• Step 1 APPLICANT ANSWERS QUESTION 1 SAT Standard UNSAT Applicants response is 25.5 minutes OW 25 minutes 30 seconds.

Page 12 of above reference states that the Quarterly TED Admin Limit is 2 rem and the Annual TEDE Limit is 4 rem.

Margin to yearly limit = 4.00 - [ 0.72 + 1.98 -t0.131 = 1.17 rem (more limiting)

Margin to quarterly limit = 2.00 [ 0.131 = 1.87 rem

~

[ 1.17 rem] / [ 0.400 rem / hr] = 2.925 hour0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 55.5 minutes = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 55 minutes 30 seconds

• Step 2 APPLICANT ANSWERS QUESTtON 2 -- SAT Standard UNSAT Applicants response is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 18 minutes OW 2.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Page 12 of above reference states that the Annual TEDE Limit is 4 rem, but may be granted a dose extension up to 4750 mrem with proper management approval.

Margin to yearly limit = 4.75 - [ 0.72 + 1.98 + 0.131 = 1.92 rem Margin to quarterly limit = 2.00 - [ 0.131 = 1.87 rem (more limiting)

[ 1.87 rem] 1[ 0.480 rem / hr] = 4.675aerr = 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 40 minutes 30 seconds STOP PBME:

EvaBuators Comments Page 3 of 7

2004-301 Stay Time Calculation Page 4 of 7

Surry 2804-301 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

I&&

To be performed in a classroom.

Answer radiation control questions.

The evaluator will read the questions that are to be answered and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

D An operator must perform work in an area with a general dose rate of 400 mremhour.

D It is currently the third annual quarter of the year.

D The operators quarterly accumulated dose for TED is as follows:

D Quarter 1: 0.72 Rem Quarter 2: 1.98 Rem Quarter 3: 0.13 Rem m You are to answer two radiation control questions, placing your responses on the paper containing the questions.

0 When you finish responding to the questions, inform an examiner.

Surly 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Iask To be performed in a classroom.

o Answer radiation control questions.

The evaluator will read the questions that are to be answered and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

o An operator must perform work in an area with a general dose rate of 400 mremhour.

o It is currently the third annual quarler of the year.

The operator's quarterly accumulated dose for TED is as follows:

o Quarter 1: 0.72 Rem o Quarter 2: 4.98 Rem o Quarter 3: 0.13 Rem o You are to answer two radiation control questions, placing your responses on the paper containing the questions.

When you finish responding to the questions, inform an examiner.

Surry 2004-301 (TO BE GIVEN TO APPLICANT)

QUESTION 1:

What is the maximum time the worker can stay in the area without violating Dominions Administrative Dose Limit for TEDE?

(Assuming no dose extensions to the Administrative Limits)

QUESTION 1:

What is the maximum time the worker can stay in the area without violating Dominions Administrative Dose Limit for TEDE?

(Assuming the maximum dose extensions to the Administrative Limits are approved by management)

Surry 2004-301 SDM Calculation Task PERFORM A SHUTDOWN MARGIN CALCULATION AT ZERO POWER.

Applicability Est Completion Time Actual Time RQ/SRO 60 Minutes WA (Importance Ratinqs)

(32.1.7 (3.7/4.4)

References Station Curve Book, Rev. 63 1-OP-RX-O02, Shutdown Margin (Calculated at Zero Power), Rev. 013.

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 12

Surry 2004-301 SDM Calculation Conditions Task may be PERFORMED in the simulator (or any other area with access to a Station Curve Book).

Unit 1 ramped off-line from 76% power.

Standards 1-OF-RX-002, Shutdown Margin (Calculated at Zero Power) lnitiatina Cues Shift Supervisor directicn Terminatlnq Cues D 1-0P-RX-002, Shutdown Margin (Calculatedat Zero Power) completed.

Tools9Equipment, and Procedures 1-0P-RX-002. Shutdown Margin (Calculated at Zero Power)

• Station Cuwe Bo&

D Calculator Safetv Considerations Ncne Page 2 of 12

20634-301 SDM Calculation PERFORMANCE CHECKLIST Notes Po the EvaBuator.

The trainee will utilize a Curve Book to locate the necessary curves for 1-OP-RX-002.

Task critical elements are denoted by an asterisk (*). If substeps of a critical element also have an asterisk (*),

then only those asterisked substeps are critical to performance of that task element.

Critical step sequencing requirements: None a STARTTIME:

Step 1 REVIEW ADMINISTRATIVE SECTIONS OF 1-OP-RX-002. SAT Standard UNSAT a) Reviews Section 1, Purpose b) Reviews Section 2, References c) Reviews Section 3, Initial Conditions d) Reviews Sectlon 4, Precautions and Limitations Evaluator Comments Step 2 RECORDS PREVIOUS CRITICAL CONDITIONS NEEDED TO DOCUMENT AND PERFORM SAT THE SHUTDOWN MARGIN CALCULATIONS IN SECTION 5.1 UNSAT Standard a) Determines and records time and dare of previous critical conditions. (Yesterday -

1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />) b) 5etermines and records previous critical reactor power. (76%)

c) Determines and records previous critical boron concentration.(800 PPM) d) Determines and records cycle burnup. (9,OQO MWD/MTU) e) Determines and records D Bank rod position at previous critical conditions. (180 steps on D bank)

Evaluator Comments Page 3 of I2

Surry 2004-301 SDM Calculation "Step 3 CALCULATES PARAMETERS FOR SECTION 5.1 FROM DATA RECORDED. SAT Standard I

- UNSAT a) Calculates Xenon Worth for 76% power to be 2475 pcm using the Xenon Reactivity Worth at HZP vs. Previous Equilibrium Power Level Curve. (2450 - 2500 acceptable) b) Calculates Power Defect for 76% power and 800 PPM boron to be 1525 pcm using the Power Defect Curve. (1 500 1550 acceptable) c) Calculates rod worth for 180 steps on "D" bank to be 242.55(220.5 X 1.I) using the AT Power Integral Rod Worth Table for Control Banks C 8, D in Overlap. (242.0 to 243.0 acceptable)

Evaluator Comments RDS REACTOR SHUTDOWN INFORMATION 188 SECTION 5.2 SAT Standard UNSAT a) Deterrnines and records time and date the reactor initially reaches shutdown. (today -

now b) Determines and records method of shutdown as an orderly shutdown and initial power prior to shutdown was 76%.

c) Determines and records that the orderly shutdown xenon curve best represents core conditions.

I Evaluator Comments Step 5 RECORDS SHUTDOWN CONDITIONS NEEDED TO DOCUMENT AND PERFORM THE SAT SHUTDOWN MARGIN CALCULATIONS 6N SECTION 5.3 UNSAT Standard a) Determines and records Cycle Burnup. (9,000 MWBIMTU).

b) Determines and records time and date covered by this SDM. (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching HSD).

c) Determines and records control rod position during shutdown conditions. (All rods in).

d) Determines and records that current boron concentration is 860 PPM.

e) Determines and records that minimum temperature during the shutdown is 14QF.

(Recalls from directions that the SDM is to Ise calculated for the minimum temperature throughout the shutdown)

Evaluator Comments Page 4 of 12

Surry 2004-381 SDM Calculation "Step 6 CALCULATE PARAMETERS FOR SECTION 5.3 FROM DATA RECORDED Standard a) Calculates worth of all rods to be 7352 pcm from the Total Rod Worth vs. Burnup Curve. (7350 7360 is acceptable)

~

b) Enters Zero (0) in blanks for worth of equivalent stuck rods, shutdown banks withdrawn and other rods out. (Wecalk from initial data that ali rods are in during the shutdown) c) Calculates Total Rod Worth to be 7202 pcm ( W O N of all rods + additional conservatism) (7200 - 7210 Acceptable) d) Calculates Temperature defect at 860 ppm boron and 140F to be 4207.5 pcm using the Hot to Cold Temperature Defect vs. Average Moderator Temperature Curve.

(4150 - 4220 acceptable) e) Enters (1550) pcm for value of xenon worth. (1 500 to 4 600 acceptable) f) Calculates Net lsotopic Decay to be Zero (0) pcm using the Net Isotopic Decay Reactivity After Shutdown from HFP Curve.

g) Calculates the Boron Coefficient at Zero Power to be 7.18 pcm/ppm using the Boron Coefficient vs. Burnup Curve. (7.15 7.25 acceptable) h) Calculates the Redistribution Factor to be 257 p m using the Reactivity Redistribution Factor vs. Burnup Curve. (250 - 260 acceptable)

Step 7 CALCULATES SUBCRITICAL MARGIN IN SECTION 5.4 Calculates Boron Reactivity from data previously calculated to be -430.8 pcm. (860 ppm - 800 ppm X 7.18 pcmippm) (-435.0 to -429.0 Acceptable)

Calculates Power Defect from data previously calculated to be 91525 pcm. (0 pcm -

(-1525 pcrn)) (1500 - I550 Acceptable)

Cdculates Temperature Defect from data previously calculated to be 4207.5 pcm.

(4207.5 pcm - 0 pcrn) (4150 - 4220 Acceptable)

Calculates Rod Worth from data previously calculated to be -6959.45 pcm (-7202 - (-

242.55)) (-6968.0to -6957.0 Acceptable)

Calculates Xenon Worth from data previously calculated to be +925 pcm (1550 pcm -

(-2475 pcm)) (850 - 1000 Acceptable)

Calculates Net Isotopic Decay from data previously calculated to be 0 pcm (0pcm - 0 pcm)

Calculates Reactivity Redistribution Factor (RRF) from data previously calculated to be +257 pcm (257 pcm - 0 pcm) (250 - 260 Acceptable)

Calculates Subcritical Margin by adding the above values to be -475.75 pcm (-653 to

-356 Acceptable)

Evaluator Comments Page 5 of 12

SUrV 2004-301 SDM Calculation

• Step 8 CALCULATES THE REQUIRED SUBCRITICAL BORON CONCENTRATION IN SECTION 5.5. SAT Standard UNSAT a) Identifies and records the required SDM to be -1 770 pcm.

b) Calculates the difference in reactivity between present SBM and required SDM to be

-1 294.25 pcm. (-1770 pcm - (+475.75p m ) ) (-141 4 to -1 117 acceptable) c) Calculates the required boron addition to be 180.26 ppm (-1294.25 pcmi-7.18 pcmlppm) (1 54.07 to 197.76 acceptable) d) Calculates the minimum Subcritical Boron Concentration to be 1040.26 pprn (860 ppm + 180.26 ppm) (1014.07to 1Q57.76acceptable) e) Determines that Attachment 3 does not need to be performed.

Evaluator Comments

• Step 9 VERIFIES COMPLIANCE WlTW TECHNICAL SPECIFICATION 3.92.A.4 IN SECTION 5.6 SAT Standard UNSAT a) Determines that RCS temperature will be greatw than 53OF during the time period covered by this SDM and proceeds to Attachment 2 of 1-0P-WX-002 to calculate the Critical Boron Concentration at HSD with B Bank Rods at 23 Steps.

b) Calculates Power Defect from data previously calculated to be 1525 pcm (1500 ~

9.500acceptable) c) Calculates the Reactivity Redistribution Factor from data previously calculated to be 257 pcrn. (250 - 260 acceptable) d) Calculates Xenon Worth from data previously calculated to be +925 pem (858 1000 ~

acceptable) e) Calculates Rod Worth at 23 steps on D Bank to be 1580.2 pcm using the HZP Integral Rod Worth Table for Control Banks C and B in Overlap Table (1570.4 to 1590.0 acceptable) f) Calculates Rod Worth from data previously recorded to be 1179.6 pcm. (1170.36 to 1189.0acceptable) g) Calculates Net Isotopic Decay from data previously recorded to be 0 pcm.

h j Calculates Temperature Defect at 530F and 860 PPM boron to be 250 pcm. (100 -

400 acceptable) i ) Calculates the reactivity change from previous critical conditions by adding the above listed values to be +1777.37 pcm. (1511.OO to 2039.64 acceptable) j) Calculates the boron equivalent of the reactivity change to be -247.54 ppm. (-285.26 to -288.41acceptable) k) Calculates the required critical boron concentration at WSD with CY Bank rods at 23 steps to be 1047.54 ppm. (800 ppm - (-247.54 ppm)) (1088.41 to 1085.26 acceptable)

I) Records value obtained in (j) above in Section 5.6 of $-OP-RX-O02 (this step not critical)

Evaluator Comments Page6of 1%

Surry 2004-304 SDM Calculation Step 10 VERIFIES COMPLIANCE WITH TECHNICAL SPECIFICATION 3.12.A.4. IN BORON DILUP[ON SAT SECTION 5.7.

UNSAT Standard a) Determines that temperature during time period covered by this SDM will be greater than 20QF and completion of Section 5.7 is required.

b) Determines that C WCP is to remain running while the unit is shutdown and enters NA for step 5.7.1 .a.

c) Recurds the lowest anticipated temperature during the time period C O V ~ by F ~this

~

SBM as 200F.

d) Calculates the value for boron concentration to be 1335 ppm using the 1.1 X Cb(N-1) vs Temperature at Various Burnups Curve for 20OF and 9,000 MWD/MTU. (1300 to 1375 acceptable.

e) Determines values for Equivalent Boron for worth of stuck rods is Zero (0) ppm.

f) Calculates the Adjusted Boron Dilution Accident Analysis Requirement to be 1335 ppm.(1300 bo 1375 acceptable)

Evaluator Comments Step 11 VERIFIES COMPLIANCE WITH TECHNICAL SPECIFICATION 3.12.8.4IN SECTION 5.8. SAT Standard -___ UNSAT a) Betermines that Attachment 3 was not performed and records the value from substep 5.5.2.b for step 5.8.1. (1040.26 ppm) (1014.07- 1057.76 acceptable) b) Enters the value for borun concentration from substep 5.8.1. (1047.54 ppm) (1008.41 to 1085.26acceptable) c) Enters the value for boron concentration from substep 5.7.1.b.5. (1335 ppm)(l380 to 4 375 acceptable) d) Determines that pressurizer spray is available and enters 0 ppm for step 5.9.4 (not a critical step) e) Enters value for highest borun concentration listed in Section 5.8 (1335 pprn)(l300 to 1375 acceptable)

Evaluator Comments Page 7 of 42

~~

Surry 2004-381 SDM Calculation Step 12 CALCULATES ADDITIONAL VOLUME OF BORIC ACID REQUIRED IN SECTION 5.9. SAT Standard UNSAT a) Records 860 ppm for the most recent measured boron concentration b) Records 1335 pprn from step 5.9.5(1300 - 1375 acceptable)

• c) Calculates number of gallons of boric acid to increase boron by 1 pprn to be 4.044 gallons/ppm based on present concentration of 860 ppm and 8.0 w/o in A BAST.

(4.0 to 4.1 acceptable) d) Calculates additional volume of boric acid to be added to be 1920.9 gallons. (1335 pprn - $60 ppm) X 4.044 (1760.0 - 21 11.5 acceptable) e) Informs SS that 1921 gallons of boric acid should be added to the RCS.

Evaluator Comments Step $ 3 COM$LTES SECTION 5.10 FOR FOLLOW ON ACTIONS SAT Standard UNSAT a) Records time and date for performance of the next SBM as 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching HSD.

b) Determines P-250 is in sewice and enters M/A for step 5.1 1.2.

c) Determines another SBM is needed and retains procedure to allow copying of data.

Evaluators Comments step 14 REPORT TO THE SHIFT SUPERWSOR SAT Standard UNSAT Verbal status report made. of task cornpietion STOP TIME:

Evaluators Comments Page 8 of 12

2004-301 SDM Calculation Page 9 of 12

Surry 2004-301 Operator Directloras Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task

• Task is to be performed in any location where the applicant has access to a Station Curve Book.

0 Task is to perform a Shutdown Margin Calculation.

Directions The evaluator wll explain the initial conditions of the task to be performed and will provide the initiating cue.

Ensure you indicate to the evaluator when you understand your assigned task Initial Conditions

• Unit 1 ramped off-line from 76% power.

• The Unit just reached HSD.

• Data sheet is provided containing the necessary calculation information.

Initiating Cues Perform a Shutdown Margin Calculation for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following Unit Shutdown.

e When you finish the actions necessary to accomplish this, please inform me.

SUrV 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Task 0 Task is to be performed in any location where the applicant has access to a Station Curve Book.

e Task is to perform a Shutdown Margin Calculation.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue.

Ensure you indicate to the evaluator when you understand your assigned task Initial Conditions e Unit 1 ramped off-line from 76% power.

0 The Unit just reached HSB.

e Dada sheet is provided containing the necessary calculation information.

Initiating Cues Perform a Shutdown Margin Calculation for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following Unit Shutdown.

0 When you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 (TO BE PROWDED TO APPLICANT)

ATTACHMENT 1 SHUTDOWN MARGIN CONDITIONS Previous Critical Conditions Data taken from stable conditions yesterday at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />.

e 76% Reactor Power - stable for previous 3 days with Delta Flux at Target Value.

6 800 PPIJ Boron e 9000 MWD/MBU e 180 Steps on D Bank Present Unit Conditions e Orderly ramp at 155 MWIHs began 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago e Unit is at HSB e 860 PPM Boron Shutdown Unit Conditions e All Rods fully inserted e Minimum Temperature during S/B is 140F e C RCP to remain running throughout shutdown e Spray valve 1-RC-PCV-l455A is available e A BAST boron concentration is 8.0 w/o P-250 computer is in service.

You are directed to perform a SDM to cover the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching HSD.

Surry 2004-301 Rx Vent Time Calculation Iask CALCULATE THE MAXIMUM ALLOWABLE REACTOR VESSEL HYDROGEN VENTING TIME WOISRO 5 Minutes 62.1 2 3 (3.914.0)

G2.1.25 (2.W3.1)

Rebrences Surry JPM LOW-10 FR-1.3, Response to Void in Reactor Vessel, Attachments 1 and 2, Rev. 16.

Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 8

Surry 2004-301 Wx Vent Time Calculation e Task is to be PERFORMED in the classroom.

e A simulated SBLOCA has occurred on Unit 1.

stzukds e Allowable vent time calcuiated IAW FW-1.3, Attachment I .

aximum allowable reactor vessel hydrogen venting time using FR-1.3, Attachments 1 and 2.

e When you finish the actions necessary to accomplish this, please inform me of the allowable vessel venting time.

e Report received of allowable vessel vent period.

e FR-1.3, Response to Void in Reactor Vessel, attachments I and 2.

e Calculator e None Page 2 of 8

Surry 2004-304 Rx Vent Time Calculation Task critical elements are denoted by an asterisk (1. If substeps of a critical element also have an asterisk p),

then only those asterisked substeps are critical to performance of that task element.

Critical step sequencing requirements: 1 & 2 (any order) before 3; 3 & 4 (any order) before 5.

STARTTIME:

• step 1 DETERMINE CONTAINMENT VOLUME (SBP). SAT Standards UNSAT a) Determines containment temperature from Initial Conditions.

b) Converts containment temperature in =I= to 8.(4 E C F+ 460 = 625 R) c) Determines containment pressure from Initial Conditions.

d) Inserts containment pressure and ORinto formula.

• e) Determines Containment volume (ref: 1.312 x lo6 Cu Ft).

Evaluators Note

• • This step is sequence critical.**

Evaluators Comments Step 2 DETERMINE CONTAINMENT HYDROGEN CONCENTRATION.

Standards a) Gets results of Chemistry department H2analysis from Initial Conditions.

6) Records Containment hydrogen concentration.

EvZdUa?OrSMote

• • This step is sequence criticai.**

Evaluators Comments Page 3 of 8

Surry 2004-301 Wx Vent Time Calculation

• Step 3 DETERMINE MAXIMUM HYDROGEN VOLUME PO BE VENTED. SAT Standards UNSAY a) Inserts H2concentration and containment volume into formula.

b) Determines max Hz volume to be vented. (Ref: 31488 Cu Ft).

Evaluators Note

• • This step is sequence critical.**

Evaluators Comments Step4 DETERMINE HYDROGEN FLOW RAPE BASED ON RCS PRESSURE SAT Standard UNSAT a) Consults Attachment 2 to determine hydrogen flow rate.

b) htermines RCS pressure from Initial Conditions.

• c) Based on RCS pressure of 1800 psig, determines flow rate (Ref: 8500 4-100 scfrn).

d) Records flow rate in step 4b.

Evaluators Note Thisstep is sequence critical**

Evaiuators Comments Step 5 CALCULATE MAXIMUM VENT PERIOD. SAT Standard UNSAT a) Recalls maximum H2volume and inserts into formula.

b) Recalls H2flowrate and inserts into formula.

• c) Calculates venting period as 3.70 minutes or 3 minutes 42 seconds (3.65 - 3.75 acceptable).

e) Records vent period in step 4d.

Evaluators Note

• This step is sequence critical.**

Evaluators Comments Page 4 of 8

Surly 2004-301 Rx Vent Time Calculation Step 6 REPORT TO NUCLEAR SHIFT MANAGER (EVALUATOR). SAT Standard UNSAT Verbal status report made of task completion.

STOP TIME:

Evaluators Comments Page 5 of 8

2004-301 Rx Vent Time Gaiculation Page 6 of 8

2004-301 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

E&

Task is to be PERFORMED in the classroom.

Calculate maximum allowable Reactor Vessel Hydrogen venting time.

The evaluator will exDiain the initial conditions of the task to be performed and will provide the initiating cue.

Ensure you indicate td the evaluator when you understand your assigned task.

D A SBLQCA has occurred on Unit 1.

FR-1.3, Response to Void in Reactor Vessel, Step 18 is being performed in response to a hydrogen void in the vessel head.

D RCS Pressure = 4 BOO psig Containment Pressure = 14.0 psia Containment Temperature = 165 O F Hydrogen Concentration = 0.6%

D Calculate maximum allowable reactor vessel hydrogen venting time using FR-1.3, Attachments 1 and 2.

When you finish the actions necessary to raccoimpliih this, pleise inform i n examiner.

2004-301 Operator Directions Handout (TO BE GWEN TO APPLICANT)

D Task is to be PERFORMED in the classroom.

Calculate maximum allowable Reactor Vessel Hydrogen venting time.

The evaluator will exdain the initial conditions of the task to be performed and will provide the initiating

- cue.

Ensure you indicate ad the evaluator when you understand your assigned task.

D A SBLOCA has occurred on Unit 1.

FR-1.3, Response to Void in Reactor Vessel, Step 18 is b h g performed in response to a hydrogen void in the vessel head.

D RCS Pressure = 48Q0psig D Containment Pressure = 14.0 psia Containment Temperature = 165 O F Hydrogen Concentration = 0.6%

D Calculate maximum allowable reactor vessel hvdwaen ventina time using FW-1.3. Attachments 1 and 2.

0 when ~ Q L finish J the actions necessary to accimpGh this, please inform i n examiner.

Surry 2004-301 Tagging Elements m

DETERMINETAGGING ELEMENTS / BOUNDARY DETERMINATION 25 Minutes G2.2.13 (3.6B.8)

B&xewes OQAQ-0030,BAG-OUTS, Rev. 16 11448-FE-1 K, 48DV One Line Diagram Sheet 5, Sheet 1 of I , Rev. 35 11448-FM-I24A, Steam Gen B ~ ~ W ~ Recirc O W Rand Xfer System, Sheet 3 of 4, Rev. 30 Applicant:

Pelformanee Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 7

Surry 2004-301 Tagging Elements Task is to be PERFORMED in a classroom.

6 Correctly state the critical elements of the tagging order.

uested to determine all requirementsielements necessary to prepare 1-RT-P-1C, Steam Generator

. Wecirc And Transfer Pump, for the required maintenance (Tag out elements, valvehreaker positions, etc).

Use the attached table to identify all components and their required positions. The number of blanks on this table

. does not indicate the number of steps in the tagout or the number of components to be tagged.

The order in which tags should be placed is not necessary.

When you finish responding to the questions, inform an examiner.

Computerized Tagging Systems are not operaticnal and may not be used for this bask.

e Applicant infcrms examiner that the task has been completed.

6 Applicants may request administrative procedures and plant drawings.

. None Page 2 of 7

Surry 2004-301 Tagging Elements Task critical elements are denoted by an asterisk (*).

0 STARTTIME:

8 I 1-RT-47,l -BT-P-lC Suction Drain I Open with Cap Removed I

STOP TIME:

Page 3 of 7

2004-301 Tagging Elements Page 4 of 7

Surry 2004-301 Operator Directions Handout (TO BE READ TO APPUCANT BY EXAMINER) hsk To be performed in a classroom.

Determine tagging elements / boundary determination for 1-RT-P-1C, Steam Generator Recirc And Transfer Pump.

The evaluator will explain the initial conditions and initiating cues. Ensure you indicate to the evaluator when you understand your assigned task. When you finish the task, inform an examiner.

eam Generator Recirc And Transfer Pump, has been experiencing high vibrations and requires maintenance.

1-RT-P-IC, Steam Generator Recirc And Transfer Pump, must be isolated electrically and mechanically to support maintenance.

You are requested to determine all requirementsielements necessary to prepare 1-RT-P-16, Steam Generator Recirc. And Transfer Pump, for the required maintenance (Tag out elements, valvehreaker positions, etc).

Use the attached table to identify all components and their required positions. The number of blanks on this table does not indicate the slumber of steps in the tagcut or the number of components to be tagged.

The order in which tags should be placed is not necessary.

When you finish responding to the questions, inform an examiner.

e Computerized Tagging Systems are not operational and may not be used for this task.

Surry 2004-301 Operator Directions Handout (PO BE GIVEN TO APPLICANT)

To be performed in a classroom.

Determine tagging elements I boundary determination for 1-RT-P-1C, Steam Generator Recirc And Transfer Pump.

The evaluator will explain the initial conditions and initiating cues. Ensure you indicate to the evaluator when you understand your assigned task. When you finish the task, inform an examiner.

earn Generator Recirc And Transfer Pump, has been experiencing high vibrations and requires maintenance.

e 1-RT-P-lC, Steam Generator Recirc And Transfer Pump, must be isolated electrically and mechanically to support maintenance.

You are requested to determine all requirements/elements necessary to prepare 1-RT-P-l C,Steam Generator Recirc. And Transfer Pump, for the required maintenance (Tag out elements$valvebreaker positions, etc).

Use the attached table to identify all components and their required positions. The number of blanks on this table does not indicate the number of steps in the tagout or the number of components to be tagged.

The order in which tags should be placed is not necessary.

When you finish responding to the questions, inform an examiner.

Computerized Tagging Systems are not operational and may not be used for this task.

Surry 2004-301 I I 24 t I I 24 i

Surry 2004-381 Cross Connect Instrument Air CROSS-CONNECT TURBINE BUILDING INSTRUMENT AIR TO CONTAINMENT.

RO/SRO 6 Minutes 065AK3.08 (3.7139) 065AK3.04 (3.013.2) 069AA2.02 (3.914.4)

S u r JPM

~ LO17-02 AKP 1B-FG, CTMT INST AIR LO HDR PRESS, Step 2 RNO, Rev. 1 Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 7

SlIrry 2004-301 Cross Connect Instrument Air e Task is lo be SIMULATED in the plant.

e Any plant msdekondition.

e 1-IA-448 and 1-IA-447 open.

periencing a loss of Ctmt IA pressure.

e Perform ARP 1B-F6, Step 1 and 2 WNO to manually align valves.

e When you finish the actions necessary to accomplish this, please inform me.

Turb Rldg 14 . cross-connected to containment.

e Zone 5 (Aux Bldg) Admin Key e ARP 1BF6, CTMT INST AIR LO HDW PRESS, Step 2 RNO.

e Standard Personal Safety Equipment e AURA

e. Potential overhead contamination Page 2 of 7

Surry 2004-301 Cross Connect Instrument Air o This task is to be SIMUMTEB. Do NOT allow the operator to manipulate valves or violate the containment integrity beundaiy.

There is potential overhead contamination in the Aux Bldg basement clean floor areas, DO NOT touch overhead piping.

e Task critical elements are denoted by an asterisk (*I. If substeps of a critical element also have an asterisk v),

then only those asterisked substeps are critical to performance of that task element.

e Critical step sequencing requirements: 1 4 5 (4 8 5 any order).

a STARTTIME:

"STEP 1:

OBTAIN ZONE 5 ADMIN KEY SAT STANDARD: UNSAT Obtains Zone 5 Admin key.

EVALUATOR'S NOTE:

• • Thisstep is sequence critical.**

When operator demonstrates ability to obtain key, simulate having the key (do not actually remove key from the MCR ANNEX).

STEP 2:

LOCATE 1-1A-446 AND 1-18-447. SAT STANDARD: UNSAT Proceeds to the Unit 1 side of Aux Bldg bsmt penetration area and locates these valves (in overhead).

COBVIMENTS:

Page 3 of 7

Surry 2004-301 Cross Connect Instrument Air REMOVE CHAIN FROM 1-IA-446 AND 1-IA-447. SAT UNSAT Unlocks & removes leck and chain from Unit 1 cross-connect valves.

EVALUATORS NOTE:

• • Thisstep is sequence critical. **

Following simulated chain removal, inform Applicant that chains are removed.

COMMENTS:

SAT UNSAT Opens valve by turning handwheel counterslockwise.

EVALUATORS NOTE:

• • This step is sequence critical.**

• STEP 5:

OPEN 1-lA-447. SAT STANDARD: UNSAT Opens valve by turning handwheel counter-clockwise.

CUE:

When the second valve is being throttled open, notify performer that air flow is heard through the valve.

EVALUATORS NOTE:

• • This step is sequence critical.**

COMMENTS:

Page 4 of 7

2MM-381 Cross Coflnecl Instrument Air STEP 6:

REPORT PO NUCLEAR SHIFT MANAGER (EVALUATOR).

STANDARD:

Verbal status report made of task completion.

STOP TIME:

COMMENTS:

Page 5 of 7

Surry 2004-304 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

. The task will be simulated in the olant.

Cross-connect turbine building instrument air to containment.

The evaluator will explain the initial conditions of the task to be performed. The evaluator will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task. This task is to be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

.. Unit 1 is experiencing a loss of Ctmt IA pressure.

ARP 1B-F6, CTMT INST AIR LO HDW PRESS, has annunciated.

Unit 1 is experiencing a loss of Ctmt IA pressure.

Perform ARP 1B-R, Step 1 and 2 RNO to manually align valves.

Whm you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

I%&

The task will be simulated in the plant.

Cross-connect turbine building instrument air to containment.

or will explain the initial conditions of the task to be performed. The evaluator will provide the initiating cue. Ensure you indicate to the evaluator when yuu understand your assigned task. This task is to be SIMULATED. DQNOT turn switches, manipulate controls or repusition valves.

. Unit 1 is experiencing a loss of Ctmt IA pressure.

AWP 1BF6, CTMT BNST AIR LO HDR PRESS, has annunciated.

.. Unit 1 is experiencing a loss of Ctmt IA pressure.

Perform ARP 1B - R 3Step 1 and 2 RNO to manually align valves.

When you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 Cross Tie Unit 2 Buses S-TIE UNIT 2 EMERGENCY BUSES FOR GW ISOLATION.

RO/SRQ 056AAl.02 (4.013.9) 062A2.12(3.Z3.6) 062A82.02(2.9B.6) 076A2.01(333.7)

S U ~ JPM V L835-02 1-ECA-0.0,Loss of All AC Power, Attachment 3, Rev. 21.

Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 11

Surry 2004-301 Cross Tie Unit 2 Buses Task is to be SIMULATED in the plant.

A simulated loss of all on-site and off-site power (station blackout) is in progress on h i t 1. Unit 2 has the 2H emergency bus energized. 4 -ECA-0.0 is in progress and at step 10 for actions to conserve canal level. The Unit 1 CW MOVs are still open (MBV-CW-IOOA, 106B, 40OC, 408D).

1-ECA-O.O, Attachment 3.

Q.Q, Loss of All AC, Attachment 3 perform Parts 1 & 2 to cross-tie the Unit 2 emergency buses for

. Circ Water isolation.

When you finish the actions necessary to accomplish this, please inform me.

-ECA-O.O, attachment 3, part 2, step 6.

Breaker racking tool 1-ECA-Q.Q,Loss of All AC Power, Attachment 3.

e Standard Personal Safety Equipment Page 2 of 11

SlIrry 2004-301 Gross Tie Unit 2 Buses e This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition valves.

e Task critical elements are denoted by an asterisk (*). If substeps of a critical element also have an asterisk (+I, then only those asterisked substeps are criticat to performance of that task element.

e Critical step sequencing requirements: 1 through 13 (any order) before 14.

D STARTTIME:

STEP I :

-0CKOUT EQUIPMENT. SAT STANDARD: UNSAT Jlacesthe following controls in the PTL OF LOCKOUT position:

a)

• 1-VS-F58A, b)

• 2-W-P-3B, c)

• 2-CH-P-1C (Alternate supply),

d)

• 2-CH-P-1B, e)

• Unit 2 PWZR heater group A, f )

• 2-CS-P-1B, g)

• 2-WS-P-2Bx h) + 2-RS-P-1B, i) 2-SI-P-1B, j)

• 2-VS-F-1B, k)

• 25J3 (#3 EDG supply to Unit a),

I)

• Bus tie (25H1),

m)

• f 5J3 (163ED6 supply to Unit 1).

CUES:

If asked: 1-VS-F-58A is powered from Unit 1 1 Bus EVALUATORS NOTE:

• • This step is sequence critical.**

COUMEIWS:

Page 3 of 11

Surry 2004-301 Cross Tie Unit 2 Buses STEP 2:

LOCALLY VERIFY THE "B"CONTAINMENT SPRAY PUMP BREAKER OPEN. -- SAP STANDARD: - - UNSAT Proceeds to 48Ov breaker 268-5 and verifies breaker indicates OPEN by obsewing the breaker mechanical indicating flag.

CUES:

If asked: Breaker mechanical indicator Rag shows OPEN.

COMMENTS:

STEP 3:

LOCALLY VERIFY THE "B" REClRC SPRAY PUMP BREAKER OPEN. SAT STANDARD: UNSAT Proceeds to 480v breaker 24J-4and verifies breaker indicates OPEN by observing the breaker mechanical indicating flag.

CUES:

If asked: Breaker mechanical indicator flag shows OPEN.

COMMENTS:

• STEP 4:

LOCALLY OPEN THE SUPPLY BREAKER FOR MCC 2J1-2. SAT STANDARD: UNSAT Proceeds to 480v breaker 24J1-4 (behind Unit 2 EHC control cabinets) and opens the breaker by depressing the breaker TRIP pushbutton.

CUES:

If asked: Breaker mechanical indicator flag shows CLOSED before trip.

Tell operator: (When breaker trip button pressed), a "bang" breaker operating noise is heard.

If asked: Breaker mechanical indicator flag shows OPEN following trip.

EVALUATOR'S NOTE:

• • This step is sequence crifical. **

COMMENTS:

Page 4 of 11

Surry 2004-301 Cross Tie Unit 2 Buses STEP 5:

LOCALLY VERIFY THE "B"AUXILIARY FEEDWATER PUMP BREAKER OPEN. SAT STANDARD: UNSAT Proceeds to 416Ov breaker 25J4 and verifies breaker indicates OPEN by observing the breakei indicating lights and/or breaker mechanical indicator flag.

CUES:

If asked: Breaker mechanical indicator flag shows OPEN.

If asked: Breaker indicating lights show green light lit & red light off.

COMMENTS:

STEP 6:

LOCALLY VERIFY 2J BUS STUB BUS SEPARATED. SAT STANDARD: UNSAT Proceeds to Unit 2 mergency Switchgear Room 476Ov breaker 25J9 and verifies breaker indicates OPEN by observing breaker indicating lights and/or breaker mechanical imficator flag.

CUES:

tf asked: Breaker mechanical indicator flag shows OPEN.

If asked: Breaker indicating lights show green and amber lights lit and red light off.

COMMENTS:

STEP 7:

LOCALLY OPEN ALL BREAKERS ON MCC 2JI-1. SAT STANDARD: UNSAT a) Proceeds to MCC 2J1-1 (beside double doors exiting to #I TB).

b) Records on attachment 4 , all breakers found open or tagged-open on MCC 23-1.

c)

• Opens a11 other breakers on the MCC by turning handles to the OFF psition.

EWLUATQR'S NOTE:

• • This step is sequence critical.**

COMMENTS:

Page 5 of 11

Sur9 2004-301 Cross Pie Unit 2 Buses

• STEP 8:

LOCALLY CLOSE UNIT 2 SUPPLY TO MCC 1Jl-1A (#3 EDG AUTOMATIC BUS TRANSFER SAT DEVICE SUPPLY BREAKER).

UNSAT STANDARD:

At MCC 2J1-1, closes #3 EDG ABT supply breaker, ZJI-l-LtC, by rotating handle to the ON position.

EVALUATORS NOTE:

• • This step is sequence critical.**

COMMENTS:

STEP 9:

LOCALLY VERIFY FUSES INSTALLED IN CROSSTIE BREAKER. SAT STANDARD: UNSAT Proceeds to 41WV breaker 25H1 and perfoms the following:

a) Verifies the breaker control power fuses are installed.

b) Verifies breaker trip fuses are installed in fuse socket.

CUES:

If asked: Trip and control fuses are already installed properly in fuse sockets.

COMMENTS:

STEP 10:

LOCALLY VERIFY CHARGING SPRING TOGGLE SWITCH ON. SAT STANDARD: UNSAT Observes bottom area of breaker to verify the breaker charging spring toggle switch is in the ON position.

CUES:

If asked: Breaker charging spring toggle switch is ON.

CQMMENTS:

Page 6 of 11

Surry 2004-401 Cross Tie Unit 2 Buses

• STEP 11:

LOCALLY RACK-IN THE EMERGENCY BUS CWOSS-TIE BREAKER.

STANDARD:

a) Checks breaker racked to the DISCONNECT position by opening breaker door and observing mechanical position indicator inside cubicle.

b) Closes breaker door.

c)

• Obtains breaker racking tool from storage hanger.

d)

• Inserts breaker racking tool into racking mechanism.

e)

• Racks breaker to the CONNECT position by turning racking tool in the clockwise direction.

f) Removes breaker racking tool from racking mechanism.

CUES:

If asked: Breaker initially racked to DISCONNECT position.

If asked: No green tags seen;no ground straps installed.

If asked: SS approval for RED tag removal granted.

If asked: When breaker correctly racked, it is in CONNECT position EVALUATORS NOTE:

• • This 5tep is sequence critical.**

COMMENTS:

STEP 12:

INFORM UNIT 2 OPERATOR OF CRBSS-CONNECT OF 2H & 2J EMERGENCY BUSES. _- SAT STANDARD: UNSAT a) Returns to MCR.

b) Informs Unit 2 operator that next action that will cross-connect the 2H and 2J emergency buses.

COMMENTS:

Page 7 of 11

Surry 2004-301 Cross Tie Unit 2 Buses

• STEP 13:

CLOSE EMERGENCY BUS CRQSS-TIE BREAKER. 25H1. SAT STANDARD: UNSAT a) + Removes 25H1 breaker control switch from PTL.

b)

• Places 25H1 breaker control switch to the CLOSED position.

6) Verifies breaker closes (red light lit).

d) Checks voltage indicated on 2J bus voltmeter.

CUES:

If asked: Initial indication is green light on & red off.

If asked: After closure, red light is on and green off.

Ifasked: 2H & 2J bus voltages indicate 4200 volts.

If local closure attempted using breaker close lever TELL operator: Breaker operating noise heard; it initially indicated red light lit; then breaker operstlng noise heard again and breaker indication shows green light lit.

If local closure attempted using local control switch TELL operator: the green light is lit end the local indicator indicates open.

EVALUATORS NOTE:

• • This step is sequence critkai.**

COMMENTS:

STEP 14:

VERIFY CLOSURE OF UNIT 1 CIRCULATING WATER MOVs. SAT STANDARD: UNSAT Prmeeds to Unit I benchboard 1-1 CW section and verifies cbsed indication (green light lit) for the following MOVs:

e 1-CW-MOV-IWA, e 1-CW-MQV-I06B, e 1-CW-MOV-1OOC, e 1-CW-MOV-l06D.

CUES:

If asked: Green lights on & red off for all above listed MOVs.

COMMENTS:

Page 8 of 11

Surry 2004-381 Cross Tie Unit 2 Buses STEP 15:

REPORT TO NUCLEAR SHIFT MANAGER (EVALUATOR). SAT STANDARD: LBNSAT Verbal status report made that CW MOVs closed.

STOP TIME:

COMMENTS:

Page 9 of 11

2004-301 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

IaSk e Task is to be simulated in the plant.

a Cross-Tie Unit 2 Emergency Buses For CW Isolation The evaluator will explain the initial conditions of the task to be performed. The evaluator will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task. This task is to be SIMULATED. Bo NOT turn switches, manipulate controls or reposition valves.

ss of a11 on-site and off-site power (station blackout) is in progress on Unit 1. Unit 2 has the 2H emergency bus energized. 1-ECA-0.0 is in progress and at step 10 for actions to consewe canal level. The Unit 1 CVV MOVs are still open (MOV-CW-100A, 106B,10Q@,106D).

D Using ECA-0.0, Loss of All AC, Attachment 3 perform Parts 1 & 2 to cross-tie the Unit 2 emergency buses for Circ Water isolation.

D When you finish the actions necessary to accomplish this, piease inform me.

2004-301 Operator Directions Handout Up0 BE GIVEN TO APPLICANT)

Iask m Task is to be simulated in the plant.

0 Cross-Pie Unit 2 Emergency Buses For CW Isolation The evaluator will explain the initial conditions of the task to be performed. The evaluator will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task. This task is lo be SIMULATED. Do NOT turn switches, manipulate controls or reposition valves.

ss of all on-site and off-site power (station blackout) is in progress on Unit 1 . Unit 2 has the 2H emergency bus energized. 1-ECA-O.O is in progress and at step 10 for actions to conserve canal Bevel. The Unit 4 CW MOVs are still apen (MOV-CW-ICOA, I E B , f OW,10BD).

e Using ECA-0.0, Loss of All AC, Attachment 3 perfern Parts 1 & 2 to cross-tie the Unit 2 emergency buses for Circ Water isolation.

m When you finish the actions necessary to accomplish this, please inform me.

Sur9 2004-301 Local Emergency Boration DSls LOCALLY EMERGENCY BORATE

&imalmm 10 Minutes Sur9 4PM LO44 -01B 2-AP-3.00, Emergency Boration, Rev. 1 Performance Rating: SAT: UNSAT:

Examiner: -

NAME SIGNATURE DATE COMMENTS:

Page 1 of 7

Surry 2004-301 Local Emergency Boration to be SIMULATED in the plant.

A simulated unit startup is in progress when a condition requiring emergency boration occurred.

smdauls D 2-CH-228 locally opened BAW 2-AP-3.00 step l b RNO.

te emergency boration in accordance with 2-AP-3.00, Emergency Baration, Step 1b RNO.

When you finish the actions necessary to accomplish this, please inform me.

2-CH-228 locally opened.

Standard Personal Safety Equipment ALARA a DO NOT enter contaminated areas.

Page 2 of 7

Surry 2004-301 Local Emergency bration

. This task is to be SIMULATED. Do NOT allow the operator to manipulate controls, operate switches or reposition

. valves. DO NOT allow the operator to enter a contaminated area for the simulation of this JPM.

Task critical elements are denoted by an asterisk ("). If substeps of a critical element also have an asterisk PI, then only those asterisked substeps are critical to performance of that task element.

Critical step sequencing requirements: None.

e STARTTIME:

STEP 1:

LOCATES 2-CH-MOV-2350. SAT STANDARD: UNSAT a) Proceeds to Aux building 13 ft level boric acid flats.

b) Locates MOV on EAST end of the BA Rats area.

EVALUATOR'S NOTE:

If valve is in Contaminated area, pointing out w/ flashlight is acceptable.

COMMENTS:

STEP 2:

LOCALLY ATTEMPTS TO OPENS 2-CW-MOV-2350. SAT STANDARD: UNSAT a) Attempts lo engage 2-CH-MOV-2350 manual operator by depressing clutch mechanism.

b) Attempts to open valve by rotating MOV handwheel in the counter-clockwise direction.

CUES:

Tell operator: The MOV handwheel will not turn or move in the counter-clockwise direction (regardless of how much opening pressure is applied).

Ifasked: Valve stem rod does not move.

If asked: No flow noise heard through valve.

If asked: Ne change in either the audible BATP operating noise or BATP discharge pressure.

If asked: The MOV handwheel will move in the clockwise direction approximately one-quarter turn.

COMMENTS:

Page 3 of 7

Surry 2004-30 1 Local Emergency Boration STEP 3:

REPORT TO SHIFT suFmvisaa (EVALUATOR) THAT MQV NOT OPERATING.

STANDARD:

a) Contacts Shift Supervisor (Evaluator).

b) Informs him that CH-MOV-2350 will not locally operate (appears to be jammed or frozen-up).

CUES:

If applicant asked if 2-CH-228 should be locally opened, ask the applicant for a recommendation.

COMMENTS:

STVEP 4:

LOCALLY OPENS 2-CH-228, MANUAL &ORATION VALVE. SAT STANDARD: UNSAT a) Operator requests the WO to Manually open 1-CH-FCV-2113A.

b) Locates 2-CH-228 on EAST wall of BA flats area.

c)

• Opens 2-CH-228 by turning valve handwheel in the counter-clockwise direction.

CUES:

Tell operator: When operator attempts to open CH-228, teil him that the handwheel turns in the counter-clockwise direction.

tf asked: The valve stem rises as valve is opened.

EVALUATORSNOTE:

2-CH-228 is a small grinnetl valve on the EAST wall area of the RA flats in the BA piping.

If valve is in Contaminated area, pointing out w/ flashlight is acceptable.

If asked: The RO has manually opened 2-CH-FCV-21138.

COMMENTS:

STEP 5:

REPORT TO SHIFT SUPERVISOR (EVALUATOR). SAT STANBARB: UNSAT Reports to Shift Supervisor (Evaluator) that 2-CH-228 is open.

STOP TIME:

COMMENTS:

Page 4 of 7

Page 5 of 7 Surry 2004-304 Operator Directions Handout (TOBE READ TO APPLICANT BY EXAMINER) e Task is to be simulated in the plant.

Local Emergency Boration The evaluator will explain the initial conditions of the task to be performed. The evaluator will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task. This task is to be SIMULATED.

Do NOT turn switches, manipulate controls or reposition valves.

There is a challenge to unit 2's Shutdown Margin in progress.

A simulated unit startup is in progress when a condition requiring emergency boration occurred.

Emergency boration was attempted from the Contro! Room, but the MOV thermalled before it opened.

Local& initiate emergency boration in accordance with 2-AP-3.00, Emergency Boration, Step 1b RNO.

a When you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Iash e Task is to be simulated in the plant.

e Local Emergency bration The evaluator will explain the initial conditions of the task to be performed. The evaluator will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task. This task is to be SIMULATED.

Do NOT turn switches, manipulate controls or reposition valves.

e There is a challenge to unit 2's Shutdown Margin in progress.

A simulated unit startup is in progress when a condition requiring emergency boration occurred.

Emergency boration was attempted from the Control Room, but the MQV thermalled before it opened.

Locally initiate emergency boration in accordance with 2-AP-3.00, Emergency Boration, Step I b RNO.

E When you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 Fuel Handling Abnormal Conditions Iask 0-AP-22.00, FUEL HANDLING ABNORMAL CONDITIONS IMMEDIATE ACTIONS RO/SRO 5 Minutes 0M.M~Ol (3.6M.4) 036.AK1.01 (334.1)

J3&wxe§ Surry JPM LO36-04 0-WM-B3, 1-RM-RI-l53 High Annunciator Response Procedure, Rev. 4.

0-AP-22.60, Fuel Handling Abnormal Conditions, Rev. 18 Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DAT COMMENTS:

Page 1 of 6

Surry 2084-301 Fuel Handling Abnormal Conditions to be PERFORMED in the simulator.

Unit 1 is operating at 100% power, Unit 2 is at CSD for refueling.

2.00, Fuel Handling Abnormal Conditions, Steps 6 and 7 completed.

. There has been a Fuel Handling accident in the Fuel Building. The Fuel handling crew has placed the leaking fuel assembly in a safe condition and evacuated the Fuel Building. No fuel repair was or is in progress.

e You are to perform the Bast two Immediate Action Steps of Q-AP-22.80,Fuel Handling Abnormal Conditions, without the use of the procedure. (Secure Normal MCR Ventilation and Bump MCR Bottled Air) e When you finish the actions necessary to accomplish this, please inform me.

8-AP-22.00, Fuel Handling Abnormal Conditions, Steps 6 and 7 completed.

I Response Procedure.

0 Standard Personal Safety Equipment e ALARA

. Gail up 100% IC and initialize.

Place the Fuel Building on Filtered Exhaust (VS-F-58A and B)using 0-QP-VS-014. The MCR is on normal ventilation.

Enter malfunctions for Fuel Bldg Bridge Crane, New Fuel Area, and Vent-Vent RMs so that Alert and High Alarms are lit.

e Override OFF annunciator VSP-C-1 e Start the air compressor for simulating air pressure to the MCR and close the door from the simuiator booth to the simulator. The door must be closed in order to have positive air pressure indicated in the simulator.

Place the simulator in freeze until JPM Performance.

Page 2 of 6

Surry 2004-301 Fuel Handling Abnormal Conditions Task critical elements are denoted by an asterisk (*). If substeps of a critical element also have an asterisk r)r then only those asterisked substeps are critical to performance of that task element.

Critical step sequeflcing requirements: None.

0 STARTTIME:

"STEP 1:

SECURE NORMAL MAIN CONTROL ROOM VENTILATION (0-A&-22.00, Step 6 ) SAT STANDARD: UNSAT a)

• Close 1-VS-MOB-l03C.

b) Verify closed: Green Light lit and Red tight not lit.

c)

• Close 1-VS-MOD-l03D.

d) Verify closed: Green Light lit and Red bight not lit.

e) Verifies MCR Exhaust Fan 1-VS-F-15 is secured (Green Light lit, Red bight not lit).

f) Verifies MCR Supply Fan 1-VS-AC-4 is secured (Green Light fit, Red Light not lit).

COMMENTS:

"STEP 2:

BUMP MCR BOTTLED AIR (0-WP-22.00, Step 7) SAT STANDARD: UNSAT a) Applicant attempts to close 4-VS-MOD1038 (dumps Unit 1 Cable Vault air bottles).

Valve does not close and RNO must be performed. Valve red light on handswitch still lit.

b)

• RNO: Closes 4 -VS-l03A (Dumps MEW 3 air bottles).

COMMENTS:

STEP 3:

REPORTS TO SHIFT SUPERVISOR (EVALUATOR) THAT TASK IS COMPLETE. SAT STANDARD: UNSAT a) Reports to SS that Steps 6 and 7 of AP-22.00 have been completed and the WNO for Step 7 was utilized.

COMMENTS:

Page 3 of 6

2004-301 Fuel Handling Abnormal Conditions Page 4 of 6

Surry 2004-301 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

IadS e Task is to be performed in the simulator.

e Perform 0-A$-22.00, Fuel Handling Abnormal Conditions, Immediate Action Steps.

The evaluator wilI explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understandyour assigned task.

Unit 1 is operating at 100% power, Unit 2 is at CSD for refueling.

There has been a Fuel Handling accident in the Fuel Building. The Fuel handling crew has placed the leaking fuel assembly in a safe condition and evacuated the Fuel Building. No fuel repair was. or is, in progress.

a You are to perform the last two hrnediate Action Steps of 0-AP-22.00, Fuel Handling Abnormal Conditions, without the use of the procedure. (Secure Normal MCW Ventilation and Dump MCR Rottled Air)

When you finish the actions necessaty to accomplish this, please inform me.

2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT) rn Task is to be performed in the simulator.

e Perform Q-AP-22.80, Fuel Handling Abnormal Conditions, Immediate Action Steps.

The evaluator will exolain the initial conditions of the task to be oerformed and will Drovide the initiatina cue. Ensure you indicate to the eialuator when you understand your assignedtask.

e Unit 1 is operating at 100% power, Unit 2 is at CSD for refueling.

e There has been a Fuel Handling accident in the Fuel Building. The Fuel handling crew has placed the leaking fuel assembly in a safe condition and evacuated the Fuel Building. No fuel repair was, or is, in progress.

e You are to perform the last two Immediate Action Steps ot 0-A$-22.00, Fuel Handiing Abnormal Conditions, without the use of the procedure. (Secure Normal MCR Ventilation and Dump MCR Bottled Air) e When you finish the actions necessary to accomplish this, please inform me.

Surry 2804-301 Transfer FRV Byp to FRV TRANSFER FEED WATER CONTROL FROM FW BY19 FLOW HCVS TO THE FEED REG FCVS IN MANUAL CONTROL.

10 Minutes 1-GO$-1.5, Unit Startup, 2% Reactor Power to Max Allowable Power, Rev. 32 Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 7

Surry 2004-301 Transfer FRV Byp to FRV o You are the Unit 1 BOP.

o The unit is operating at 2055 power.

Feedwater is being controlled by FW BYF FLOW HCVs for all SG.

All FEED REG FCVs are in MANUAL.

IFeed Water Control from FW BYP FLOW HCVs to the FEED REG FCVs in MANUAL control then place FRVs in AUTO.

Stabilize SG Levels at Program Level.

You are to transfer Feedwater Control from the IW 5YP FLOW HCVs to the FEED REG FCVs in MANUAL per GO$-1.5, Unit Startup 2% Reactor Power to Max Allowable Power, Step 5.3.28 through 5.3.30 for a11 Steam Generators. Than place FEED REG FCVs in AUTO per step 5.3.31.

rogram Level and FEED REG FCVs are in AUTO.

o 1-GOP-l.5, Unit Startup, 2% Reactor Power to Max Allowable Power, Rev. 32 None o Call up 20% power IC Page 2 of 7

Surry 2004-301 Transfer FRV Byp to FRV Task critical elements are denoted by an asterisk (*). If substeps of a critical element also have an asterisk e),

then only those asterisked substeps are critical to performance of that task element.

START TIME:

Step I:

Transfer Wed Water Control from FW BY$ FiOW HCVs to the FEED REG FCVs in §AT MANUAL control. (GOP-1.5, Step 5.3.28)

UNSAT Open 1-W-MOV-l54A, SG A W ISOL..

Open 1-Fw-MOV-1548, SG B W ISOi..

Open I -fW-MOV-l54C, SG C FW ISOh.

Throttle open 1-FW-FCV-1498, SG A FEED REG.

Close I-NV-HCV-l5M, SG A FW BYP FLOW.

Throttle open 1-FW-FCV-1488, SG A FEED REG.

Close 1-FW-HCV-1558,SG B FW BY$ FLOW.

Throttle open I-FW-FCV-5498, SG c FEED REG.

Close f-FW-HCV-l55C, SG C Nv BYP FLOW.

Evaluator'sComments Step 2:

4pplicant determines that MFRVs are not in AUTO and WAS GOP-1.5, Step 5.3.29. SAT Standards ____ UNSAT a) N/As step 5.3.29.

Evaluator's Comments Page 3 of 7

Surry 2004-301 Transfer FWV Byp to FRV step 3:

Verifies feed fDow is indicated on all six channels of SG FEED FLOW PROTECT SAT (GOP-1.5, Step 5.3.30)

UNSAT Standards a) 1-FW-FI-1477,SG A FEEQ FLOW PROTECT b) 4-FW-FI-1476, SG A FEED FLOW PWOTECT C) 1-FW-FI-1489, SG B FEEB FLOW PROTECT d) 4 -FW-FI-1486, SG B FEED FLOW PKOTECT e) 1-FW-FI-1497, SG C FEED FLOW PROTECT f) 1-FW-FI-i496, SG C FEED FLOW PROTECT Evaluator's Note Evaluator's Comments i

5 t e p 4:

When feedwater flow is nearly equal to steam flow AND SG levels are being SAT controlied at the setpoint, THEN place the FEED REG FCVs in AUTO. (GOP-1.5, Step 5.3.31) UNSAT Standards a} When feed flow and steam flow are approximately equal for the A SG, then 1-RN-FCV-1478 IS placed in AUTO.

b} When feed flow and steam flow are approximately equal for the B SG then 1-%W-FCV-1488 is placed in AUTO.

c) When feed flow and steam flow are approximately equal for the C SG, then 1-FW-FCV-1498is placed in AUTO.

Evaluator's Comments Step 5:

Reports t~ the Shift Manager that MFRVs are controlling feedwater flow in AUTO to -

I SAT all three SGs.

--UNSAT Standards a) Reports that MFRVs are controlling feedwater flow in AUTO to all three SGS.

Step Time:

Evaluator's Comments Page 4 of 9

2004-301 Transfer FRV Byp to FRV Page 5 of 7

Surry 2004-301 operator Directions Handout (TO BE READ TO APPLEANT BY EXAMINER) m e Task is to be performed in the simulator.

e Transfer Feedwater Control from the t=W BYP FLOW HCVa to the FEED REG FCVs The evaluator will exthin the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your aslgnedtask.

e You are the Unit 1 BOP.

e The unit is operating at 20% power.

e Feedwater is being controlled by FW BYP FLOW HCVs for all SG.

e All FEED REG FGVs are in MANUAL.

You are to transfer Feedwater Control from the I=W BVP FLOW HCVs to the FEED REG FCVs in MANUAL per GOP-1.5, Unit Startup 2% Reactor Power to Max Allowable Power, Step 5.3.28 through 5.3.30 for all Steam Generators. Then place FEED REG FCVs in AUTO per step 5.3.31.

2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT) o Task is to be performed in the simulator.

Transfer Feedwater Control from the FW BYP FLOW HCVs to the FEED REG FCVs The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

e You are the Unit 1 BOP.

o The unit is operating at 2096 power.

e Feedwater is being controlled by W 5YP FLOW HCVs for ail SG.

o All FEED REG FCVs are in MANUAL.

You are to transfer Feedwater Control from the W BY$ FLOW HCVs to the FEED REG FCVs in MANUAL per GOP-1.5, Unit Startup 2% Reactor Power to Max Allowable Power, Step 5.3.28 through 5.3.30 for all Steam Generators. Then place FEED REG FCVs in AUTQ pes step 5.3.31.

Surry 2004-301 Start Second RCP Iask START THE B RCP 20 Minutes 015Ml.23(3.5/3.2)

EldwmaS 1 -0P-RC-001, Starting And Running Any Reactor Coolant Pump. Rev. 13 1C-H4, RCP FRAME DANGER, Rev. 2 1C-HS, RCP SHAFT DANGER, Rev. 1 Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE BATE COMMENTS:

Page 1 of 15

Surry 2004-301 Start Second RCP

.. You are the Unit 1 R B and 1 am the Nuclear Shift Manager.

A Unit 1 startup is in progress.

A RCP is operating satisfactorily.

e B:RCP is cwpled 4-QP-RC-001, Section 5.1 has been completed a Unit 2 is shutdown with no RCPs operating Standards a Starts B WCP Secures B RCP due to High Vibrations ccordance with 1-OQ-RC-001, Starting and Running Any Reactor Coolant Pump, Section 5.3.

9 B WCP is secured due to high vibrations.

QP-RC-001, Starting and Running Any Reactor Coolant Pump, Rev. 13 e 1C-H4, RCP FRAME DANGER, Rev. 2 a 1C-H5, RCP SHAFT DANGER, Rev. 1 None e Call up R% power IC Page 2 of 15

Surry 2004-301 Start Second RCP 6 Task critical elements are denoted by an asterisk p). If substeps of a critical element also have an asterisk p),

then only those asteriaked substeps are critical to performance of that task element.

6 Critical step sequencing requirements: Step 16 prior to Step 32.

START TIME:

Step 1:

Obtains correct procedure and verifies correct revision. SAT Standards LSNSAT Applicant obtains procedure and verifies the correct revision.

Examiner's Cue After the appiicant explains how to obtain a copy of the procedure, then provide a copy of the procedure.

Evaluator's Cornmerats Step 2:

Reviews 1 -OP-RC-001Initial Conditions and Precautions and Limitations. SAT

$kWIdaKdS UNSAT a) Reviews 1-OB-RC-001, Section3.0.

b) Reviews 1-OB-RC-001, Section 4.0.

Evaluator's Comments Step 3:

Verifies Subsection 5.1 completed (1-OP-RC-001,Step 5.3.1) SAT Standards llNSAf Check initiating cues and determines that Subsection 5.1 has been completed.

Examiner's Cue If applicant asks if Subsection 5.1 is completed: Have applicant check initiating cues.

Evalua%or'sComments Page 3 of 15

Sur9 2004-301 Start Second RCP 1

I Step 4:

Rack Breaker 15B3, 1-RC-P-1B, to TEST (1-OP-RC-001, Step 5.3.2). SAT Standards UNSAT Calls field operator to rack 1583 to TEST.

Evaluator'sComments Step 5:

Verify 1-RC-MOV-1593, LOOP B COLD LEG ISOL, and 1-RC-MOV-1592, LOOP B SAT HOT LEG ISOL, are open (? -0P-RC-001, Step 5.3.3).

UNSAT Standards 1-RC-MOV-1593 and 1592 Red Breaker Indication illuminated.

Evaluator's Comments Step 6:

Verify l-CH-FI-l127A, WCP B SEAL WTR IMJ FLOW, is greater than 6.5 gpm and SAT less than 13 gpm (4-OP-RC-001, Step 5.3.4).

UMSAT Standards I-CH-FI-1727A indicates between 6.5 and 13 gpm.

Evaluator's Comments Step a:

Verify 1-CH-PI-I 1 19, VCT Press, is greater than or equal to 15 psig (1-0P-RC-001, Step 5.3.5).

Standards 1-CH-PI-1117is greater than 15 psig.

Evaluator's Comments Page 4 of 45

Surry 2004-301 Start Second RCP Step 8:

Verify RCP No. 1 Seal Delta P is greater than or equal to 200 psid for 7 -GH-PI-l155A, SAT RCP B No. 1 SEAL Delta P (7 -0P-RC-OO1, Step 5.3.6).

UNSAT Standards Verify 1-CH-PI-1f55A indicates greater than 200 psid.

Evaluator'sComments Step 9:

Verify Open or Open 1-CH-19038, RCP 1B SEAL LEAKOFF ISOL VV (1-OP-RC- SAT 001, Step 5.3.7).

UNSAT Standards Ensure Red Indicating Light illuminated for 1-CH-1303B.

Evaluator's Comments Step 10:

Vesify that No. 1 seal leakoff is within the NORMAL OPERATING RANGE for 1-CH- SAT PI-1155A, WCP B NO.1 SEAL &Ita P (I-OP-RC-BO1, Step 5.3.8).

UNSAT Standards Determines leak off within normal operating range using Attachment 7.

Evaluator's Comments step 1a :

Verify Component Cooling flow has been established to the following: SAT Thermal Barrier, Lube Oil Coolers, and Stator Cooler (1-0P-RC-001, Step 5.3.9)

UNSAT Standards Verify CCW flow to Thermal Barrier, Lube Oil Coolers, and Stator Cooler.

Evaluator's Comments Page 5 of 15

Surry 2004-301 Start Second RCP Step 12:

Verify the overcurrent and speed sensing start permissives for WCP 1B are clear IAW SAT (1-0Q-RC-001,Step 5.3.10).

UNSAT Standards AI! lights specified in Attachment 2 are verified per the attachment. All are lit excepl for Pro Star Motor Protestion System LEDs.

EvaluatoPs Comments step 13:

Acknowledge Note prior to Step 5.3.11 SAT Standards UNSAT If 1K-D4 is in alarm. then determine cause.

Evaluator's Comments step 14:

Verify common RCP annunciators are clear (1-OP-RC-001, Step 5.3.1 1). SAT Standards UNSAT Verify Clear:

a) 1C-B2, WCP THERMAL BARRIER RETURN HDR HI FLOW is) lC-E2, SEAL WTW INJ FILTER HI Delta PRESS C) 1C-F2, WCP BEARING HI TEMP el) 1K-D4,4KV BKR AUTO TRIP Evaluator's Comments Page 6 of 15

Surry 2004-301 Start Second RCP Step 15 Verify RCP 1B alarms are clear (1-OP-RC-001, Step 5.3.12). SAT Standards UNSAT Verify Clear:

a) 1 B-E7, WCP 1B OIL RSVR HI-LO LEVEL b) 1 BE8, RCP I B VAPOR SEAL TK LO LVL C) 1C-61, WCP 1B CC RETURN LQ FLOW d) 1C-62, RCP t B THERMAL BARRIER CC HI FLOW e) 1C-B3, RCP 1B THERMAL BARRIEfl CC HI TEMP 9 1C-54,RCP f B SEAL LEAKOFF HI FLOW g) 1C-M, RCP 1B SEAL WTR RTUWN LO DELTA PRESS h) lC-EI, RCP 1B CC RETURN HI TEMP i) 1C-E3, RCP 1B SHAFT SEAL WTR LO INJ FLOW j) 1 C-E4, WCP 18 SEAL LEAKOFF LO FLOW Evaluators Comments Step 16 Start the associated Bearing Lift Pump and record start time (1-OP-RC-001, Step SAT 5.3.43).

UNSAT Bearing Lift Pump for WCP 4 5 started and time recorded.

Evaluators Comments CP Bearing bifl Pump has been running for greater than 2 minutes (1-OP-RC- -- SAT UNSAT Two minutes have elapsed since starting the Bearing Lift Pump.

Evaluators Commends Step 18 Verify proper Bearing Lift Pump discharge pressure (1-OP-RC-001~ Step 5.3.15). SAT Standards UNSAT White oil pressure light is LIT for 1-RC-P-lB.

Evaluators Comments

Surry 2004-301 Start Second RCP Step 19 Verify RCP start logic is established. (1-OP-WC-001,Step 5.3.16) SAT UNSAT Standards Place control switch to START and verify breaker 15B3 closes Evaluators Comments Step 20 Place control switch for RCP 1B in PTL. (I-OP-RC-001, Step 5.3.17) SAT Standards UNSAT RCP 1B is placed to PTL..

Evaluators Comments

• step 21 Rack breaker 1583, I-RC-P-1 B to CONNECT (1-OP-RC-001, Step 5.3.18). SAT Standards UNSAT Instructs field operator to place 1583 to CONNECT.

Evaluators Comments step 22 Acknowledges CAUTION prior to step 5.3.19. SAT Standards UNSAT Acknowledges caution.

Examiners Cue If asked about Unit 2 Station Service supply: state that the Unit 2 Station Sewice is being supplied by Reserve Station Service Transformers.

Evaluators Comments Page 8 of 15

Surty 2004-301 Star? Second RCP Step 23 Determine required position for Load Shed Mode Select Switch (1-OP-RC-QB1,Step SAT 5.3.19).

_ I-UNSAT Standards Chooses the DISABLE position due to all Unit 2 RCPs secured.

Examiners Cue If applicant asks if Unit 2 RCPs are running: Have applicant check initiating cues.

Evaluators Comments Step 24 Determines Step 5.3.20is ~ oapplicable.

t SAT Standards UNSAT Appkant does not perfom Step 5.3.20.

Evaluators Comments Step 25 Place Load Shed Mode Selector in required position (1-QP-RC-OQl~ Step 5.3.21 ). SAT Standards UNSAT Places switch in DISABLE position.

Evaluators Comments Step 26 Select and monitor RCP temperatures on the PCS using CRT or Digital Trend block SAT (1-OQ-RC-001,Step 5.3.22).

~. UNSAT Standards Monitors RCP temperatures using PCS.

Evaluators Comments Page 9 of 15

Surry 2004-301 Start Second RCP step 27 Verify an Emergency Diesel Generator is not connected tQ the grid(1-OP-RC-001, SAT Step 5.3.23) .

- UNSAP Standards All Diesel Output Breakers have Green Breaker Indication illuminated.

Evaluators Comments step 28 Acknowledge CAUTION prior to Step 5.3.24. SAT Standards: UNSAT This caution does not apply.

Evaluators Comments step 29 Acknowledge Step 5.3.24 does not apply. SAT Standards: UNSAT This step does not apply.

Evaluators Comments Step 30 Verify personnel are clear of pump (1-0P-WC-001,Step 53.25). SAT Standards: UNSAT Makes plant announcement or dispatches operator to make the verification.

Evaiuators Comments step 31 Acknowledge CAUTION prior to Step 5.3.26. SAT Standards: UNSAT Acknowledges caution.

Evaluators Comments Page 10 of 45

Surry 2004-301 Start Second RCP

• step 32 Start 1-RC-P-IB (1-OP-WC-001, Step 5.3.26) -~

SAT Standards: UNSAK Starts 5 -WC-P-l B.

Note Input High Vibration 30 seconds after 1-RC-P-1Bstart.

Evaluators Comments step 33 Record No. 1 Seal Leak Off Flow (1-OP-RC-001,Step 5.3.27). SAT Standards UNSAT Records flow and verifies that it is acceptable iaw Attachment 1 Evaluators Comments Step 34 Record Parameters (1 -OP-RC-004, Step 5.3.28). SAK Standards UNSAT Records parameters.

Evaluators Comments Step 35 Stop associated Lift Pump (1-0P-RC-001 Step 5.3.29).

Standards Lift Pump is secured.

Evaluators Comments Step 36 4cknowledge 1GH4, WCP FRAME DANGER. SAT Standards UNSAT derifies that RCP 1B is the source of the alarm and vibrations are greater than 5 mils 3n 1-RC-P-I B.

Evaluators Comments Page 11 of 15

Surry 2804-301 Start Second RCP

• Step 37 Secures 1-RC-P-lB per 1C-H4. SAT Standards UNSAT Stops Rep 1B.

Note Applicant may not refer to ARP when securing pump. This is acceptable.

Evaluators Comments step 38 Notifies Shift Manager that RCP 1B was secured. SAT Standards UNSAT Shift Manager was notified that WCP 1E3 was secured.

STOP TIME:

Evaluators Comments Page 52 of 15

Surry 2004-301 Start Second RCP Page 43of 15

2004-301 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

IEik a Task is to be performed in the simulator.

e StartBRCP The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

You are the Unit 1 RO.

m A Unit 1 startup is in progress.

ARCP is operating satisfactorily.

a 83 RCP is coupled 1-OP-Re-001, Section 5.1 has been cmpleted Unit 2 is shutdown with no RCPs operating Start the B RCP in accordance with f -0P-RC-001, Starting and Running Any Reactor Coolant Pump, Section 5.3.

Surry 2004-301 Operator Directions Handout (TOBE GIVEN TO APPLICANT)

E.%&

Task is to be pelformed in the simulator.

StartBRCP The evaluator wi[l explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

You are the Unit 1 RO.

a A Unit 1 startup is in progress.

m ARCP is operating satisfactorily.

m B RCP is Coupled 1-OP-RC-001, Section 5.1 has been completed Unit 2 is shutdQwnwith no RcPs operating Start the B RCP in accordance with 1-OQ-RC-001,Starting and Running Any Reactor Coolant Pump, Section 5.3.

Surry 2004-301 Restore 1H Bus RESTORE OFFSITE POWER TO 1W 4160V EMERGENCY BUS IAW AP-10.88.

13 Minutes 055EA2.06 (3.714.1)

Sursy JPM LO18-06 AP-18.08, Station Power Restoration, Rev. 8 Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 8

Surry 2004-301 Restore 1 H Bus

.. Task is to be PERFORMED in the Simulator.

A loss of #6 34.5 KV Bus power has occurred.

Standards AP-10.08, Station Power Restoration.

. YOUare to restore power to 1H Bus from off-site IAW 0-AP-10.08 (beginning with Step 21) and inform me when

.. #1 EDG may be shut down.

Unit 2 operator will perform all necessary evolutions on Unit 2 when requested.

When you finish the actions necessary to accomplish this, please inform me.

Breaker 15H8, 1 H 4160v Emergency Bus Supply Breaker closed.

m A$-1 0.08, Station Power Restoration.

m a

. Call up IC #1 and initialize.

Place the simulator in run.

From MONITOR, open breaker 15F1 (B15F1 = F).

Place 5 -CC-P-1A control switch in PTL.

0 m From MONITOR, close the stub bus 15H9 (B45H9 = T).

Place the control switches for 1 -SW-P-1OB and 1-CC-P-PB to off and return to auto.

e Stop the A CH pump and place in auto.

0 Once conditions have stabilized then freeze the simulator.

Surry 2004-301 Restore 4 H Bus Bask critical elements are denoted by an asterisk ("). If substeps of a critical element also have an asterisk (*),

then only those asterisked substeps are critical to performance of that task element.

Critical step sequencing requirements: 4i, before 6k; 6f before 6k.

a STARTTIME:

34.5 KV BUS 6 ENERGIZED FROM OFF-SITE POWER. (0-AQ-10.08,Step 21) -- SAT UNSAT a) Acknowledges NOTE that the RAD waste facility is powered from bus 6.

b) Checks C.B. L-202 en switchyard status panel closed by observing the red light on and the green light off.

STEP 2:

VERIFY RSS TRANSFORMER "C" ENERGIZED. (0-AP-10.08, Step 22) SAT STANDARD: UNSAT Checks C.B. 262 on switchyard status panel closed by observing the red light on and the green light off.

COMMENTS:

STEP 3:

CHECK 15F1 OPEN. (0-AP-10.08, Step 23) SAT STANDARD: UNSAT Checks ACB-I 5F1 open by observing green light ON and red light OFF for 15F1.

COMMENTS:

Page 3 of 8

~

Surry 2004-301 Restore 1H Bus STEP 4:

ENERGIZE TRANSFER BUS "F". (0-AP-10.08, Step 24)

STANDARD:

a) Acknowledges caution that load placed on EDG should not exceed 2950 KW.

b) Verifies breaker ACB-15HB open by observing the green light on and the red light off.

c) Verifies breaker ACB-25d8 open by asking Unit 2 operator.

d) Verifies breaker ACB-1SCI open by observing the green light on and the red light off.

e) Verifies breaker ACB-25C1 open by asking Unit 2 operator.

f ) Checks breaker ACB-15C2 shut by observing red light on and green light off.

g) Checks breaker ACB-25C2 shut by asking Unit 2 operator.

h) Resets breaker disagreement on breaker ACB-15F1 by momentarily turning switch to open position and observing amber light goes out.

i)

• Closes breaker ACB-15F1 by taking control switch to close and holding until the red light comes on and the green light goes off end 15 seconds have elapsed.

CUES:

If asked: 2J bus is energized by #3 EDG.

'f asked: ACB-2UEi and ACB-255Cl am open.

f asked: ACB-25C2 is shut.

EVALUATOR'S NOTE:

,*This step is sqquenee cmticai. **

3XWulENTS:

STEP 5:

HECK 4160V BUS 1H ENEKGIZEB FROM EBG 1. (0-AQ-10.08, Step 25) SAT STANIDARD

UNSAT a) Checks 4160 V bus 1H energized by observing voltage on the EDG Panel.

bj Goes to Attachment 8. (0-AQ-10.08, Step 26)

ZOMM ENTS:

Page 4 of 8

~

Surry 2004-301 Restore 1H Bus STEP 6:

DABALLEL 1H BUS TO THE "F"TRANSFER BUS. (0-AQ-10.08, Att. 8) SAT STANDARD: UNSAT a) Turns to AP-10.08, Attachment 8.

b)

• Turns the #I EDG AUTO-EXERCISE switch to EXEBCISE.

c) Acknowledges annunciator C-6-6 (#I EDG auto start disabled).

d)

• Plashes the fast start reset push button.

e) Checks the fast start reset red light is illuminated.

f)

• Notifies auxiliary operator to adjust speed droop from 0 to the scribe mark.

g) *Turns sync switch ACB-15H8 on.

h) Adjusts incoming voltage to within k5 volts of running voltage using VOLT ABJ switch.

i)

• Adjusts ED6 speed untig sync scope is moving slowly in the fast direction using the SPEED ADJ switch.

j) Resets breaker disagreement on breaker ACB-15H8 by momentarily turning switch to the open position and observing amber Bight goes out.

k)

• Closes the ACB-15H8 breaker when the sync scope is between 5 minutes of and 12 o'ciock.

I) Verifies Kilowatts are greater than zero.

m) Using the volt adj switch, maintain reactive 100 - 500 Kilovars out and emerg bus 1H volts between 4000 and 4400 volts.

n) Turns sync switch ACB-15H8 off.

CUES:

relf sprator: After call made to auxiliary operator, inform operator that the speed droop has been set to the scribe mark.

EVALUATOR'S NOTE:

'*This step is sequence critical.**

Simulator timing response to closing the ACB-15H8 breaker is slow. The breaker may not actually close until the sync scope is slightly beyond 42 o'clock.

coMM ENTS:

Page 5 of 8

Surry 2004-301 Restore 1H Bus STEP 7:

REPORT PO NUCLEAR SHIFT MANAGER (EVALUATOR). SAT STANDARD: UNSAT Verbal status report that offsite power has been restored to 1H emergency bus and #1 EDG may be shut down IAW 1-OP-EG-001.

aJJ3 Tell operator: The service building operator will shutdown the #I EDG IAW 1-OP-EG-001.

STOP TIME:

COMMENTS:

Page 6 of 8

Surry 2004-301 Operator Directions Handout (TO BE READ TO APPLICANT 5 Y EXAMINER) c Task is to be performed in the simulator.

Restore Offsite Power To 1H 416OV Emergency Bus IAW AP-lO.O8., Station Power Restoration.

The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue.

Ensure you indicate to the evaluator when you understand your assigned task.

c A loss of ri6 34.5 KV bus power has occurred.

c Unit conditions have stabilized and Bus #6 has been re-energized using a local switching order and power has been restored to the low level intake.

c AP-10.08, Station Power Restoration, Steps 1 through 20 have been completed.

e You are to restore power to 1 H Bus from off-site IAW 0-AP-10.08 (beginning with Step 211 and inform me when

1. I EDG may be shut down.

Unit 2 operator will perfform all necessary evolutions on Unit 2 when requested.

When you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT) e Task is to be performed in the simulator.

a Restore Offsite Power To 1H 4160V Emergency 5us EAW AP-10.08., Station Power Restoration.

The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue.

Ensure you indicate to the evaluator when you understand your assigned task.

A loss of #6 34.5 KV bus power has occurred.

Unit conditions Rave stabilized and Bus #6 has been re-energized using a local switching order and power has been restored to the IQWlevel intake.

AP-10.08, Station Power Restoration, Steps f through 20 have been completed.

e You are to restore power to 1H Bus from off-site IAW 0-AP-10.08 (beginning with Step 211 and inform me when

1. 1 EDG may be shut down.

e Unit 2 operator will perform all necessary evolutions on Unit 2 when requested.

When you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 Remove SR NI From Service Iasln REMOVE A FAILED SOURCE RANGE NI FRQM SERVICE DURING A REACTOR STARTUP.

4 Minutes 075A2.82 (3.1135) 015,4403 (3.8/3.9)

References Surry JPM LO62-02 1-AP-4.00, Nuclear Instrumentation Malfunction, Rev. 18 Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 7

Surry 2004-301 Remove SR NI From Service o Bask is to be PERFORMED in the simulator.

a N-31 has failed low with reactor power at 1.3 x 10. amps during a startup, and the SR high voltage cannot be removed from either N-31 or N-32.

1-AP-4.Q0, Nuclear Instrumentation Malfunction.

During a reactor startup, when P-6 was reached the operator pushed 1/N-33A TR A and 1/N-335 TR B to de-energize the Source Range Nls. However, N-31 failed low instead, and the high voltage was not removed from either detector (PI-31 Of N-32).

a I need you to respond to a failure of both Source Range Nls, IAW 1-AQ-4.00,so the reactor startup can continue.

When you finish the actions necessary lo accomplish this, please inform me.

lear Instrumentation Malfunction, step 18.c completed.

e 1-AQ-4.00, Nuclear Instrumentation Malfunction.

e Call up Reactor Startup IC and initialize.

e Perform the startup to obtain power at -1.2 x ICf amps (or slightly greater), then implement malfunction (MN10101, 1 sec, 58 to B%), N-31 failure in the low direction. Implement switch overrides (SWTRP-BLK-BRA-P5 AND SRTRP._BLK-TRB-PB, ACTIVE), Flux Level Trip Cutout Pushbuttons. Freeze the simulator until ready for operator to perform JPM.

e Do not allow the SUR to be greater than +0.1 dpm.

Page 2 of 7

Surry 2004-301 Remove SR NI From Service Task critical elements are denoted by an asterisk ("). If substeps of a critical element also have an asterisk p),

then only those asterisked substeps are critical to performance of that task element.

e Critical step sequencing requirements: Step 2 before Step 4. Step 4(c) before 4(d), 4(e) before 4(f).

0 An additiomi instmctor/opemtor may be needed to operate the control boards for the examinee.

STARTTIME:

MINES PROCEDURAL STEPS TO RESPOND TO SWNi FAILURE. SAT UNSAT a) Enters 1-AP-4.00 at Step 1.

b) Determines failure not in Power Range NI and goes to step IO.

c) Determines failure not in Intermediate Range NI and goes to step 43.

STEP 2:

STABILIZES UNIT CONDITIONS SAT STANDARD: UNSAT a) Determines failure in the Source Range Mls.

b) Verifies unit conditions stable with a zero startup rate.

c) Maintains power with zero startup rate.

EVACUATOR'S NOTE:

A manual reactor trip is NOT an acceptable action.

COMMENTS:

Page 3 of 7

Surry 2004-301 Remove SW NI From Service SAT I

STANDARD: UNSAT Checks reactor power level by observing INT RN6 FLUX meters NI-1-35B and NI-1-368 (on Benchboaad 6-2) or the meters on the IR NIS cabinets. (Reactor power should be above 1 x IO- amps).

COMMENTS:

I

• STEP 4:

REMOVE FAILED SOURCE RANGE NI FROM OPERATION. SAT STANDARD: UNSAT a) Pushes " l i N 33A TR 8" pushbutton and "IN33B BW B" pushbutton.

b) Notes that N-31 and N-32 still have high voltage applied to the detectors.

c) Informs operator that annunciator G-B-1, "Source or INT RNG NIS TRIP BY$" will be received.

d)

• Places LEVEL TRIP switch for N-31 in BYPASS.

e)

• Removes INSTRUMENT POWER fuses for N-31.

f)

• Places LEVEL TfllP switch for N-32 in BYPASS.

g)

• Removes INSTRUMENT POWER fuses for N-32.

h) Notes requirement to refer to Tech Spec Table 3.7-1 Item 4.

i) Notes requirement to make entry in PSL and shift turnover to reinstall fuses.

j) Goes to step 36 of 1-AP-4.00.

EVALUATOR'S NOTE:

When the 1/N 338 TR A or l i M 338 TR B buttons are pressed, annunciator 6-A-3, "NIS SOURCE RNG LOSS OF BET VQb" is received but clears when acknowledged.

It is acceptable to place both SRNl in LEVEL TRIP BYPASS before removing the INSTRUMENT POWER fuses.

CUES e Tell operator (or if asked): The SS will ensure that Tech Specs are checked and that appropriate log entries will be made.

COMMENTS:

Page 4 of 7

SUFW 2004-301 Remove SR NI From Service STEP 5:

REPORT TO SHIFT SUPERVISOR (EVALUATOR). SAT STANDARD: UNSAT Verbal status report that N-31 and N-32 have been removed from service LAW AQ-4.00.

STOP TIME:

COMMENTS:

I -

Page 5 of 3

Suri-j 2004-301 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER) msk

. Task is to be performed in the simulator.

Perform Steps of I -AP-4.00, Nuclear Instrumentation Malfunction. to allow reactor startup to continue.

The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

. N-31 has failed low with reactor Dower at 1.3 x 10-" amps during removedfrom either N-31 or N-32.

- a startup, and the SI3 high

- voltage cannot be e During a reactor startup, when P-6 was reached the operator pushed 1/N-338 TR A and 1/N-33B TW B to de-energize the Source Range Nls. However, N-31 failed low instead, and the high voltage was not removed from either detector (N-31 or N-32).

e I need you to respond to a failure of both Source Range Nls, IAW 1-A$-4.00, so the reactor startup can continue.

When you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT) lasla e Task is to be performed in the simulator.

e Perform Steps of 1-AP-4.00, Nuclear Instrumentation Malfunction, to allow reactor startup to continue.

tor will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

N-37 has failed low with reactor power at 1.3 x 10-" amps during a startup, and the SR high voltage cannot be removed from either N-31 or N-32.

During a reactor starkup, when P-6 was reached the operator pushed IN-33A TR W and 1/N-33B TR B to de-energize the Source Range Nls. However, N-31 failed low instead, and the high voltage was not removed from either detector (N-31 or N-32).

e I need you to respond to a failure of both Source Range Nls, IAW 1-AP-4.00, so the reactor startup can continue.

e When you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 Pzr Level Channel Fails LOW Iask RESPONSE TO PRESSURIZER LEVEL CHANNEL9 FAILING LOW RO/SRO 10 Minutes 028M1.08(3.7/3.6)

Bf&mmas Surty JPM 1038-09 1E-H6, PRZR LO LVb CH-3, Rev. 3 lC-E8, PWZR LO LVb HTFiS OFF &. LETDOWN ISOL, Rev. 1 1-OP-CH-020,Placing Letdown In Service Follow-iring Auto or Manual Isolation, Rev. 1 Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE DATE COMMENTS:

Page 1 of 9

Surry 2004-301 Pzr bevel Channel Fails Low to be PERFORMED in the simulator.

0 Plant is at 100% Power, Steady State stmda&

0 Pressurizer Heaters Energized and Letdown Flow Established RO. You are to respond to plant conditions as they present themselves.

0 1-OP-CH-O2Qcompleted 0 1C-E$, PRZR LO bVh HTRS OFF & LETDOWN ISOL.

1-OP-6H-020, Placing Letdown In Service FfftlffwiflgAuto or Manual Isolation None 0 Call up 100% power IC and initialize place in RUN, select position Wl1 on the Pressurizer level control selector switch..

Program malfunction for low failure of Pressurizer bevel Channel 111 (RC-LT-l461), trigger 1.

Freeze sirnulator for task performance.

Obtain a copy of 0P-CH-020.

0 After evaluation begins, activate trigger 1.

Page 2 of 9

Surry 2004-301 Pzr bevel Channel Fails Low Task critical elements are denoted by an asterisk (*). If substeps of a critical element also have an asterisk r),

then only those asterisked substeps are critical to performance of that task element.

Critical step sequencing requirements: Step 3 prior to Step 5; Step 50 prior to Step 5r.

START TIME:

SAT UNSAT (a) Identifies 1-RC-61-1461failed low.

(b) Acknowledges Annunciator E-H-6, PRZR LO LVL CH-3.

Evaluator's Comments step 2:

IDENTIFIES PRESSURIZER HEATERS DE-ENERGIZED I LETDOWN ISOLATED. SAT Standards UNSM (a) Identifies amber lights on above all Pressurizer Heater Control bank switches (b) Acknowledges Annunciator 6-E-8, PWZR LO LVL HTRS OFF & LETDOWN ISOL.

(c) Identifies 0 flow indicated en 1-CH-FI-1150, letdown line flow.

Evaluator's Comments Page 3 of 9

2004-301 Pnr Level Channel Fails how SAT

- - UNSAT

• (a) Moves PRZR LVL CH SEL to the 1/11 position.

(b) Verifbs Pressurizer Heater banks re-energize as indicated by RED Lights above the Heater control switches on.

Evaluator'sNote

""This step is sequence critical.**

Procedural guidance is given in ARP E-H-6: PRZW LO LVt CH-3, C-e)-8: PRZR bC LVL., or C-E-$: P M R LO LVL HTRS OFF & LETDOWN ISOL, But is not required to controi critical parameter (PRZR level).

If ARP C-E-8 is used, Pressurizer heaters are placed in OFF (Step 4 WNO a) and Returned tO seervice (Step 4 RNO e.3.c). Step b above is ONLY a critical step failure il the pressurizer heaters are NOT returned to service.

Evaluator's Comments Step 4:

REDUCES CHARGING FLOW TO MINIMIZE PRESSURIZER FILL. SAT Standards UNSAT (a) Places 1 -CH-FCV-l 122 controller in manual.

(b) Reduces charging flow to minimum as indicated on 1-CH-LI-1122, Charging bine Flow.

Evaluator's Comments I

Surry 2004-301 Pzr Level Channel Fails Low E Step 5:

RESTORES LETDOWN FLOW, SAT Standards LBMSAT Obtains a copy of 1-QP-CW-020.

Verifies and signs Section 3.0, Initial Conditions, that normal and excess Letdown are not in service.

Acknowledges statements in Section 4.0, Precautions and Limitations.

Acknowledges Caution concerning Cation Bed.

Verifies Pressurizer level is greater than 14.4% on 1-RC-LI-1459 and 1-RC-LI-1460.

Verifies C-E-8, PRZR LO LVb HTRS OFF & LETDOWN SOL is clear.

Verifies one GC pump is running by verifying Red light on.

Verifies closed the following valves as indicated by Green light on:

1-CH-FCV-l46QA, LETDOWN LINE ISOL 1-CH-FCV-14608, LETDOWN LINE ISOL o l-CH-HCV-l200A, LETTDOWN OfllFlCE [SOL 1-CH-#CV-1200B, LETDOWN ORIFICE SOL s l-CH-HCV-l20OC, LETDOWN ORIFICE ISOL Verifies open the following valves as indicated by Red light on:

1-CH-TV-I 204A, LETDOWN LIN E l/S TV o 1-CH-TV-I 204B, LETDOWN LINE O/S TV Verifies I-CH-PCV-1145, LFTBWON LINE PRESS CNTRL, setpoint at 5.0 on the controller stpoint dial.

Races 1-CH-PCV-1145 in Manual and increases demand to 0.

Enters N/A for steps 5.1.9 and IO.

Verifies 1-CH-LCV-lI1SA3 VCT LEVEL DIVEflT, is aligned to the VCT as indicated by Red light on.

Acknowledges NOTE concerning Flashing in NRHX.

Increases demand on 1-CH-FCV-1122 to establish at least 45 gpm of charging flow.

Opens the following valves as indicated by Red light on:

m 1-CH-LCV-1460A, LETDOWN LINE ISQL o 1-CH-LCV-I460B, LETDOWN LINE ISOL Notes concerning one 45 gpm and one 65 gpm orifice; 45 gpm orifice first; end care to limit letdown flow to 125 gpm.

Opens 1-CH-HCV-I20OA as indicated by red light on.

Verifies proper response on the following meters:

1-CH-FI-1150 indicates 45 gpm (60 gpm if 12008 or C used) 1-CC-TCV-103 demand indicated 1-CH-TI-I 144 indicates 9Qdegrees Opens 1-CH-HCV-l200B or 1-CH-HCV-12OOC as indicated by Red light on.

Verifies 1-CH-FI-T15D indicates 115 gpm.

Lowers demand on 1-CH-PCV-1145 until 300-350 psig is indicated on f -

CH-PI-1145 Places 1-CH-PCV-I 145 in Auto as indicated by AUTO illuminated.

Adjusts charging flow to lower charging flow to program level.

If Task reported completed prior to Letdown in service: State - "I need you to complete all aRDlkabk AWPs." ~~

Page 5 of 9

2004-301 Pzr Level Channel Fails Low e If Requested: Supply a copy of QP-CH-020.

If Asked: Cation Bed is NOT in service.

If Asked: Mixed Bed IX will remain in service.

If Asked: Deborating bed was not previously in service.

Evaluator's Note

• • This step is sequence critical. **

Evaluator's Note Step r may be Interchanged with step t, however a follow-up question should be asked to determine basis to deviate from the NOTE prior to step 5.7.12.c.

JPM performance may be terminated at the discretion of the evaluator if all steps accomplished and Pressurizer level decreasing towards program.

Notes Evaluator's Comments

'Step 6:

VERIFY PRESSURIZER HEATERS ON. SAT Standards UNSAT If heaters not already on, then applicant re-energizes heaters.

Heater RED indicating lights above Heater control switches illuminated.

Stop Time:

Evaluator's Commnts step 7:

REPORTS TO NUCLEAR SHIFT MANAGER (EVALUATOR). SAT

--UNSAT Standards Verbal status report made that normal charging established.

Stop Time:

Evaluator's Comments I

Page 6 of 9

Surry 2004-301 Pzr Level Channel Fails Low Page 7 of 9

Surry 2084-301 Operator Directions b n d o u t (PQ BE READ TQ APPLICANT BY EXAMINER)

. Task is to be performed in the simulator.

Respond to plant conditions.

The evaluator will explain the initial conditions of the task to be performed. The sirnulator will provide the initiating cue.

Ensure you indicate to the evaluator when you understand your assigned task.

% Power, Steady State

. You are the fl0. You are to respond to plant conditions as they present themselves.

Surry 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Iask 0 Task is to be petformed in the simulator.

Respond to plant conditions.

The evaluator will explain the initial conditions of the task to be performed. The simulator will provide the initiating cue.

Ensure you indicate to the evaluator when you understand your assigned task.

• Plant is at 100% Power, Steady State You are the 80.You are to respond to plant conditions as they present themselves.

Surry 2004-301 Hydrogen Analyzer PLACE HYDROGEN ANALYZERS IN SERVICE FOLLOWING A LQCA.

RO/SWO 5 Minutes

%Fry JPM h058-01 1-E-l, Attachment 3, Hydrogen Analyzer Operation, Rev. 21 Applicant:

Performance Rating: SAT: UNSAT:

Examiner:

NAME SIGNATURE BATE COMMENTS:

Page 1 of 8

Sury 2004-301 Hydrogen Analyzer k is to be PERFORMED in the simulator.

• A LOCA has occurred from 100% power.

e A determination of Containment Hydrogen concentration is desired.

m 1-E- 1 Attachment 3, Hydrogen Analyzer Operation.

~

You are to place Unit 1's Hydrogen Analyzer in service on Unit 1 Containment.

When you finish the actions necessary to accomplish this, please inform me.

1 -E-?, Attachment 3, Hydrogen Analyzer Operation e Call up 100% IC, initialize & place simulator in RUN.

D Initiate LBLOCA malfunction.

m Allow CBMB pressure to increase and return to e 18 psia.

8 Place selector switch for H2A-GW104 in the Unit 2 position.

m Verify selector switch for the H2ANALYZER (H2A-GW-I04) MEAT TRACE PANEL 6,1 -HT-HTP6, is in the AUTO position 8 reset Sf. Check heat tracing de-energized.

• Freeze simulator.

Page 2 of 8

Surry 2004-301 Hydrogen Analyzer e Task critical elements are denoted by an asterisk (*). If substeps of a critical eiement also have an asterisk e), then only those asterisked substeps are critical to performance of that task element.

e Critical step sequencing requirements: 3,4,5(any order) before 6; 6 before 7.

• START TIME:

CHECKS NOTES AT BEGINNING OF ATTACHMENT 3. SAT UNSAT a) Determines containment pressure is between 9 & 60 psia by observing containment pressure indication (1-LM-PI-?OOA, B, C, and D).

b) Betermines containment temperature is between 40°F and 290°F by observing containment Temperature indication (1-LM-TI-lOQ-l and 1-LM-TI-100-2).

COMMEblTS:

STEP2:

DETERMINES ANALYZER TO BE USED. SAT STANDARD: UNSAT Determines from previous instructions that H2A-GW104 is the analyzer to be used.

CUES:

If asked: Unit 1s analyzer is the desired analyzer.

I COMMENTS:

• STEP 3:

SELECT THE ANALYZER (H2A-GW104).

STANDARD:

a) Places selector switch XFER CKB UNIT #f TO UNIT #2 (for H2A-GW104) to the UNIT 1 position.

b) Checks that whhite analyer indicating light for Unit 1 lit.

EVALUATOR NOTE:

• • Phisstep is sequence critical.**

COMMENTS:

Page 3 of 8

Surry 2004-301 Hydrogen Analyzer

• STEP 4:

ENERGIZE HEAT TRACING. __I___ SAT STANDARD: UNSAT a)

• Places selector switch for H2ANALYZER (H2A-GW-104) HEAT TRACE PANEL 6, 1-HT-HTP 6, in the ON position.

b) Checks RED light illuminates after switch is in ON position.

c) Records time that heat tracing was energized in the appropriate block on Attachment 3.

EVALUATOR NOTE:

"'Thhhis step is sequence critical.**

COMMENTS:

STEP 5:

PERFORM VALVE LINEUP TO HPA-GWI04. SAT STANDARD: UNSAT a)

• Opens analyzer inlet, 1-GW-TV-lOO.

b) Checks valve open by observing red indicating light lit & green off.

c) Opens analyzer inlet, 1-GW-TV-101.

d) Checks valve open by observing red indicating light lit & green off.

e)

• Opens analyzer return, 1-GW-PV-183.

f) Checks valve open by observing red indicating light lit & green off.

g)

• Opens analyzer return, 1-GW-TV-102.

h) Checks valve open by observing red indicating light lit & green off.

COMMENTS:

Page 4 of 8

Surry 2004-301 Hydrogen Analyzer

• STEP 6:

ENSURE HEAT TRACING HAS HEATED TO MINIMUM ANALYSIS TEMPERATURE. SAT STANDARD: UNSAT a) Reads NOTE that heat tracing must be in service fer 20 minutes prior to placing the analyzer in service.

b)

• Determines that 20 minute period has NOT yet elapsed and a wait period will be required.

c) Following a 20 minute heat tracing warm-up period, proceeds to next step.

1 ER OPERATOR DETERMINES WAIT PERIOD REQuIBm, tell operator that a TIME I COMPRESSION has occurred and 20 minutes has elapsed.

I EVALUATOR NOTE:

'"This step is sequence cpifical.**

COMMENTS:

• STEP 7:

INITIATE ATMOSPHERE ANALYSIS. SAT STANDARD: UNSAT a)

• Places H2A-GWlO4 mode select switch to the ANALYZE position.

bj Checks RED light illuminates after switch is in ANALYZE position.

EVALUATOR NOTE:

• • Thisstep is sequenm critical.**

COMMENTS:

T TO NUCLEAR SHIFT MANAGER (EVALUATOR). - _ SAT l _

UNSAT Verbal status report made that analyzer has been placed in service.

COMMENTS:

Page 5 of 8

Surry 2004-301 Hydrogen Analyzer Page 6 of 8

Surry 2004-301 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

IaSk a Task is to be performed in the simulator.

a Place Unit 1's hydrogen analyzer in service on Unit 1 Containment.

- cue. Ensure The evaluator will explain the initial conditions of the task to be Deriorrned and will provide the initiatina YOU indicate to the evaluator when you understand your assigned'task.

. ccurred from 100% power.

A determination of Containment Hydrogen concentration is desired (145-4, Loss of Reactor or Secondary Coolant, step 2%)

e You are to place Unit 1's Hydrogen Analyzer in service on Unit 1 Containment.

When you finish the actions necessary to accomplish this, please inform me.

Sur9 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT) ask is to be performed in the simulator.

Place Unit 1's hydrogen analyzer in service on Unit 1 Containment.

The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

e A LOCA has occurred from 1OOo/0 power.

A determination of Containment Hydrogen concentration is desired (1-E-1 , Loss of Reactor or Secondary Coolant, step 25a.)

- - Analyzer in service on Unit 1 Containment.

You are to w lace Unit 1's Hvdrogen e When you finish the actions necessary t6 accomplish this, please inform me.

Surry 2004-301 Transfer To Hot Leg Recirc Disk TRANSFER THE SI SYSTEM TO HOT LEG RECIRCULATION.

WO/SRO 6 Minutes OIlA1.11(4.2/4.2) lReferenees Surry JPM LO52-02 143-1.4, Transfer to Hot beg Recirculation, Revv.4 1-E-1, Loss of Reactor or Secondary Coolant, Rev. 21 Applicant:

Performance Rating: SAT: UMSAT:

Examiner:

NAME SGNATURE DATE COMMENTS:

Page 1 of 7

Surry 2004-301 Transfer To Hot Leg Wecirc to be PERFQRMED in the simulator.

The SI system is on Ts Recirc with the time simulated to be 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after a BBA.

.4,Transfer to Hot Leg Recirculation.

You are the Unit 80. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> point after a major LOCA on Unit 1 has been reached. Currently the SI system is in the Cold Leg Recirc mode with " C Charging pump on the normal header.

. You are to get a copy of l-E§-l.4 end transfer the SI system to Hot beg Recirculation.

When you finish the actions necessary to accomplish this, please inform me.

-§-1.4, Transfer to Hot Leg Recirculation.

n.

e If no pre-staged IC is available, this setup takes -55 minutes.

e Call up 100% power IC & initialize. Put "A" Chg PP in PTL.

e From SIMLOC, energize MOV-l890A, l8903,189QC,1869A & 1%9B.

e Place keys (#46& 47)in MQV control switches For 1890A51890B,1869A & 18698.

e Initiate a LBLOCA on " A loop; perform 1-E-8 and transfer to 1-El; perform E-1 boss of Reactor or Secondary I

Coolant, up to step 27; 2 HHSl pumps (C on normal hdrB on alt hdr) and 2 LHSl pumps are to be operating on Cold beg Recirc.

After system is stable on Cold beg Recirc, freeze simulator for JPM performance.

Page 2 of 7

Surry 2ow-301 Transfer Po Hot Leg Recirc

. Task critical elements are denoted by an asterisk (*). tf substeps of a critical element also have an asterisk ?)>

. then only those asterisked substeps are critical to performance of that task element.

Critical step sequencing requirements: None.

0 STARTTIME:

step 1:

REVIEW NOTE PRIOR TO STEP 1. -- SAT Standards UNSAT Notes that if Hot Leg injection MOV will not open, then the TSG should be consulted to determine the optimal SI alignment.

Evaluator's Comments

• Step 2:

ALIGN "A" LHSl PUMP TO THE HOT LEG FLOWPATH. SAT Standards UNSAT (a) Verifies "A LHSl pump running by observing breaker indication red ligh?on, amps indicated, and flow indication on 1-SI-FI-1945.

• ($) Closes l-SI-MOV-18MA ("A" LHSl to Tc) by holding control switch in CLOSE position.

(c) Verifies l-SI-MOV-1864A dosed by observing green light on & red off.

• (d) Throttles open 1-SI-MOV-1890A ("A" LHSl to Th) until "A" LHSl pump stabilized flow < 3500 gpm as shown on 1-SI-FI-1945.

Ewahator's Comments Page 3 of 7

Surry 2004-381 Transfer To Hot Leg Recirc

• Step 3:

ALIGN " 5 LHSE PUMP TO THE HOT LEG FLOWPATH. SAP Standards UNSAT (e) Verifies B LHSl pump running by observing breaker indication ~ e lightd on, amps indicated, and flow indicated on 1-SI-FI-l946.

• (b) Closes ?-SI-MOV-18645 ("B"LHSl to Tc) by holding control switch in CLOSE position.

(c) Verifies 1-SI-MBV-18648 closed by observing green light on & red off.

• (d) Throttles open 1-SI-MBV-18905 ("B" LHSl to Th) until "B" LHSl pump stabilized flow < 3500 gpm as shown on 1-SI-FI-l946.

Evaluator's Comments Step 4:

REVIEW CAUTION AND NOTE PRIOR TO STEP 2. SAT Standards UMSAT (a) Notes that the amount of time the CHG pumps are stopped should be minimized.

(b) Notes that CHG pumps order of priority is C, B, A.

Evaluator's Comments I *step 5:

i CHECK CHARGING PUMPS -TWO RUNNING. SAT Standards UNSAT (a) Checks that I-CH-P-1C running by observing breaker indication red eight on and amps indicated.

(is) Notes that 1-CH-P-1B is not running by observing breaker indication green light on and no amps indicated. (recall 1-CH-P-?Ais Tagged Out of Service)

• (c) Places 1-CH-P-1C in PTL.

• (d) Opens 1-SI-MOV-18698,HHSl to Hot Legs.

'(e) Closes ?-SI-MOV-1867(3,HHSl to Cold begs

'(f) Closes 1-SI-M0V-1867D3,HHSl to Cold Legs

• (g) Starts 1-CH-P-1C, CHARGING PUMP (k) Verify HHSI flow a 1-SI-FI-1943 & A 4-SI-FI-1933 & 1960 & 1932 (NQ)

Notes If applicant tries to start l-CH-P-IB, it will not start.

Evaluator's Comments Page 4 of 7

Surry 2004-301 Transfer To Hot Leg Recirc Step 6:

REPORT TO SHIIT SUPERVISOR (EVALUATOR). SAT Standards I- UNSAT Verbal status report made that Hot beg Recirc established.

Stop Time Evaluator's Comments

_- I Page 5 of 7

2004-301 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER) e Task is to be performed in the simulator.

m Transfer to Hot Leg Recirculation.

- cue. Ensure The evaluator will exolain the initial conditions of the task to be Derformed and will Dravide the initiatina you indicate to the evaluator when you understand your assignedtask.

The SI system is on Tc Recirc with the time simulated to be 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after a BBA.

m You are the Unit WO. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> point after a major LBCA on Unit 1 has been reached. Currently the SI system is in the Cold Leg Recirc mode with "C" Charging pump on the normal header.

e You are to get a copy of 1-ES-f .4and transfer the SI system to Hot Leg Recirculation.

e When you finish the actions necessary to accomplish this, please inform me.

Surry 2004-301 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Iask Task is to be performed in the simulator.

Transfer to Hot Leg Recirculation.

The evaluator will explain the initial conditions of the task to be performed end will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

e The SB system is on Tc Recirc with the time simulated to be 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after a BBA.

You are the Unit 80. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Doint after a maior LOCA on Unit 1 has been reached. Currently the SI svstsrn is in the Cold Leg Recirc mode with "C"Charging pump on the normal header.

You are to get a copy of 1-ES-l.4 and transfer the SI system to Hot Leg Recirculation.

When you finish the actions necessary to accom@slisk this, please inform me.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Surry Date of EXaminatiQn:FEB2Q04 Examination bevel (Underline one): RO i SFaO Qperating Test Number: 2084-301 AdministratiTopic TDescribe activity to tse perform&

Conduct of Operations I Calculate the Maximum Allowable Reactor Vessel Hydrogen Venting Time G2.1.23 (3.9/4.0); (32.1.25 (2.w3.1)

Conduct of Operations G2.1.7 (3.7M.4)

Construct Tagout fer I -WT-P-IC (SG Recirc & Transfer Pump)

Equipment Cantro! G2.2.13(3.6/3.8)

Dose / Stay Time Calculation Radiation Control G2.3.1 (2l33.1); G2.3.4 (233.1)

Emergency Plan 2.4.41 (2.34.1); 2.4.44 (2.114.Q)

NOTE: All items (5 total) are required far SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

..-- NUREG-1021, Draft Revision 9

ES-302 Administrative Topics Outline Form ES-301-1 Facility: Surry Date of Examination: FEE32004 Examination Level (Underline one): mi SRO Operating Test Number: 2004-301 Administrative Topic Describe activity to be performed (see Note)

Calculate the Maximum Allowable Reactor Vessel Hydrogen Conduct of Operations Venting Time Shutdown Margin Calculation at Zero Power Conduct of Operations Construct Tagout for 1-RT-P-1C (SG Wecirc & Transfer Pump)

Equipment Control Dose / Stay Time Calculation Radiation Control Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

NUREG-1821, Draft Revision 9

ES-301 Control Room/ln-Plant Systems Form ES-301-2 Outline Facility: Surry Date of Examination: FEB200s Exam Level (underline one): m/%flQ(l) / SRO/U) Operating test No.: 2004-301 Control Floom Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

I System / JPM Title Safety Function

b. Place Hydrogen Analyzer In Service Following LOCA (58.01) 028A4.03 (3.1B.3) l 5 C. 0-AP-22.00, Fuel Handling Abnormal Condition Immediate Actions (36.06) d.

034~2.01 (3.~4.4);0 3 6 ~.ai~ 1(3.514.1)

Restore Qffsite Power to 1W 4160V Emergency Bus IAW AP-10.08 (18.06)

I 8 6

062A4.01 (3.33.1); 055EA2.06(3.7t4.1) 8 . Transfer to Hot Leg Recirculationwith 1 Charging Pump in Service (52.02) ESF

~ 8\11 S 3 01 1EA1.11(4.Y4.2)

f. Transfer Feedwater Contra1from !W RYP FLOW HCVs to the FEED REG FCVs NbS in Manual control 059A4.08 (3.012.9)

9. Response io tailed low Pressurizer Level Channel (38.07) 028881.08 (3.9/3.6) 1 DAS 2 61582.02 (3.113.5);015A4.03(3.8/3.9)

In-Plant Systems (3 for WO;3 for SRQ-I; 3 or 2 for SRQ-U) 024AA1.04 (3.813.7)

k. Cross-Connect Turbine Buddlng instrument Air (17.02) 8 065AK3.04 (3.013.2);078K1.03 (3.3/3.4); 065AK3.08(3.7/3.9);069AA2.02(3.9/4.4)

• Type Codes: (B)irect from bank, (M)odified from bank, (NJew, (Allternate path, (C)ontrsl room, (S)imulator, (L)ow-Power, (R)CA NUREG-1022fI Draft Revision 9

ES-301 Control Room/ln-Plant Svsterns Form ES-304 -2 Outline i..

Facility: Surry Date of Examination: FEE32001 Exam Level (underline one): 8 0 / SROfI) / SRQ(U) Operating Test No.: 2004-30' Control Room Systems (8 for WO;'7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title

8. Start Zd RCP / High Vibration

b. I I C. 0-AB-22.00, Fuel Handling AbnormaJ Condition Immediate Actions (36.06)

. Restore Oflsile Power to 1H 416BV Emergency Bus IAW AP-10.08

e. -

Transfer to Hot Leg Recirculation with 1 Charging Pump in Service (52.02) ESF

f. Transfer Feedwater Control from FW BYP FLOW HCVs to the FEED REG FCVs in Manual control for SG 1A in-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SWO-U)

i. Cross-Tie Unit 2 Emergency Buses far Circulating Water Isolation J. Locally Emergency Borate per AOP-3.0, Emergency Boration IDAR 1 1

• Type Codes: (B)irect from bank, (M)odified from bank, (Ngew, fA)lternate path, (C)ontrol room, (Sbimulator, (L)ow-Power, (R)CA NUREG-1021 Deaft Revision 9 I

ES-301 Control Roorn/ln-Plant Systems Form ES-301-2 Outline

• Type Codes: (8)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)irnulator, &)ow-Power, (R)CA Facility: Surry Date of Examination: FEE32001 Exam bevel (underline one): RO / SRO(i) / SROCU) Operating Test No.: 2004-30 Control Room Systems (8 for RO;7 for SRO-l; 2 or 3 for SRO-U) b.

I I

c. I I d.

e. -

Transfer to #et Leg Recirculation with 1 Charging Pump in Service (52.02) ESF I

f. Transfer Feedwater Control from FW BYP FLOW HCVs to the FEED REG FCVs in Manual w t r o l fer SG 1A I NLs I 4S030ndary h.

In-Plant Systems (3 for 8 0 ; 3 for §BO-l; 3 or 2 for SRO-U) 1.

1. beeally Emergency Borate per WOP-3.0, Emergency Boratian

k. Cross-Connect Turbine Building Instrument Air I I

• Type Codess: (8)irect from bank, (Mjodified from bank, (N)ew, (A)lternate path, (6)ontsol room, (S)imulator, (L)ow-Power, (R)CA NUWEG-1821, Draft Revision 9