ML110390422

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Initial Exam 2010-302 Final Administrative JPMs
ML110390422
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 02/04/2011
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
50-327/10-302, 50-328/10-302
Download: ML110390422 (253)


Text

F AL Sequoyah Nuclear Plant L SEPT 2010 NRC INITIAL LICENSE ROISRO Admin JPM ExAM Administrative JPMs (RO/SRO)

NAL

JPM RO A-2 Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE RO A-2 Boric Acid Storage Tank Level Operability Determination

JPM RO A-2 Page 2 of 10 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Determine the Operability of a BAT before use.

Task#: 0040090101 (RO)

Task Standard:

Determine the operability of BAST C prior to placing tank in service.

Time Critical Task: YES: NO: X KIA Reference/Ratings: 2.1.25 (3.9/4.2) 2.2.12 (3.7/4.1)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 15 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS SPECIAL INSTRUCTIONS TO EVALUATOR:

JPM RO A-2 Page 3 of 10 Rev. 0

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
2. Any UNSAT requires comments
3. Ensure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.

Tools/Equipment/Procedures Needed:

TRM (TR 3.1.2.5 and 3.1.2.6) 1 -Sl-OPS-000-003.W OPSLINKS READ TO OPERATOR DIRECTIONS TO TRAINEE:

JPMROA..2 Page 4 of 10 Rev. 0 I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is at 100% power
2. Preparations are in progress to place a clearance on BAT A for Maintenance.
3. BAT C level is indicating is 10,000 gallons on 0-LI-62-242.

INITIATING CUES:

1. You are the Unit 1 OATC and the US has directed you to determine operability status for BAT C level in accordance with 1-Sl-OPS-000-003.W, prior to aligning BAT C to Unit 1.
2. Plot minimum level for operability of BAT C and notify the US of results when determination of operability has been completed.

JPMROA-2 Page 5 of 10 Rev. 0 Job Performance Checklist:

STEP I STANDARD SAT I UNSAT STEP 1.: Operator goes to 1 -Sl-OPS-000-003.W to review BAT C SAT Level operability requirements.

UNSAT STANDARD: Operator reviews 1-Sl-OPS-000-003.W, Appendix A, SR requirements for BAT C level operability. Start Time COMMENTS:

NOTE: Operator may call Chem Lab to verify the latest boron concentration for Unit 1 RWST and BAT C.

STEP 2.:: Operator obtains a copy of the Operations Information SAT sheet containing Chemistry data from Computer:

Opslinks/Common/Chemistry Information for the current UNSAT day to determine the boron concentration of BAT C and the Unit I RWST or call Chemistry lab to verify Ui RWST and BAT C Boric Acid concentrations.

CUE When Operator describes how the chemistry data would be obtained, give them Attachment 1, Operations Information (Chemistry data sheet)

STANDARD: Operator determines the current Boric Acid concentration for BAT C and Unit 1 RWST.

STEP 3.: Operator utilizes the TRM and reviews TR 3.1 .2.6.a.1 SAT requirement for BAT C level.

UNSAT NOTE: Figure 3.1.2.6 has three separate graphs, one for each BAT, operator must select graph for BAT C.

STANDARD: Operator states the BAT storage system is required to contain a volume of borated water in accordance with Figure 3.1.2.6.

COMMENT:

JPM RO A-2 Page 6 of 10 Rev. 0 Job Performance Checklist:

STEP I STANDARD SAT I UNSAT STEP 4. tépt2. SAT UNSAT STANDARD: Operator selects TRM FIGURE 3.1.2.6 for BAT C only, the figure required to be used is found on page 3/ 4 1-1 Ob. CRITICAL STEP This is critical to select the correct figure for BAT C.

COMMENT:

NOTE: Steps to determine Region of Acceptable Operation on FIGURE 3.1.2.6 based on RWST Boric Acid Concentration or BAT Boric Acid concentration may be performed in either order (JPM step 5 and 6).

STEP 5. SAT UNSAT CRITICAL STEP STANDARD: Using Attachment 1, Operations Information, the operator determines the correct Boric Acid Tank Concentration is 6763 ppm. Conservatively the operator can use the 6750 line for determination of Region of Acceptable Operation.

Critical step for candidate select correct line on Fig 3.1.2.6 to ensure BAT operable.

COMMENT:

STEP 6.

Critical Step STANDARD: Using the chemistry page the operator determines the correct RWST Concentration is 2597 ppm. Conservatively the candidate selects the line for the RWST labeled 2550 ppm.

Critical step to determine the correct RWST boron concentration line.

COMMENTS:

JPM RO A-2 Page 7 of 10 Rev. 0 Job Performance Checklist:

STEP ISTANDARD SAT IUNSAT Evaluator Note: If Operator addresses the statement at the bottom of graph concerning the indicated values including the unusable volume and the instrument error, they should explain the contained water volume limits include allowance for water not available and is discussed in the TRM bases.

STEP 7.

the4htersebon of tfe lmne forthe RWST and AT Bor9n n6entations and verifyipg the actual level in thetanks atr UNSAT Critical Step STANDARD: Operator determines the minimum BAT level in gallons required for operability is 9250 gallons (+50/-1 00 gal.) by picking the point the boric acid concentration lines for the RWST and the BAT intersect, and verifying the actual number of gallons is in the Region of Acceptable Operation.

Critical for candidate to correctly determine the BAT C is acceptable COMMENT:

STEP 8. Operator notifies the US that the level in the C BAT, 10,000 gallons SAT meets the operability requirements for level in accordance with TR 3.1.2.6.a UNSAT STANDARD: SRO is notified that level is BAT is C is adequate to meet the operability requirements in accordance with the TRM. Stop Time COMMENTS:

Cue: This completes the JPM.

READ TO OPERATOR DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit I is at 100% power
2. Preparations are in progress to place a clearance on BAT A for Maintenance.
3. BAT C level is indicating is 10,000 gallons on 0-Ll-62-242.

INITIATING CUES:

1. You are the Unit I OATC and the US has directed you to determine operability status for BAT C level in accordance with 1 -Sl-OPS-000-003.W, prior to aligning BAT Cto Unit 1.
2. Plot minimum level for operability of BAT C and notify the US of results when determination of operability has been completed.

Attachment I Operations Information (Chemistry)

(Page I of 2)

Sample Point Units Boron Date I Time Goal Limit UI RCS ppm 1 130 11/3/09 1130 Variable Variable U2 RCS ppm 2476 1 1/4/09 0856 Variable Variable Ui RWST ppm 2597 11/01/09 0330 25502650 25002700 U2RWST ppm 2608 10/30/09 1114 25502650 25002700 BAT A ppm 6869 1 1/02/09 0320 Variable Variable BAT B ppm 6932 11/05/09 0202 Variable Variable BAT C ppm 6763 11/02/09 0320 Variable Variable UI CLA #1 ppm 2549 1 1/02/09 0330 2470-2630 2400-2700 Ui CLA #2 ppm 2558 11/02/09 0336 2470-2630 2400-2700 Ui CLA #3 ppm 2567 11/02/09 0320 2470-2630 2400-2700 UI CLA #4 ppm 2555 11/02/09 0341 2470-2630 2400-2700 U2 CLA #1 ppm 2539 9/28/09 0947 2470-2630 2400-2700 U2 CLA #2 ppm 2455 10/14/09 1455 2470-2630 2400-2700 U2 CLA #3 ppm 2542 9/28/09 11 15 2470-2630 2400-2700 U2 CLA #4 ppm 2534 9/28/09 1023 2470-2630 2400-2700 Spent Fuel Pool ppm 2285 11/04/09 0215 > 2050 > 2000 Lithium esuIts Date I Time Goal Midpoint Ui RCS Lithium ppm 4.02 11/3/09 1130 3.84-4.14 3.99 U2 RCS Lithium ppm 0.09 10/26/09 1615

Attachment I Operations Information (Chemistry)

(Page 2 of 2)

Indicator Units UI DatelTime U2 DatelTime SI 50 SIG Leakage? Yes/No 11/05/09 11/02/09 No No 0005 0001 SI 137.5 CVE Leakrate gpd <0.1 11/03/09 10/6/09

<5.0 0500 0310 5 gpd leak equivalent cpm 11/03/09 10/03/09 71 135 0500 0130 30 gpd leak equivalent cpm 224 11/03/09 10/03/09 612 0500 0130 50 gpd leak equivalent cpm 11/03/09 10/03/09 0500 0130 75 gpd leak equivalent cpm 11/03/09 10/03/09 500 1469 0500 0130 CVE Air Inleakage cfm 11/03/09 10/03/09 26 8.4 0500 0130 Bkgd on 99/119 11/03/09 10/03/09 cpm 40 40 0500 0130 Correlation Factor 99/119 cpm/gpd 11/03/09 10/03/09 6.13 1906 0500 . 0130 Steady State conditions are necessary for an accurate determination of leak rate using the CVE Rad Monitor

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SURVEILLANCE INSTRUCTION I -SI-OPS-000-003.W WEEKLY SHIFT LOG Revision 43 QUALITY RELATED PREPARED/PROOFREAD BY: H J RICKS RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE:__04/08/09 LEVEL OF USE: CONTINUOUS REVISION DESCRIPTION: Updated breaker UNID on 125VDC Vital Batt Bd III feeder to Vital Inverter 1-Ill per WO 07-777880-000 (EDCN E22208A)

SQN WEEKLY SHIFT LOG 1-SI-OPS-000-003.W Rev. 43 I Page 24 of 46 APPENDIX A Page 17 of 22 SR T.S.

DESCRIPTION MODE NOTE INSTRUMENT UNITS DATA REMARKS REFERENCE LIMITS With Spent Fuel Pit Water Level spent Mm of 23 4.9.11 1 Local depth gage (1) el 734 fuel in ft above pool fuel

TR 4,5,6 11 6400 Gal.

4.1.2.5.a.2 gal.

Boric Acid Tank A Level TRM 1-M-6 TR 1,2,3 12 figure 1-Ll-62-238 Gal.

4.1 .2.6.a.2 3.1.2.6 TR 4,5,6 11 6400 Gal.

4.1.2.5.a.2 gal.

Boric Acid Tank C Level TRM 1-M-6 TR 1,2,3 12 figure 0-LI-62-242 4.1.2.6.a.2 3.1.2.6 Gal.

TR 370,000 1-LI-63-46 4.1.2.6.b.2 1,2,3,4 13,14 or Gal.

4.5.5.a.1 375,000 1-LI-63-49 RWST Level 10% or 1 -Ll-63-50 or I M 6 TR 4,5,6 11 55,000 1-Ll-63-51 or

- 4.1.2.5.b.2 gal 1-LI-63-52or orGal.

1 -LI-63-53 UO/RO REVIEW NOTES

1. Verify water level is above bottom mark on depth gage installed on west wall of spent fuel pit. If water level is in the bottom of the normal range, then contact MCR to make-up to high in the normal range per O-SO-78-1
11. In modes 4, 5 and 6 one boric acid storage tank or RWST is required to be operable.
12. In modes 1,2, and 3 one boric acid storage tank isto be operable if required by LCO 3.1.2.2.
13. In modes 1, 2, 3, and 4 RWST is required to be operable.
14. If deviation of 1000 gallons exists between channels, then submit work request (WR) to have transmitter repaired.

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION TR 3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:

a. A boric acid storage system with:
1. A minimum contained borated water volume of 6400 gallons,

- 2. Between 6120 and 6990 ppm of boron, and

3. A minimum solution temperature of 63°F.
b. The refueling water storage tank with:
1. A minimum contained borated water volume of 55,000 gallons,
2. A minimum boron concentration of 2500 ppm, and
3. A minimum solution temperature of 60°F.

APPLICABILITY: MODES 4, 5 and 6.

ACTION:

MODE 4 - With no borated water source OPERABLE, suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of Technical Specification LCO 3.1.1.1.

MODE 5 - With no borated water source OPERABLE, suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of Technical Specification LCO 3.1.1.2.

MODE 6 - With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS and suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet Technical Specification LCO 3.9.1.

SURVEILLANCE REQUIREMENTS TR 4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:

a. For the boric acid storage system, when it is the source of borated water by:
1. Verifying the boron concentration at least once per 7 days,
2. Verifying the borated water volume at least once per 7 days, and SEQUOYAH UNITS 1 AND 2

- 3/4 1-6 October 19, 2005 TECHNICAL REQUIREMENTS Revision Nos. 13, 25, 35, 36

REACTIVITY CONTROL SYSTEMS RVEILLANCE REQUIREMENTS (Continued)

3. Verifying the boric acid storage tank solution temperature is greater than or equal to 63°F at least once per 7 days by verifying the area temperature to be greater than or equal to 63° F, or
4. When the boric acid tank area temperature is less than 63°F and the boric acid storage system being used as the source of borated water, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify the boric acid tank solution temperature to be

- greater than or equal to 63°F until the boric acid tank area temperature has returned to greater than or equal to 63°F.

For the refueling water storage tank by:

1. Verifying the boron concentration at least once per 7 days,
2. Verifying the borated water volume at least once per 7 days, and
3. Verifying the solution temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while in Mode 4 or while in Modes 5 or 6 when it is the source of borated water.

SEQUOYAH UNITS 1 AND 2

- 3/4 1-7 January 4, 2001 TECHNICAL REQUIREMENTS Revision Nos. 13

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION water source(s) shall be OPERABLE as required by TR 3.1.2.6 As a minimum, the following borated TR 3.1.2.2:

a. A boric acid storage system with:

Figure 3.1.2.6,

1. A contained volume of borated water in accordance with
2. A boron concentration in accordance with Figure 3.1.2.6, and
3. A minimum solution temperature of 63°F.
b. The refueling water storage tank with:

000 gallons,

1. A contained borated water volume of between 370,000 and 375.
2. Between 2500 and 2700 ppm of boron,
3. A minimum solution temperature of 60°F, and
4. A maximum solution temperature of 105°F.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

the above

a. With the boric acid storage system inoperable and being used as one of s within required borated water sources, restore the storage system to OPERABLE statu s and bora ted to a 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> resto re the boric acid SHUTDOWN MARG1N equivalent to at least 1% delta k/k at 200°F:

in HOT SHUT DOWN storage system to OPERABLE status within the next 7 days or be within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ABLE status

b. With the refueling water storage tank inoperable, restore the tank to OPER s and in COLD within one hour or be in at least HOT STANDBY within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

3/4 1-8 January 4, 2001 SEQUOYAH UNITS 1 AND 2 Revision Nos. 13 TECHNICAL REQUIREMENTS

REACTIVITY CONTROL SYSTEMS VEILLANCE REQUIREMENTS TR 4.1.2.6 Each borated water source shall be demonstrated OPERABLE:

a. For the boric acid storage system, when it is the source of borated water by:
1. Verifying the boron concentration at least once per 7 days,
2. Verifying the borated water volume at least once per 7 days, and
3. Verifying the boric acid storage tank solution temperature is greater than or equal to 63°F at least once per 7 days by verifying the area temperature to be greater than or equal to 63°F, or
4. Whenever the boric acid tank area temperature is less than 63°F and the boric acid storage system being used as the source of borated water, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify the boric acid tank solution temperature to be greater than or equal to 63°F until the boric acid tank area temperature has returned to greater than or equal to 63°F.

b For the refueling water storage tank by:

1. Verifying the boron concentration at least once per 7 days,
2. Verifying the borated water volume at least once per 7 days, and
3. Verifying the solution temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SEQUOYAH UNITS 1 AND 2

- 3/4 1-9 June 20, 2005 TECHNICAL REQUIREMENTS Revision Nos. 13, 33

This fiaure is for Boric Acid Tank A only.

TRM FIGURE 3.1.16 (Units 1 8. 2)

BORIC ACID TANK LIMITS BASED ON RWST BORON CONCENTRATION 11000 10500 10000 Cl, z

0

-J

-j 9500 0

uJ D

-J 0

> 9000 C) 8500 C.)

0

£0 Ui I

8000 C) z 7500 7000 6500 6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 BORIC ACID TANK CONCENTRATION - PPM BORON RWST Concentration 42500 PPM +2550 PPM +-2600 PPM 2650 PPM -2700 PPM SEUQYAH UNI I S 1 ANU 2 SeptemBer 2b, 2003 TECHNICAL REQUIREMENTS 3/4 1-10 Revision Nos. 13, 26

This figure is for Boric Acid Tank B only.

[

BORIC ACID TANK REQUIRED VOLUME vs. BORIC ACID TANK CONCENTRATION 9,500 C)

A DCEP ABL OPE ATI N 0 9,000 _\

-J _-\

-j CD F--

X_SL 8,500 s I____

0  %* . ..

-Aç -_

ci: .__

0 F

C) 8,000 :_____

uJ  :

D __

F &

1 -

CON ENTR TI0N IN RW T 3T: / i > b..

0 7,500

> 2E f--fl 5(Lpnm /

-, /

/

.7

/.*

2( QO pm 4// N D 4 ci p4m 7,000 .

._2 QQ_p m 2:

7

( 12fl ppm 10_p im_

(Minin urn) (F aximun) 6,500 6,200 6,400 6,600 6,800 7,000 Co N CENTRATIO N - ppm BORON FIGURE 31.2.6 SEQUOYAH UNITS 1 AND 2

- 3/4 1-ba January 4, 2001 TECHNICAL REQUIREMENTS Revision Nos. 13

This figure is for Boric Acid Tank C only.

TRM FIGURE 3.1.2.6 (Units I & 2)

BORIC ACID TANK LIMITS BASED ON RWST BORON CONCENTRATION 11000 I I I I I I I I I I z

[REGION OF ACCEPTABLE OPERATION 10500 S 4WST=25OOpprnB1

___RWST=2550ppmB j

10000 s  %.j N. 11 4 ,LRWST = 2600 ppm B 1 U) z 0

-J RWST = 2700 ppnU

=

:z:z:z

-J

< 9500 0

Ui D

-J 0

> 9000 *--

-J C)

C) 8500

_______z__

0 -====-

( 6990 ppm (Maximum)

Ui 0

8000 N (6120ppm(Minimum)I Q

z 7500 ERATN

] -

7000 1jIicated values include 1140 gal unusable volume and 800 gal for instrument error 6500 I I I I I I I I I -

6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 BORIC ACID TANK CONCENTRATION - PPM BORON RWST Concentration 42500 PPM 2550 PPM 4--2600 PPM 2650 PPM r2700 PPM bQUOYAI-I UNI I S 1 AND 2 September 26, 2003 TECHNICAL REQUIREMENTS 3/4 1-lOb Revision Nos. 13, 26

REACTIVITY CONTROL SYSTEMS B ORATED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION sources shall be OPERABLE:

TR 3.1.2.5 As a minimum, one of the following borated water

a. A boric acid storage system with:
1. A minimum contained borated water volume of 6400 gallons,
2. Between 6120 and 6990 ppm of boron, and
3. A minimum solution temperature of 63°F.
b. The refueling water storage tank with:

s,

1. A minimum contained borated water volume of 55,000 gallon
2. A minimum boron concentration of 2500 ppm, and
3. A minimum solution temperature of 60°F.

APPLICABILITY: MODES 4, 5 and 6.

ACTION:

would cause introduction MODE 4 With no borated water source OPERABLE, suspend operations that to meet SDM of Technical of coolant into the RCS with boron concentration less than required Specification LCO 3.1.1.1.

that would cause introduction MODE 5 With no borated water source OPERABLE, suspend operations d to meet SDM of Technical of coolant into the RCS with boron concentration less than require Specification LCO 3.1.1.2.

involving CORE MODE 6 With no borated water source OPERABLE, suspend all operations of coolant into the RCS ALTERATIONS and suspend operati ons that would cause introdu ction d to meet Techni cal Specif ication LCO 3.9.1.

with boron concentration less than require SURVEILLANCE REQUIREMENTS demonstrated OPERABLE:

TR4I.2.5 The above required borated water source shall be borated water by:

a. For the boric acid storage system, when it is the source of
1. Verifying the boron concentration at least once per 7 days, and
2. Verifying the borated water volume at least once per 7 days, 314 1-6 October 19, 2005 SEQUOYAH UNITS 1 AND 2 Nos. 13, 25, 35, 36 Revisi on TECHNICAL REQUIREMENTS

REACTIVITY CONTROL SYSTEMS RVEILLANCE REQUIREMENTS (Continued)

3. Verifying the boric acid storage tank solution temperature is greater than or equal to 63°F at least once per 7 days by verifying the area temperature to be greater than or equal to 63°F, or acid
4. When the boric acid tank area temperature is less than 63°F and the boric the source of borated water, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and storage system being used as to be every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify the boric acid tank solution temperature greater than or equal to 63°F until the boric acid tank area temper ature has returned to greater than or equal to 63°F.
b. For the refueling water storage tank by:
1. Verifying.thé boron concentration at least once per 7 days,
2. Verifying the borated water volume at least once per 7 days, and or
3. Verifying the solution temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while in Mode 4 while in Modes 5 or 6 when it is the source of borated water.

3/4 1-7 January 4, 2001 SEQUOYAH UNITS 1 AND 2 Revision Nos. 13 TECHNICAL REQUIREMENTS

TEMS RACTIVITY CONTROL SYS OPERATING BORATED WATER SOURCES OPERATION LIMITING CONDITION FOR OPERABLE as required by mini mum , the follo wing bora ted water source(s) shall be TR 3.1.2.6 As a TR 3.1.2.2:

with:

a. A boric acid storage system

.6, water in accordance with Figure 3.1.2

1. A contained volume of berated ance with Figure 3.1.2.6, and
2. A boron concentration in accord of 63°F.
3. A minimum solution temperature with:
b. The refueling water storage tank gallons, me of between 370,000 and 375.000
1. A contained borated water volu boron,
2. Between 2500 and 2700 ppm of 60°F, and
3. A minimum solution temperature of 105°F.
4. A maximum solution temperature of APPLICABILITY MODES 1,2, and 3.

ACTION:

e erable and being used as one of the abov

a. With the boric acid storage system inop s within the storage system to OPERABLE statu required borated water sources, restore ted to a Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and bera 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDB boric acid least 1% delta klk at 200°F; restore the SHUTDOWN MARGIN equivalent to at TDO WN within the next 7 days or be in HOT SHU storage system to OPERABLE status within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

LE status inoperable, restore the tank to OPERAB

b. With the refueling water storage tank and in COLD STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> within one hour or be in at least HOT hours.

SHUTDOWN within the following 30 January 4, 2001 314 1-8 SEQUOYAH UNITS 1 AND 2

- Revision Nos. 13 TECHNICAL REQUIREMENTS

REACTIViTY CONTROL SYSTEMS VEILLANCE REQUIREMENTS OPERABLE:

TR 4.1.2.6 Each borated water source shall be demonstrated water by:

a. For the boric acid storage system, when it is the source of borated
1. Verifying the boron concentration at least once per 7 days, and
2. Verifying the borated water volume at least once per 7 days, than or equal to
3. Verifying the boric acid storage tank solution temperature is greater ature to be greater than or 63°F at least once per 7 days by verifying the area temper equal to 63°F, or 63°F and the boric acid
4. Whenever the boric acid tank area temperature is less than within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and every storage system being used as the source of borated water, ature to be greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify the boric acid tank solution temper returne d to greater or equal to 63°F until the boric acid tank area temperature has than or equal to 63°F.
b. For the refueling water storage tank by:
1. Verifying the boron concentration at least once per 7 days,
2. Verifying the borated water volume at least once per 7 days, and
3. Verifying the solution temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3/4 1-9 June 20, 2005 SEQUOYAH UNITS 1 AND 2 Revision Nos. 13, 33 TECHNICAL REQUIREMENTS

This figure is for Boric Acid Tank A only.

TRM FIGURE 3.1.26 (Units I & 2)

BORIC ACID TANK LIMITS BASED ON RWST BORON CONCENTRATION 11000*

I II I I II I z

IREGION OF ACCEPTABLE OPERATION (RWST=25OoppmB__zr I

10500

%4 I I

{RWST255OPPmB

- / WST=2600ppmB - -

10000 ARWST=265oPpmB U) z - L 0

-j

-J

< 9500 HN j/(RWST=2700PPn 0

Lu D

-J 0

> 9000 -

C)

< 8500 ---

C-)

90 ppm (Maximum) 0 -

0 Ui 8000 Ci [2oppmimum) 0 z

7500 ER EGI ON OF UNACCEPTABLE OPERA11ON 7000 HHT1H I I 1

[indicated values include 1140 gal unusable voiume and 800 gal for instrument error.

6500 - I I I I I I I -

6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 BORIC ACID TANK CONCENTRATION PPM BORON -

RWST Concentration

+2500 PPM 4-2550 PPM +2600 PPM *2650 PPM 2700 PPM tzQUUYPM - UNI I 1 I\NU September 26, 2003 TECHNICAL REQUIREMENTS 3/4 1-10 Revision Nos. 13, 26

This figure is for Boric Acid Tank B only.

L BORIC ACID TANK REQUIRED VOLUME vs. BORIC ACID TANK CONCENTRATION 9,500 (I)

7, A DCEP ABL OPERATION 0 9,000 _

-J E-* . -

1

-. 4

\

%% *4 CD H---

-z

%\

8,500 D

uJ cc 0

1 Cl) 8,000 :______

w D

a-r.

-J 0 7,500 CON ENTR \TION IN RWT: / )<,

QQp4 m 7/

> 2F 0PEm // / V 2f Qflpj m / / / I____

D __

Zf 5Lp m4 /

7,000 z

- ( 122 ppin 3fLp m -

(Miriin urn) (Maximu )

6,500 1._____

6,200 6,400 6,600 6,800 7,000 CONCENTRATION - ppm BORON FIGURE 3.1.2.6 SEQUOYAH UNITS 1 AND 2 3/4 1-ba January 4, 2001 TECHNICAL REQUIREMENTS Revision Nos. 13

Iiiiflre is for Boric Acid Tank C only.

TRM FIGURE 3.1.2.6 (Units I & 2)

BORIC ACID TANK LIMITS BASED ON RWST BORON CONCENTRATION 11000 I I I

[EGION_OF ACCEPTABLE OPERATION (I I I 10500 JRWST=2500ppmB J I I I RWST = 2550 ppm B

/

10000 RWST = 2600 ppmB 1 U) z -- I I 0 = 2700 pp

-J 4/tRWST -

-J

< 9500 . - - - -

CD Ui

--- i --

D --

-J 0

> 9000 --I--

çc C)

< 8500 .-- -

0 0

cri 0

Ui 8000 0 {6Oppmimum) 0 z

7500 zz:_____

[_REGION OF UNACCEPTABLE OPERATION J

7000 iicated values indude 1140 gal unusable volume and 800 gal for instrument error.

6500 - I I I I I I I I I 6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 BORIC ACID TANK CONCENTRATION - PPM BORON

[bLUOYAM

+2500 PPM

- UNI I TECHNICAL REQUIREMENTS 1 I\NU 2550 PPM RWST Concentration

+-2600 PPM 3/4 1-lOb

-2650 PPM 2700 PPM September 26, 2003 Revision Nos. 13, 26

JPM ROA.1.b Page 1 of 7 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam RO A.1.b Perform RCS Deboration Calculation

JPM ROA.1.b Page 2 of 7 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task Place a CVCS Mixed Bed Demineralizer in Service Task # 0040100101 (RO)

Task Standard: Determine the in service time for an unborated mixed bed demineralizer to remove the desired amount of boron for reactivity control at end of life.

Time Critical Task: YES: NO: X KIA Ratings: 2.1.25 (3.9/4.2)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: /

Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 15 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

JPM ROA.1.b Page 3 of 7 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical Steps are identified in step SAT/UNSAT column by bold print Critical Step.
2. Any UNSAT requires comments
3. Task should be performed in a classroom.

ToolslEquipment/Procedures Needed: 1-SO-62-9, section 5.2 and App. B

REFERENCES:

Reference Title Rev No.

1 -SO-62-9 CVCS Purification System 41

JPM ROA.i.b Page 4 of 7 Rev. 0 READ TO OPERATOR DIRECTIONS TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. All steps shall be performed for this task When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit-i is in Mode I coasting down prior to refueling with rods in Auto.
2. The current RCS CB is 61 ppm.
3. Current RCS temperature is 575°F.
4. Mixed Bed 1A contains fresh, unborated resin; 1 B Mixed Bed is in service for RCS cleanup.
5. Maximum letdown flow will be used during this evolution.
6. The iA mixed bed will be used for RCS deboration in accordance with i-SO-62-9 section 5.2.2 Placing Mixed Bed A In Service For RCS Deboration.
7. You are an extra operator.

INITIATING CUES:

1. The Unit SRO has directed you to perform 1-SO-62-9, CVCS Purification System,: Appendix B RCS Deboration Calculation, to estimate the time that CVCS Mixed Bed Demineralizer Amust be in service in order to reduce RCS boron concentration to 59 ppm.
2. Report the results of your calculation to the Unit-i SRO.

JPM ROA.1.b Page 5 of 7 Rev. 0 Job Performance Checklist:

STEPISTANDARD SAT/UNSAT STEP 1: The candidate reviews the in-progress procedure and locates SAT Appendix B.

UNSAT Cue: Provide the candidate a copy of the in-progress procedure including Appendix B.

STANDARD: The candidate locates Appendix B.

COMMENTS:

STEP 2: Cf = e 0

C SAT where:

Cf = Final Boron Concentration UNSAT 0 = Initial Boron Concentration C

Q Mixed Bed Flow Rate (gpm) (Letdown Flow)

V = At Temperature RCS Volume (-64,0O0 gal)

T = Mixed Bed Time In Service (mm)

OR Time = -(64,000IQ)(Ln[Cf÷ 0 C

] )

NOTE: This calculation is based on the Mixed Bed being a fresh unborated bed, and assumes all letdown flow is through the bed.

STANDARD: The candidate identifies the equation solved for the desired variable; Time.

COMMENTS:

JPM ROA.1.b Page 6 of 7 Rev. 0 Job Performance Checklist:

STEPISTANDARD SATIUNSAT STE P3: SAT U N SAT Crftical Step STANDARD: The candidate properly substitutes the values provided in the initial conditions and correctly calculates the desired in service time for the 1A mixed bed as 17.8 +1- .5 minutes (17.3 to 18.3.)

This step is critical to determine the insertion time the mixed bed to achieve the desired dilution.

COMMENTS:

This completes the JPM

READ TO OPERATOR DIRECTIONS TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. All steps shall be performed for this task When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit-i is in Mode 1 coasting down prior to refueling with rods in Auto.
2. The current RCS CB is 61 ppm.
3. Current RCS temperature is 575°F.
4. Mixed Bed 1A contains fresh, unborated resin; lB Mixed Bed is in service for RCS cleanup.
5. Maximum letdown flow will be used during this evolution.
6. The 1A mixed bed will be used for RCS deboration in accordance with i-SO-62-9 section 5.2.2 Placing Mixed Bed A In Service For RCS Deboration.
7. You are an extra operator.

INITIATING CUES:

1. The Unit SRO has directed you to perform l-SO-62-9, CVCS Purification System,: Appendix B RCS Deboration Calculation, to estimate the time that CVCS Mixed Bed Demineralizer Amust be in service in order to reduce RCS boron concentration to 59 ppm.
2. Report the results of your calculation to the Unit-i SRQ.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION I -SO-62-9 CVCS PURIFICATION SYSTEM Revision 41 QUALITY RELATED PREPARED BY: OLIVIA TAYLOR RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 03/29/10 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION: Revised Section 8.3 and 8.4 to remove steps which close 1 915 due to valve operator malfunction. Also made changes to Att I for 1-62-915 configuration.(10000087)

PERFORMANCE OF THIS PROCEDURE COULD IMPACT REACTIVITY

I -S 0-62-9 SQN CVCS PURIFICATION SYSTEM Rev. 41 1

Page7of 147 3.0 PRECAUTIONS AND LIMITATIONS A. Personnel Hazards

1. Follow all radiological control procedures and precautions while performing this instruction.
2. Removing the Reactor Coolant Filter from service must be coordinated with RADOON before any valves are manipulated.
3. When the Reactor Coolant Filter is removed from service, dose rates in the area of the centrifugal charging pumps could be higher than normal.
4. Flushing a mixed bed demineralizer to Tritiated Drain Collector Tank (TDCT) may cause Airborne activity in Auxiliary Building.
5. Entry into the filter cubicles requires a confined space permit.

B. Mixed Bed Demineralizer Operation

1. The water temperature entering the mixed bed demineralizers must not exceed 145° F, to prevent resin damage.
2. Maintain flow through Mixed Bed Demineralizers within design flow rate of between 20 and 120 gpm when bed is in service, except during RCS cleanup in Modes 5 or 6. 0-GO-7 contains requirements for raising letdown flow to 180 gpm during outages.
3. Boron Concentration Changes
a. An unanticipated power change of greater than +/- 1%, OR rod motion greater than +/- 5 steps OR TAVG change greater than +/-1°F should be evaluated as a potential reactivity management event per SPP-10.4 Reactivity Management Program.
b. To avoid rapid reduction of RCS Boron concentration, either ensure mixed bed demin has been previously borated prior to placing in service, or borate slowly while placing in service.
c. Placing a previously used or borated bed in service when the RCS Boron concentration is low (EOL), may result in a decreased Tave requiring large amounts of dilution. Flush bed with RCS water before placing in service.
d. Placing a previously used or borated bed in service when the RCS Boron concentration is high (BOL) and bed was last used when Boron concentration was low (EOL), will result in an increase in Tavg and a possible increase in reactor power.

End of Section 3.0

I -SO-62-9 SQN CVCS PURIFICATION SYSTEM Rev. 41 I

Page8of 147 Date 1 Tc\

PREREQUISITE ACTIONS Throughout this instruction where an IFITHEN statement exists, the step should be N/Ad if the condition does not exist.

ENSURE the instruction to be used is a copy of the effective version.

ENSURE Precautions and Limitations, Section 3.0, has been reviewed.

ENSURE Attachment 1, CVCS Purification System Valve Checklist 1-62-9.01, is complete.

IF placing Demin Beds in to or out of service AND this could result in a change to radiological conditions, THEN

ç-

NOTIFY Radcon.

IF performing Section(s) that require Mixed Beds to be bypassed, THEN NOTIFY RCL to secure zinc injection, if required.

49-REVIEW Unit and Radwaste Status Files for any off normal alignments that may impact performance. i fiENSURE each performer documents their name and initials:

Print Name Initials cr\

1 -S 0-62-9 SQN CVCS PURIFICATION SYSTEM Rev. 41

. I Page9ofl47 Date________

PREREQUISITE ACTIONS (continued) jThiICATE below which performance section of this instruction will be used.

LT 5.0 STARTUP/STANDBY READINESS U 6.0 NORMAL OPERATION El 7.0 SHUTDOWN El 8.0 INFREQUENT OPERATION REMARKS:  ?\C\Q M S2CS End of Section 4.0

I -SO-62-9 SQN CVCS PURIFICATION SYSTEM Rev. 41 I

Page49of 147 Date L Ac..

5.2.2 Placing Mixed Bed A In Service For RCS Deboration VERIFY that entry into this section is directed by Section 5.2.1, Determining Method of Placing Mixed Bed Demineralizers In Service.

A Placing a new mixed bed in service may remove as much as 100 ppm of boric acid from the RCS.

Using this method, instead of diluting to maintain power, the inlet valve will be throttled open and closed to maintain power at desired level until bed boration is complete.

Mixed beds can be used to remove Lithium from the RCS as directed by Chem Lab Shift Supervisor.

Appendix A, Mixed Bed Boration Log, should be filled out as needed during this instruction.

J11VERIFY Mixed Bed Demineralizer B is in service.

Control rods are NOT in AUTO, THEN

_jfrLACE Control rods in AUTO, in accordance with O-SO-85-1, Control Rod Drive and Rod Position Indication System, TABLISH continuous monitoring of Tavg during this operation.

J1ENSURE radio communication is provided between AUO at local valves and Unit Control Room at all times while valves are being manipulated.

I -S 0-62-9 SQN CVCS PURIFICATION SYSTEM Rev. 41 I

Page5oof 147 Date Toc.j 5.2.2 Placing Mixed Bed A In Service For RCS Deboration (Continued)

CAUTION I Placement of an unborated I underborated mixed bed demineralizer in service will insert positive reactivity and cause Tavg to increase.

CAUTION 2 Utilization of the mixed bed demineralizer at RCS Boron concentrations above 50 ppm may fully saturate the bed before RCS Boron is fully removed.

CAUTION 3 Placing a new mixed bed in service with RCS Boron less than 100 ppm may remove as much as 35 ppm of Boron from the RCS.

NOTE Appendix A, Mixed Bed Boration Log, should be filled out as needed during performance of this instruction.

[5] IF RCS Boron concentration is 100 ppm or less, THEN

[a] PERFORM Appendix B, RCS Deboration Calculation, for amount of time [1-62-901] Mixed Bed Demineralizer A Isolation is to be open.

Minutes uo/Ro

[b] PERFORM Independent Verification of opening time calculation.

IV (SRO)

[c] IF a flush of Mixed Bed Demineralizer A is required, THEN PERFORM Appendix C.

1-SO-62-9 SQN CVCS PURIFICATION SYSTEM Rev. 41 I

Page 51 of 147 Date__________

5.2.2 Placing Mixed Bed A In Service For RCS Deboration (Continued)

[d] ENSURE [1-HS-62-79A] Mixed Bed Hi Temp Bypass is in V.C. Tk position. (Panel 1-M-6) 1st CV

[e] ENSURE [1-62-901] Mixed Bed DemineralizerA Isolation fully OPEN. (Aux Bldg, 690, outside 690 Pene Rm) 1st CV

[fi ENSURE [1-62-908] Mixed Bed Demineralizer B isolation CLOSED. (Aux BIdg, 690, outside 690 Pene Rm) 1st CV CAUTION Placing 1-HS-62-79A, Mixed Bed Hi Temp Bypass, to DEMIN position will insert positive reactivity and cause Tavg to increase.

NOTE Mixed Bed A may be removed from service to allow RCS parameters to stabilize and then returned to service, providing the total time 1-HS-62-79A is in DEMIN does not exceed the calculated opening time.

[g] PLACE [1-HS-62-79A] Mixed Bed Hi Temp Bypass to DEMIN position. (Panel 1-M-6) 1st CV

[h] ADJUST charging flow using [I-HIC-62-93A1 and

[1-HIC-62-89A] to maintain level program with the following parameters:

1. Between 6 and 11 gpm supply to each RCP seal. (Panel 1-M-5) LI
2. Total RCP seal flow less than 40 gpm (for all 4 RCP5). (Panel 1-M-5)

I -SO-62-9 SQN CVCS PURIFICATION SYSTEM Rev. 41 I

Page52of 147 Date__________

5.2.2 Placing Mixed Bed A In Service For RCS Deboration (Continued)

[i] WHEN the calculated opening time has elapsed, THEN

1. PLACE [1-HS-62-79A] to V.C. Tk position.

1st CV

2. OPEN [1 9081. 1t s
3. CLOSE [1 9011.

1st CV

4. PLACE [I-HS-62-79A1 Mixed Bed Hi Temp Bypass to DEMIN position. (Panel 1-M-6) 1st CV
5. COMPLETE time and date signoffs on Appendix A, Mixed Bed Boration Log.

NOTE The mixed bed will not be considered borated until Chem Lab confirms by sample that it is borated.

[6] REQUEST RCS Boron concentration sample from Chem Lab Shift Supervisor, and RECORD results, Boron.

[7] IF additional deboration is required, THEN RETURN to step [5].

I -S 0-62-9 SQN CVCS PURIFICATION SYSTEM Rev. 41 I

Page53of 147 Date 5.2.2 Placing Mixed Bed A In Service For RCS Deboration (Continued)

CAUTION Immediately prior to unit refueling outages, an underborated mixed bed may be placed in service for maximum cleanup. This in-service mixed bed could remove up to 60 ppm of RCS boron.

Chemistry and Reactor Engineering assistance will be required to assess reactivity requirements.

[8] IF Mixed Bed A is to be placed in service continuously, THEN

[a] CONTACT Reactor Engineering and Chemistry for guidance on additional boric acid/control rod requirements. (N/A if mixed bed fully borated)

[b] OPEN [1-62-9011 Mixed Bed DemineralizerA Isolation. (Aux Bldg, 690, outside 690 Pene Rm) 1st CV

[c] ENSURE [1 908] Mixed Bed Demineralizer B Isolation CLOSED (Aux Bldg, 690, outside 690 Pene Rm).

1st CV

[d] ENSURE [1-HS-62-79A] Mixed Bed Hi Temp Bypass to DEMIN position. (Panel 1-M-6) 1st CV

[e] ENSURE Resin Status Log Sheet updated, AND N/A remainder of section 5.2.2.

1-SO-62-9 SQN CVCS PURIFICATION SYSTEM Rev. 41 1

Page54of 147 Date___________

5.2.2 Placing Mixed Bed A In Service For RCS Deboration (Continued)

[9] COMPLETE time and date signoff on Appendix A, Mixed Bed Boration Log, and send the original to the Unit US/SRO.

NOTE Maximum flow through a Mixed Bed Demineralizer is 120 gpm (180 gpm during RCS cleanup in Mode 5 or 6).

[10] OBTAIN from, the Chem Lab Shift Supervisor, verification that the following conditions exist:

[a] Mixed Bed A is borated to RCS conditions.

[b] Mixed Bed A Lithium removal is within required range.

[c] Resin Status Log Sheet has been noted by Chem Lab that Mixed Bed A is borated and ready for service.

[11] IF Mixed Bed A has been placed in service to remove Lithium, THEN LOG the following in the Unit log:

[a] Time and date Mixed Bed A was placed in service.

[b] Time and date Mixed Bed A is expected to be removed from service.

[12] IF Control rods are NOT in AUTO, THEN PLACE Control rods in AUTO, in accordance with 0-SO-85-1, Control Rod Drive and Rod Position Indication System.

End of Section 5.2.2

l-SO-62-9 SQN CVCS PURIFICATION SYTEM Rev. 41 I

Pagel32ofl47 APPENDIX B Page 1 of I RCS DEBORATION CALCULATION NOTE This calculation is based on the Mixed Bed being a fresh unborated bed, and assumes all letdown flow is through the bed.

-QT C=Ce I 0 v Cf = Final Boron Concentration (ppm) 0 C Initial Boron Concentration (ppm)

Q = Mixed Bed Flow Rate (gpm) (Letdown Flow)

V = At Temperature RCS Volume ( 64,000 gal)

T = Mixed Bed Time In Service (mm)

Calculation for estimated time in service.

  • (Ln )64,000)

Time=

- Q

  • Ln (64,000)

Time = - minutes

f STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

3. CHECK BOTH COPs STOPPED. IF available COP is already running AND adequate charging/seal injection flow exists, THEN GOTOStepl2.
4. ENSURE normal letdown ISOLATED:
  • FCV-62-72 CLOSED
  • FCV-62-73 CLOSED
  • FCV-62-74 CLOSED.
5. ENSURE excess letdown ISOLATED:
  • FCV.-62-54 CLOSED
  • FCV-62-55 CLOSED.

Page 4 of 34

AOP-M.09 LOSS OF CHARGING Rev. 3 SQN NSE I RESPONSE NOT OBTAINED I STEP I ACTION/EXPECTED RESPO e been P the rm al bar rie r coo lin g flow and seal injection flow hav CAUTiON If both RC rapidly.

lost, RCP seals will overheat e over P sea l coo ling has bee n lost, this AOP takes precedenc If all RC onent Cooling NOTE P-R .04 , RC P Ma lfun ctio ns, and AOP-M.03, Loss of Comp AO Water.

seal

6. MONITOR RCP lower bearing and water temperatures:

temp or

  • IF any RCP lower bearing seal water temp is gre ate r than 225°F, THEN GO TO Notes prior to Step 18.

header IF CVCS piping is ruptured,

7. CHECK charging/seal injection THEN of rup ture )

INTACT. (NO indication PERFORM the following:

tify

a. DISPATCH personnel to iden and isolate rupture.

p 18.

b. GO TO Notes prior to Ste ablished: IF SI actuated
8. ENSURE CCP suction path est OR COP suction path from VC T is uated. NOT available,
a. CHECK SI signal NOT act THEN T established: PERFORM the following:
b. ENSURE suction from VC LCV-62-136
1) ENSURE LCV-62-135 and
  • LCV-62-132 and LCV-62-133
2) ENSURE LCV-.62-132 and VCT Outlet to CCP OPEN. LCV-62-133 CLOSED.

Page 5of34

JPM#ROA.3 Page 1 of 7 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam ROA.3 Determine Stay Time

JPM#ROA.3 Page 2 of 7 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Determine Stay Time Task #: 3430290302 Task Standard: Given exposure history, determine stay time for specific task.

Time Critical Task: YES: NO: X K/A Ratings: G2.3.4 (3.2/3.7)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: /

Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 10 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

JPM#ROA.3 Page 3 of 7 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Steps are identified in step SAT/UNSAT column by bold print Critical Step.
2. Any UNSAT requires comments
3. Task should be performed in a class room.

ToolslEquipmentlProced u res Needed: None

REFERENCES:

I RCI-03 I Personnel Monitoring I Rev 48 I

JPM#ROA.3 Page 4 of 7 Rev. 0 READ TO OPERATOR Directions to Trainee:

will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. All steps shall be performed in the classroom for this task When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task.

To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The Work Control Center (WCC) SRO has requested you to hang a Clearance in a High Radiation Area where the known dose rate is 280 mrem/hr. Your current year exposure history, documented on your NRC Form 4 is as follows:

  • Committed Dose Equivalent (CDE) 10 mrem
  • Committed Effective Dose Equivalent (CEDE) 200 mrem
  • Eye dose Equivalent (LDE) 20 mrem
  • Shallow Dose Equivalent (SDE) 5 mrem INITIATING CUES:

The WCC SRO has directed you to determine your maximum stay time in the High Radiation Area while hanging the Clearance before exceeding the Sequoyah Administrative Dose Level (ADL) for Total Effective Dose Equivalent (TEDE.)

Report the results of your calculation to the WCC SRO.

JPM Page 5 of 7 Rev. 0 Job Performance Checklist:

STEPISTANDARD SAT/UNSAT STEP :1 SAT UN SAT STANDARD: Critical Step The candidate performs the following calculation to determine the current TEDE:

TEDE = DDE + CEDE TEDE = 400 mrem + 200 mrem = 600 mrem This step is critical for the RO to be able to determine his TEDE for calculations.

COMMENTS:

STEP 2 TI ditdties his? hdr rem ai dóse1aiiab1e. bef6r SAT Dose jeyéJ (ADLJ UNSAT NOTE: The AOL is 1.0 R TEDE from RCI 03 Personnel Monitoring without additional authorization. Critical Step STANDARD:

Dose Available = ADL Limit Current TEDE Dose Available = 1000 mrem 600 mrem = 400 mrem This step is critical for the RO to determine allowable dose left to calculate stay time.

COMMENTS:

JPM Page 6 of 7 Rev. 0 Job Performance Checklist:

STEP/STANDARD SAT/UNSAT STEP :3 trti: SAT UNSAT STANDARD:

Critical Step Stay time = Dose Available ÷ Dose Rate Stay time = 400 mrem ÷ 280 mrem/hr = 1.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> This step is critical to calculate stay time.

COMMENTS:

End Of JPM

Directions to Trainee:

I will explain the initial conditions, and state the task to be performed.

I will provide initiating cues and reports on other actions when directed by you. All steps shall be performed in the classroom for this task When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The Work Control Center (WCC) SRO has requested you to hang a Clearance in a High Radiation Area where the known dose rate is 280 mrem/hr. Your current year exposure history, documented on your NRCForm 4 is as follows:

  • Committed Dose Equivalent (CDE) 10 mrem
  • Committed Effective Dose Equivalent (CEDE) 200 mrem
  • Eye dose Equivalent (LDE) 20 mrem
  • Shallow Dose Equivalent (SDE) 5 mrem INITIATING CUES:

The WCC SRO has directed you to determine your maximum stay time in the High Radiation Area while hanging the Clearance before exceeding the Sequoyah Administrative Dose Level (ADL) for Total Effective Dose Equivalent (TEDE.)

Report the results of your calculation to the WCC SRO.

JPM A.1 .a Page 1 of 6 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam RO/SRO A.1.a Evaluate Overtime Restrictions

JPMA.1.a Page 2 of 6 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Evaluate Overtime Restrictions Task #: (RO) 1190030301; (SRO) 3430050302; (SRO) 0001650302 Task Standard: The candidate identifies the need for an Overtime Limitation Exception Report on 2 occasions:

On 05/30/10 to allow exceeding 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.

On 06/04/10 to allow exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days.

Time Critical Task: YES: NO: X KIA Ratings: G 2.1.5 (2.9/3.9)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 10 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS SPECIAL INSTRUCTIONS TO EVALUATOR:

JPMA.1.a Page 3 of 6 Rev. 0

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
2. Any UNSAT requires comments
3. Ensure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.

ToolslEquipmentlProcedures Needed:

SPP-1 .5, Fatigue Management and Work Hour Limits, Section 3.2

References:

Reference Title Rev No.

1. SPP-1 .5 Fatigue Management and Work Hour Limits 0008
2. 0-PI-OPS-000-027.0 Shift Manager Clerk Duty Station Shift Relief and 0038 Office Round Sheets.

JPM A.1 .a Page 4 of 6 Rev. 0 READ TO OPERATOR DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

You are a Licensed Operator that has worked the following schedule:

Date Hours Status Notes 05/26/10 OFF 05/27/10 OFF 05/28/10 OFF 05/29/10 0630 -2230 Normal Off Day Worked on an Off day and stayed over 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until relief arrived 05/30/10 1830-0700 Normal Work Day 30 minute turnover 05/31/10 1830-0645 Normal Work Day 15 minute turnover 06/01/10 1830-0715 Normal Work Day 45 minute turnover 06/02/10 1830-0730 Normal Work Day 60 minute turnover 06/03/10 OFF Normal Off Day 06/04/10 0630-1 845 Normal Off Day Called in to cover shift (15 minute turnover) 06/05/10 1300-1900 Normal Off Day Called in to cover shift to relieve a sick operator. (30 minute turnover) 06/06/10 A/L Normal Work Day Took Annual Leave for the shift 06/07110 0630-1845 Normal Work Day 15 minute turnover 06/08/10 0630-1930 Normal Work Day 60 minute turnover 06/09/10 OFF Normal Off Day INITIATING CUES:

Determine the date(s), if any, that would exceed the Fatigue Rule and would require an Overtime Limitation Exception Report to be completed prior to you completing the identified working hours and the reason(s) for the report(s) being required.

JPMA.1.a Page 5 of 6 Rev. 0 Job Performance Checklist:

STEP I STANDARD SAT I UNSAT STEP 1.: Ev1uaté tje hours wprked against te tçqØIcmep SAT U N SAT STANDARD: Candidate identifies an Overtime Limitation Exception Report is required prior to completing the 05/30/10 shift to allow exceeding 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> in a 48 Critical Step hour period. (shaded portion)

Shaded portion is critical because the worker would exceed 26 hrs in a 48 hr period if allowed to complete the shift on 05/30/10.

COMMENTS:

STEP 2.: SAT UNSAT STANDARD: Candidate identifies an Overtime Limitation Exception Report is required prior to completing the 06/04/10 shift to allow exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period. Critical Step (shaded portion)

Shaded portion is critical because the worker would exceed 72 hrs in a 7 day period if allowed to complete the shift on 05130/10.

Cue: This completes the JPM.

COMMENTS:

Stop Time

READ TO OPERATOR DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

You are a Licensed Operator that has worked the following schedule:

Date Hours Status Notes 05/26/10 OFF 05/27/10 OFF 05/28/10 OFF 05/29/10 0630 -2230 Normal Off Day Worked on an Off day and stayed over 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until relief arrived 05/30/10 1830-0700 Normal Work Day 30 minute turnover 05/31/10 1830-0645 Normal Work Day 15 minute turnover 06/01/10 1830-0715 Normal Work Day 45 minute turnover 06/02/10 1830-0730 Normal Work Day 60 minute turnover 06/03/10 OFF Normal Off Day 06/04/10 0630-1845 Normal Off Day Called in to cover shift (15 minute turnover) 06/05/10 1300-1900 Normal Off Day Called in to cover shift to relieve a sick operator.

(30 minute_turnover) 06/06/10 AlL Normal Work Day Took Annual Leave for the shift 06/07/10 0630-1845 Normal Work Day 15 minute turnover 06/08/10 0630-1930 Normal Work Day 60 minute turnover 06/09/10 OFF Normal Off Day INITIATING CUES:

Determine the date(s), if any, that would exceed the Fatigue Rule and would require an Overtime Limitation Exception Report to be completed prior to you completing the identified working hours and the reason(s) for the report(s) being required.

TITLE SPP-1.5 Fatigue Management and Rev. 0008 I Work Hour Limits Page 1 of 52 Quality Related E Yes C No NPG Standard Programs and Processes Effective Date 06-28-2010 Responsible Peer Team/Working Group: Licensing R. M. CookforR. M. Krich 6/18/2010 Approved by:

Corporate Functional Area Manager Date

  • NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 14 of 52 3.2 Requirements 3.2.1 10 Code of Federal Regulations (CFR) 26 Overtime Limits A. The following limits apply to covered individuals regardless of unit status:
1. No more than 16 work hours in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period
2. No more than 26 work hours in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period
3. No more than 72 work hours in any 7 day period
4. At least a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> break between successive work periods, or an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> break when a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is necessary to accommodate a crews scheduled transition between work schedules or shifts.
5. At least a 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> break in any 9 calendar day period.

B. Online Requirements

1. During online operations and without issuance of a waiver, an individuals required average minimum days off shall adhere to the requirements listed in Table 1 below (averaged over the shift cycle):

Table 1. Required Average Minimum Days Off for Various Shift Cycle Schedules Group 8 Hour Shift 10 Hour Shift 12 Hour Shift Maintenance I day off/week 2 days off/week 2 days off/week Operations, Radiation Protection, 1 day off/week 2 days off/week 2.5 days off/week Chemistry Security 1 day off/week 2 days off/week 3 days off/week

2. For the purposes of calculating an average number of days off the duration of the shift cycle may not exceed six weeks nor be less than one week.
3. Online rules will be applied for a shift when any portion of the shift where the unit is defined to be online.

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 15 of 52 3.2.1 10 Code of Federal Regulations (CFR) 26 Overtime Limits (continued)

C. Outage Requirements

1. While working on an outage unit, and without issuance of a waiver, an individuals required days off shall adhere to the requirements listed in Table 2 below (not an average):

Table 2. Required Minimum of Days Off for Outages Group 8 Hour Shift 10 Hour Shift 12 Hour Shift Days Off Days Off Days Off Maintenance 1 day off per week 1 day off per week 1 day off per week Operations, Radiation Protection, 3 days off in each 3 days off in each 3 days off in each Chemistry successive (i.e., successive (i.e., successive (i.e.,

non-rolling) 15 day non-rolling) 15 day non-rolling) 15 day period period period Security 4 days off in each 4 days off in each 4 days off in each successive (i.e., successive (i.e., successive (i.e.,

non-rolling) 15 day non-rolling) 15 day non-rolling) 15 day period period period

2. Table 2 applies to the first 60 days of a unit outage; after this 60 day period expires normal online work hour limits will apply.

The 60 day period may be extended seven days on an individual basis for each 7 day block during which they worked 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or less. Multiple 7 day extensions may be given to an individual as long as the 7 day blocks are not overlapping.

3. An operator who is on outage work-hour limitations should not provide relief to the operator at the controls or the senior operator in the control room for an operating unit, unless another operator who has been on non-outage work hours Is not immediately available and the operator has had 2 days off in the preceding 7 day period. If the operator has not had 2 days off in the preceding 7 day period and no other operator who has had 2 days off is immediately available, the operator may provide short-term relief (up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) to the operator at the controls or the senior operator in the control room for an operating unit or long-term relief (more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) under a waiver of the Minimum Days Off (MDO) requirement that is applicable to the shift schedule (i.e., 8, 10, or 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts) for personnel assigned to the operating unit.
4. Contractors/vendors are responsible for tracking and reporting their hours to their supervisors between outages. The NPG is not responsible for accounting for contractor/vendor work hours prior to supporting an outage unless the contractor/vendor is coming directly from another NPG site.
5. Minimum days off may be scheduled throughout the week, or 15 day period, without restraint (i.e., does not have to be one (1) day off every five (5) days).
  • NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 16 of 52 3.2.1 10 Code of Federal Regulations (CFR) 26 Overtime Limits (continued)
6. A new shift cycle will be used at the completion of an outage. Post-outage transitions are in compliance if the unplanned outage schedule for the shift cycle would have provided for the required average days off.
7. If the interval between outages for a worker is less than nine (9) days, then the individual shall have a 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> break period and shall not exceed the following limits:
a. 16 work hours in any 24-hour period,
b. 26 work hours in any 48-hour period, and
c. 72 work hours in any 7-day period.
8. The option of keeping workers on normal online work hour restrictions is still available during outages.

3.2.2 Calculating Work Hours A. Work hour limits and the associated calculation and tracking of work hours apply to the individuals who perform covered work. This calculation includes both covered and non-covered work since the latter also contributes to fatigue.

B. Work hour accounting practices may be different from record keeping for payroll purposes or gate times.

C. Work hour records should show the number of hours worked each calendar day. Work period start and stop times should be recorded and documented in a consistent manner.

D. Included In Work Hour Calculation

1. All work, both covered and non-covered work, performed by the individual for the licensee (including hours worked while working from home)
2. Non-incidental duties (i.e., incidental duties exceeding the nominal, cumulative 30 minutes) performed off-site. The time between leaving the station and the non-incidental duty are also included if that time is less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> in duration
3. Any break time during the work period
4. Time spent at lunch
5. Call-ins (when an individual is called in to work) are considered an addition to the normal work schedule and, therefore, shall be included. The time between leaving the station and the call-in work period are also included if that time is less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> in duration
6. Shift holdovers to cover for late arrivals of incoming shift members

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 17 of 52 3.2.2 Calculating Work Hours (continued)

7. Early arrivals of individuals for licensee required meetings, training, or pre-shift briefings for special evolutions (these activities are not considered shift turnover activities)
8. Holdovers for interviews needed for event investigations E. Excluded From Work Hour Calculation
1. Either on-coming or off-going shift turnover
2. Only that portion of a break or rest period during which there is a reasonable opportunity and accommodation for restorative sleep (e.g., a nap of at least 30 minutes)
3. Incidental duties performed off-site (e.g., technical assistance by telephone from home), provided the cumulative duration of the work does not exceed a nominal 30 minutes during any single break period, may be excluded and are not considered a work period/work shift. Exceeding the nominal 30 minutes results in that time period counting as a workday.
4. Hours worked above the normal scheduled work hours for the purpose of participating in the actual conduct of an unannounced emergency preparedness exercise or drill may be excluded from the calculation of an individuals work hours. If an individual is on a day off, it is still considered a day off.
5. Paid hours during which the individual is not expected to perform work (e.g.,

vacation time, sick days, personal leave).

6. Waivers for changing to/from daylight savings time are not required 3.2.3 Work Hour Scheduling A. Work hours for covered individuals shall be scheduled with the objective of preventing impairment from fatigue due to duration, frequency, or sequencing of successive shifts.

B. Consider the following factors when establishing schedules:

1. Work hour limits defined in 10 CFR 26, Subpart I
2. Consistent start/stop times for work periods
3. Impact of backward shift rotation
4. Training requirements
5. Vacation scheduling

[NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 18 of 52 3.2.3 Work Hour Scheduling (continued)

NOTE To determine if an individual is eligible for a call-in work period use the guidelines from Steps 3.2.30 and 3.2.3D.

C. Evaluation of periodic overtime for covered individuals work hours should be performed with respect to an expected average of 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> per week.

D. Hours worked should be evaluated to determine if any limit will be exceeded based on the work schedule by a backward look at the number of hours that have or will have been worked based on a time in the future (i.e., if the individual works at time T, how many hours will he/she have worked in the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s/48 hours!7 days preceding time T relative to 10 CFR 26 work hour limits as well as minimum days off and break requirements).

E. When entering an unplanned outage, unplanned security outage or increased threat condition, compliance with 10 CER 26 work hour limits is met if the schedule for the shift cycle would have provided the required average days off.

F. Deviations from 10 CFR 26 overtime limits may occur as the result of administrative errors or unforeseen circumstances. A PER shall be initiated, in accordance with SPP-3.1, Issue Identification and Screening Process, for each individual when this occurs.

G. An individual is considered reset from deviation, whether under a waiver or otherwise, when they meet the hours worked and break requirements and have met the minimum days off requirement in the last seven (7) day period.

H. Refer to eSOMS related guidance for use of the software to perform work hour calculating and scheduling.

3.2.4 Transitions A. Non-shift workers transitioning onto a shift (e.g., non-shift SRO standing proficiency watch) shall adhere to 10 CFR 26 overtime limits and have all work (including non-covered work performed before joining the shift) included in the calculation of their work hours. If the individual joins a shift after the start of a shift cycle, they shall meet the average days off requirement going forward and the minimum days off requirement for the shift from which they have transitioned.

B. If an individual is transitioning to a different shift schedule for a long period of time, the applicable day off requirement is found by calculating the average duration of the shifts worked and to be worked during a period not more than six (6) weeks that encompasses the schedule transition. If the average shift duration is not more than nine (9) hours, then the minimum day off requirements for 8-hour shift schedules would apply. If the average shift duration is more than 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> but not more than 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> then the requirements for a 10-hour shift would apply, and so forth.

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 19 of 52 3.2.4 Transitions (continued)

C. If an individual is transitioning to a temporary shift schedule, then the individuals MDOs shall be evaluated against the average shift hours.

D. When an individual works during two or more successive outages and the interval(s) between successive outages is less than nine (9) days, then the individual must have had a 34-hour break period and have not exceeded the following limits: 16 work hours in any 24-hour period, 26 work hours in any 48-hour period, and 72 work hours in any 7-day period.

3.2.5 Accounting A. Accounting practices may be different from record keeping for payroll purposes. Work periods should be rounded con.sistently. Also, it should be noted that gate or payroll times may not be an appropriate measure of 10 CFR 26 compliance since these measures may not be representative of work activities.

B. Work hour records should show the number of hours worked each calendar day. Work period start and stop times should be recorded and documented in a consistent manner. Hours worked and start/stop times are per the scheduled shift times unless a change to work times is entered and approved.

C. The cognizant supervisor will ensure any hours worked in excess of the schedule are included into eSOMS prior to the beginning of the individuals next shift.

D. The periods of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, and 7 days are considered rolling time periods.

Rolling means the period is not re-zeroed or reset following a day off or after obtaining authorization to exceed 10 CFR 26 overtime limits. The 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, and 7 days periods do not restart after a day off; the period continues to roll.

3.2.6 Waivers A. Waivers shall be granted on an individual basis and only to address circumstances that could not have been reasonably controlled. Waivers may be granted if both of the following requirements are met:

1. The Site Vice President determines that the waiver is necessary to mitigate or prevent a condition adverse to safety, or to maintain site security, and approves the waiver.

The cognizant supervisor shall perform a face-to-face fatigue assessment on the individual and determine if there is reasonable assurance that the individual will be able to safely and competently perform assigned duties during the additional work period for which the waiver will be granted. The supervisor performing the assessment shall be trained in accordance with the requirements of 10 CFR 26.29 and 10 CFR 26.203(c) (ATIS 00074642) and shall be qualified to oversee the work (or related work) to be performed by the individual.

Fatigue assessments prior to the individual performing any work under the waiver shall be performed no more than four hours before the work activity.

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 20 of 52 3.2.6 Waivers (continued)

B. If there is no supervisor on-site who is qualified to oversee the work, the assessment may be performed by another trained supervisor who is qualified to oversee the work being performed.

C. The documented basis for a waiver must include the circumstances that necessitate the waiver, a statement of the scope of work, a time period for which the waiver is approved, and the bases for the approval of the waiver.

D. Examples of instances that would most likely meet the threshold for a waiver:

1. Risk significant SSC fails placing the unit in a shutdown LCD and maintenance crews must be held over or called in for repairs.
2. At the onset of an unplanned outage an individual, who is part of the minimum shift complement, must be held over due to relief not available.
3. Severe weather that requires hold-over of personnel.

E. Cognizant supervisors must track waivers by initiating a PER. See Attachment 2 for waiver process.

3.2.7 Fatigue Assessments A. Conditions Requiring a Fatigue Assessment

1. For Cause In response to an observed condition of impaired individual alertness creating a reasonable suspicion that an individual is not fit for duty.
a. Conduct fatigue assessment in response to an observed condition of impaired individual alertness creating a reasonable suspicion that an individual is not fit to safely and competently perform their duties, except if the condition is observed during an individuals break period.
b. A fatigue assessment need only be conducted when the observed condition is reasonably believed to be due to impaired alertness with no other behaviors or physical conditions creating a reasonable suspicion of possible substance abuse.
c. The individual who observed the condition may not conduct the fatigue assessment.
2. Self-Declaration In response to an individuals self-declaration to their supervisor that they are not fit to safely and competently perform their duties for any part of a work shift because of fatigue.

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 21 of 52 3.2.7 Fatigue Assessments (continued)

a. It is the responsibility of each individual to communicate a clear self-declaration of fatigue to their cognizant supervisor. This may be verbally initiated, when necessary, by using the statement below. A casual statement to a supervisor or fellow employee that an individual is tired is not a self-declaration. Any individual covered by the FFD program can self-declare.

By the requirements of 10 CFR 26, I believe I am too fatigued to perform the duties assigned to me and would like to make a self-declaration of fatigue.

Once an individual has made a verbal self-declaration, they must be removed, as soon as practicable, from duty and given the opportunity to complete Attachment 1,Section II. The individual must ensure their cognizant supervisor receives the form prior to the end of shift. The self-declaration is formal once an individual has submitted it to the supervisor; the cognizant supervisor completes Attachment 1, Sections III and IV.

b. Self-declarations of fatigue should be encouraged to facilitate a healthy safety conscious work environment.
c. If an individual is performing or being assessed for work under a waiver and makes a self-declaration of fatigue, the cognizant supervisor, as soon as practicable, shall stop the individual from performing any covered work and allow that individual to complete Attachment 1,Section II.
d. A self-declaration fatigue assessment shall be performed as soon as possible.
e. If the individual must continue performing the covered work until relieved, then the supervisor shall take immediate action to relieve the individual and provide oversight of the individual.
f. Following the self-declaration or relief from performing the covered work, as applicable, the cognizant supervisor:

(1) May reassign the individual to duties other than covered work, but only if the results of a fatigue assessment indicate the individual is fit to safely and competently perform those other duties.

(2) May permit or require the individual to take a break of at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> before the individual returns to performing any covered work and ensure the individual is provided safe transportation home.

(3) Conduct a fatigue assessment in response to an individuals self declaration to their supervisor that they are not fit to safely and competently perform their duties for any part of a work shift because of fatigue.

NPG Standard Fatigue Management and SPP-1 .5 Programs and Work Hour Limits Rev. 0008 Processes Page 22 of 52 3.2.7 Fatigue Assessments (continued)

g. If an individual disagrees with the results of a fatigue assessment, then the individual may request a second assessment by another trained FFD assessor. The individual may also pursue other management and oversight paths for resolution.
3. Post-event In response to events requiring post-event drug and alcohol testing as specified in 10 CFR 26.31(c).
a. Conduct a fatigue assessment in response to events requiring post-event drug and alcohol testing. (SPP-1.2)
b. Necessary medical treatment shall not be delayed in order to conduct a fatigue assessment.
c. The individual who conducts the fatigue assessment may not have:

(1) Performed or directed (on-site) the work activities during which the event occurred, (2) Performed, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before the event occurred, a fatigue assessment of the individuals who were performing or directing (on-site) the work activities during which the event occurred, and (3) Evaluated or approved a waiver of the limits for any of the individuals who were performing or directing (on-site) the work activities during which the event occurred, if the event occurred while such individuals were performing work under that waiver.

4. Follow-up To follow up after a for cause fatigue assessment or before an individual returns to work after a self-declaration resulting in a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
a. Conduct a follow-up fatigue assessment and determine the need to implement controls and conditions before permitting the individual to resume performing any duties if:

(1) A fatigue assessment was conducted for cause, or (2) After a self-declaration, the individual returned to duty following a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

(3) If no break occurs, only one assessment is required.

5. Waiver As required by Section 3.2.6, Waivers.

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008

. Processes Page 23 of 52 3.2.7 Fatigue Assessments (continued)

B. Fatigue assessments shall, at a minimum, address:

1. Acute and cumulative fatigue considering the individuals work history for at least the past 15 days. Fatigue may not be assessed solely based on the fact that an individual has not exceeded any work hour limits and has met all minimum day off requirements.
2. Potential degradations in alertness and performance due to circadian variations (particularly with respect to time of day when assessing for a waiver).
3. Potential degradations in alertness and performance to affect risk significant functions.
4. Whether any controls and conditions must be established under which the individual will be permitted to perform work.

C. Conducting a Fatigue Assessment

1. Only supervisors and FFD program personnel who are trained under 10 CFR 26.29 and 10 CFR 26.203(c) (ATIS Training Course 00074642) may conduct fatigue assessments. The fatigue assessor shall limit inquiries of the individual to information necessary to assess the required factors and review the individuals performance, if applicable.
2. Individuals shall provide complete and accurate information that may be required to address the required factors. The fatigue assessor shall limit inquiries of the individual to information necessary to assess the required factors and review the individuals performance, if applicable.
3. Fatigue assessments shall not conclude an individual is fit-for-duty solely based on the fact that the individuals work hours have not exceeded any of the work hour limits or that the individual has had the minimum breaks or minimum days off, as applicable.
4. Following a fatigue assessment, the cognizant supervisor shall determine and implement the controls and conditions, if any, which are necessary to permit the individual to resume the performance of their duties for the licensee, including the need for a break.
5. Individuals sent home in lieu or as a result of a fatigue assessment should be evaluated to determine if alternate transportation is appropriate. Personnel safety should be considered in any decision to send someone home due to fatigue.
6. Cognizant supervisors shall document the circumstances that necessitated the fatigue assessment and any controls and conditions that were implemented in Attachment 1. A copy of this record will be forwarded to and maintained by the Site Subject Matter Expert. Cognizant supervisors must track fatigue assessments by initiating a PER coded as Fatigue Rule and ensure the use of appropriate anonymity in the PER.
  • NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 24 of 52 3.2.7 Fatigue Assessments (continued)
7. Each site shall maintain fatigue assessment records for covered individuals for three years. These records shall include:
a. The conditions under which each fatigue assessment was conducted (i.e.,

self-declaration, for cause, post-event, follow-up).

b. Documentation of whether or not the individual was working on outage activities at the time of the self-declaration or condition resulting in the fatigue assessment.
c. The category of duties the individual was performing, if the individual was performing covered work at the time of the self-declaration or condition resulting in the fatigue assessment.
d. The management actions, if any, resulting from each fatigue assessment.

3.3 Fatigue Management A. Fatigue management requirements, with the exception of work hour controls, are part of the FFD Program requirements and apply to all individuals (i.e., NPG employees and contractors/vendors) who:

1. Have unescorted access to protected areas (even if their current location is not on-site), or
2. Are required to physically report to the Technical Support Center or an Emergency Operations Facility, in accordance with site Emergency Plans and procedures (even if their current location is not on-site or they do not have unescorted access). Except for covered individuals in this group, the work hour limits discussed in Step 3.2 are not applied to all emergency response personnel.

B. Personnel are required to be fit for duty. Getting sufficient rest is required to ensure a person is not subject to fatigue.

C. Personnel who make choices that result in less than adequate sleep to remain alert and avoid fatigue are not meeting their obligations.

3.4 Conflict Resolution NOTE If the individual was determined to be fit-for-duty and disagrees with this finding, the cognizant supervisor needs to consider the impact of the individual working under distress. The cognizant supervisor should engage their management to discuss options and trending.

A. All applicable individuals have the right to self-declare. Self-declarations of fatigue should be encouraged and respected.

JPM SRO A.2 Page 1 of 8 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam SRO A.2 Review and Approve a Disabled Alarm Checklist

JPM SRO A.2 Page 2 of 8 Rev. 0 SRO Job Performance Measure Task: Review and Approve a Disabled Alarm Checklist, per O-SO-55-1 and OPDP-4.

Task Number: SRO 0001230301 Task Standard: Applicant identifies that the OPDP-4-1 Disabled Alarm Checklist is NOT filled out correctly for Annunciator 1-M4-B Window Dl. Applicant DOES NOT sign package at Step 7 as approved.

Time Critical Task: YES: NO: X K/A Rating(s): 2.2.43 (3.0/3.3)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: /

Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 15 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

JPM SRO A.2 Page 3 of 8 Rev. 0 ToolslEguipmentlProcedures Needed:

OPDP- 4 (Entire Procedure)

OPDP- 4-1 (Master Copy Completed ) Attachment 1, Disabled Alarm Checklist.

1-AR-M4-B, Annunciator Response, Window Dl

REFERENCES:

Reference Title Rev No.

OPDP- 4 Annunciator Disablement 0004

JPM SRO A.2 Page 4 of 8 Rev. 0 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

I. Unit-I is in Mode 3 with a normal plant shutdown in progress per O-GO-7 Unit Shutdown from Hot Standby to Cold Shutdown.

2. The Operator-at-the-Controls (OATC) has informed you that Annunciator I-M-4B (DI), XIS-68-387 REAC LEVEL CH-I HYDRO ISOLATOR TROUBLE, has been received and that an operator has been sent to the local panel and reported that no local indication supports the alarm.
3. This alarm has been designated as an invalid alarm and the OATC has initiated OPDP-4-I Disabled Alarm Checklist and Service Request 199401.
4. You are the Unit I SRO.

INITIATING CUES:

Review the OPDP-4-I Disabled Alarm Checklist for approval. Note any and all discrepancies found during your review.

JPM SRO A.2 Page 5 of 8 Rev. 0 Job Performance Checklist:

STEPISTANDARD SATIUNSAT STEP 1: Obtain a copy of the completed instruction.

STANDARD: A copy of OPDP-4-1 Attachment 1, Disabled Alarm Checklist. SAT CUE: Provide the Applicant a copy of the completed instruction.

COMMENTS: UNSAT Start time STEP 2: DISABLED ALARM CHECKLIST block reviewed. SAT STANDARD: Applicant determines that the correct Panel Number is entered in the block.

UNSAT COMMENTS:

3TEP 3: ALARM LOCATION block is reviewed. SAT STANDARD: Applicant determines correct information is entered in the Node/Mux/PtorSER.

UNSAT COMMENTS:

STEP 4: Reviews entry in 1. Description of the alarm that is being SAT defeated.

STANDARD: Applicant determines that an adequate description of the alarm function has been entered. UNSAT COMMENTS:

NOTE to evaluator: While not a critical step a comment should be made if the candidate fails to identify the missing Service Request I Work Order.

JPM SRO A.2 Page 6 of 8 Rev. 0 Job Performance Checklist:

STEPISTANDARD SATIUNSAT STEP 5: Reviews entry in 2. Describe reason for disabling the alarm (include procedure or WO number, if applicable). SAT STANDARD: Error Discovery Inadequate I incomplete reason for disabling alarm.

UNSAT The data entered should include the Service Request number.

COMMENTS:

STEP 6: Reviews entry in 3. Description of how alarm will be disabled.

SAT STANDARD: Applicant determines that the description is adequate.

COMMENTS:

UNSAT NOTE: The NOTE preceeding step B of Appendix A states that initiation of a W.O. does not constitute in-process maintnenance.

STEP 7 Reviews entry in 4 Is a IOCFR5O 59 Review reqyired prior to Critical Step disabling alarm? (Refer to Appendix A)

SAT STANDARD: Error Discovery Incorrect block checked.

Applicant determines that a IOCFR5O.59 review is required since the alarm is NOT being disabled to support in- UNSAT process maintenance.

This step is critical because this disablement cannot take credit for maintenance that has not yet began. Therefore, a IOCFR5O.59 Review is required prior to disabling the alarm.

COMMENTS:

JPM SRO A.2 Page 7 of 8 Rev. 0 Job Performance Checklist:

STEPISTANDARD SATIUNSAT STEP 8: Reviews entry in 5. Is a IOCFR5O.59 Review required prior to SAT exceeding 90 days.(alarm disabled for maintenance)?

STANDARD: Applicant determines that a 10CFR5O.59 review would be required prior to exceeding 90 days for a maintenance UNSAT evolution.

COMMENTS:

STEP 9: Reviews entry in 6. Is a Technical Evaluation (Form OPDP Critical Step 5 required prior to disabling the alarm? (Refer to Appendix A).

SAT STANDARD: Error Discovery - Incorrect block checked.

Applicant determines that a Technical Evaluation (Form OPDP-4-5) is required since no maintenance is in progress UNSAT and the affected equipment remain in service.

This step is critical because the system remains in service with its single SER point inoperable and no in-progress maintenance. Therefore, a Technical Evaluation is required prior to disabling the alarm.

COMMENTS:

STEP 8: The candidate concludes that approval block 7 cannot be Critical Step approved as presented.

STANDARD: Applicant states that the package cannot be signed as approved until after the errors have been corrected. SAT This step is critical because the alarm cannot be legally disabled without first having a IOCFR5O.59 Review and Technical Evaluation completed. UNSAT COMMENTS:

Stop time i CUE: This concludes the JPM.

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

I. Unit-I is in Mode 3 with a normal plant shutdown in progress per O-GO-7 Unit Shutdown from Hot Standby to Cold Shutdown.

2. The Operator-at-the-Controls (OATC) has informed you that Annunciator I-M-4B (Dl), XIS68-387 REAC LEVEL CH-I HYDRO ISOLATOR TROUBLE, has been received and that an operator has been sent to the local panel and reported that no local indication supports the alarm.
3. This alarm has been designated as an invalid alarm and the OATC has initiated OPDP-4-l Disabled Alarm Checklist and Service Request 199401.
4. You are the Unit I SRO.

INITIATING CUES:

Review the OPDP-4-I Disabled Alarm Checklist for approval. Note any and all discrepancies found during your review.

TITLE OPDP-4 I /i Annunciator Disablement Rev. 0004 Page lof2l Quality Related Yes D No NPG Standard Department Procedure Effective Date 02-02-2009 Responsible Peer Team/Working Group: Operations Approved by: 0. J. Miller 2-2-09 Corporate Functional Manager Date

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 2 of 21 Revision Log Revision or Affected Change Effective Page Number Date Numbers Description of RevisionlChange 0 6/24/99 All Initial issue. Replaces PAI-2.08 (WBN),

(CCC & SSP-12.53, 0-Pl-OPS-055-00l.0 (SQN), and BEN) portions of 0-01-55 (BEN).

Later SQN Yso 6/29/99 WBN 6/30/99 Yso 8/3/99 SQN 8/6/99 1 08/03/00 2-8, 10, 12 These changes were made as a result of revisions to SPP-9.3 and 9.4. The safety assessment was eliminated in SPP-9.4. SPP-9.3 was revised to add a technical evaluation and determination that a change was safe. The wording in this SDP was revised to eliminate references to the safety assessment. (Minor/editorial changes).

2 03/01/04 All General Revision. Incorporate site-specific changes for WBN and SQN. Eliminates exclusion for 50.59 reviews for nuisance alarms or alarms occurring to known input malfunctions and clarified exclusion of 50.59 from maintenance activities to be consistent with SPP-9.4. Made Disabled Alarm Index Sheet optional to use for tracking. Deleted Index of Activities in Progress That Affect MCR Annunciators OPDP-4-4. Added Alarm Disablement Technical Evaluation OPDP-4-5.

Removed specified verification requirements from this procedure and replaced them with in accordance with SPP-10.3. Made various other enhancements.

3 12/29/08 2, 4 Revised to clarify the scope of the procedure.

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 3 of 21 Revision Log Revision or Affected Change Effective Page Number Date Numbers Description of Revision/Change 4 02/02/09 All This document has been converted from Word 95 to Word 2003 (XP) using Rev. 3.

BFPER 155697 addresses the issue of BFN Ui 3 5-11 14-Vessel Head Leakoff annunciator disablement.

19-21 Added new statement 3.1.B & C. 3.1.G reworded.

Added NOTE to 3.2 and added new 3.2.F. Added 3.5.C. Section 5.0 inserted definitions, Nuisance Alarm & Valid Alarm. Added section 6.0.

Reworked forms OPDP-4-i & OPDP-4-5. Added Appendix B.

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 4 of 21 Table of Contents 1.0 PURPOSE 5 2.0 SCOPE 5 3.0 INSTRUCTIONS 5 3.1 GENERAL REQUIREMENTS 5 3.2 Disabling an Alarm 6 3.3 Enabling an Alarm 8 3.4 Identification of Out-of-Service Annunciators 9 3.5 Review and Audit 10 4.0 RECORDS 10 4.1 QA-Records 10 4.2 Non-QA Records 10 5.0 DEFINITIONS 11 6.0 REQUIREMENTS AND REFERENCES 11 Appendix A: Technical Evaluation and 50.59 Applicability 12 Appendix B: RPV Flange Leak Case Study 14 : OPDP-4-1 - Disabled Alarm Checklist 15 : OPDP-4-2 Disabled Alarm Index Sheet (Optional)

- 17 : OPDP-4-3 Disabled Alarm Compensatory Monitoring

- 18 : OPDP-4-5 Alarm Disablement Technical Evaluation

- 19

  • NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004

. Procedure Page5of2l 1.0 PURPOSE This procedure establishes the requirements for disabling/enabling alarms, tracking disabled alarms, establishing compensatory monitoring requirements, and the use of disabled alarm identifiers on annunciator windows. This instruction also establishes the requirements for disabling of individual inputs to annunciator windows. Attachments to this instruction provide the required approvals, compensatory monitoring, instructional steps, tracking mechanism, and restoration steps for strict control of this activity.

2.0 SCOPE This procedure provides administrative instructions to control and identify the status of the control room annunciators. This instruction should not be used to circumvent the permanent design change process. It is intended to apply to alarms or alarm inputs for reasons such as the following:

  • to address nuisance alarm conditions.
  • to restore alarm functions for alarms with multiple inputs.
  • to support maintenance or testing activities.

3.0 INSTRUCTIONS 3.1 GENERAL REQUIREMENTS A. Before an annunciator can be disabled, the action must be reviewed to ensure that it will not result in an unsafe condition for equipment, personnel, or the public.

B. Before an alarm can be bypassed, the ability to monitor the condition the alarm is intended to indicate must be evaluated such that if the condition were to occur as the condition changes, Operations personnel will be made aware of the condition change in a timely fashion. A timely fashion is determined by the urgency of the operator response to the alarm.

C. Any Annunciator disablement requiring a IOCFR5O.59 review or a Technical Evaluation (as specified in Appendix A) shall have necessary paperwork completed before disabling the alarm.

D. Each alarm input to be disabled will be reviewed to determine its impact on Technical Specifications, TRM, ODCM, FSAR, EOls, Radiological Monitoring, and Environmental Evaluation equipment.

E. Verification is required for removal and replacement of alarm points associated with safety systems in accordance with SPP-1 0.3.

F. An alarm point may be temporarily placed in service to determine if the condition has cleared or if corrective maintenance was sufficient to correct the deficiency provided the steps for enabling are included in the work document.

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 6 of 21 3.1 GEN ERAL REQUIREMENTS (continued)

G. Numerous alarms receive input from multiple points, any of which may cause the alarm to annunciate. If the alarm does not have reflash (i.e., the alarm contacts are Daisy Chained in the field), other alarm contacts may be masked while the one alarm contact is in. If possible, the cause of the alarm should be determined, and the individual point removed from scan, or leads disconnected in the field to restore the alarm function from other inputs.

H. Form OPDP-4-1, Disabled Alarm Checklist shall be maintained in the Disabled Annunciator Book with a copy of the 50.59 review and Technical Evaluation (if applicable).

I. The Shift Manager/Unit Supervisor shall evaluate the acceptability of and approve any compensatory monitoring required for annunciators to be disabled.

J. If an annunciator is found to be in a failed state or inoperable, the Unit Supervisor or Shift Manager should refer to the appropriate Technical Specification and/or FSAR sections to evaluate system operability.

3.2 Disabling an Alarm NOTE Appendix B, RPV Flange Leak Case Study provides Operating Experience (OE) on inappropriate alarm disablement and should be referred to prior to starting the remainder of the procedure.

Emrloyees Disablinc Alarms A. Initiate Form OPDP-4-1 for each alarm to be disabled.

B. Determine if alarm point can be disabled by Operations:

WBN Only If at WBN, determine if alarm point can be disabled using input number by looking up (NODE/MuxfPt) on any of the following:

  • MCR Alarm Printer (Address/Real Address)
  • 47W610 series prints
  • MCR Plant SSDs Refer to SOl-55.01 for disabling instructions.

SQN Only

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure . Page7of2l 3.2 Disabling an Alarm (continued)

If at SQN, determine if alarm point can be disabled using SER number by looking up SER number in 0-SO-55-1. Refer to 0-SO-55-1 for disabling instructions.

BFN Only If at BEN, software disable functions are NOT available.

C. If alarm cannot be disabled by operations, then contact Site Engineering/System Engineer to determine a method for disabling the alarm point.

D. Complete Form OPDP-4-1, items 1-6, and submit to SM/US for review and approval.

STA/Site Engineering E. Perform Technical Evaluation using Form OPDP-4-5, if required by Appendix A.

Shift Manager/Unit Supervisor F. Ensure there is a WO to correct the problem and if the alarm is an indication of an equipment deficiency, verify a PER has been initiated.

G. Review controlling work document and ensure annunciator re-enablement is included as an action before completion.

H. Ensure 50.59 review (SPP-9.4) and Technical Evaluation (Form OPDP-4-5) are attached, if required by Appendix A.

I. If Technical Evaluation (Form OPDP-4-5) required, review Form OPDP-4-5. Evaluate compensatory monitoring required when alarm is disabled.

J. Complete Form OPDP-4-1, item 7, and if approved, sign. Ensure WO or PER initiated, as appropriate.

Designated Operator (RO/SRO)

K. When all required approvals for disabling alarm are obtained, perform the following and complete Form OPDP-4-1, Item 8:

1. Review disabling steps.
2. Initiate Compensatory Monitoring as described in Forms OPDP-4-3 and/or OPDP-4-5, if applicable.

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 8 of 21 3.2 Disabling an Alarm (continued)

3. Designate a qualified individual to disable alarm(s) using method in Form OPDP-4-1, and another individual to perform verification in accordance with SPP-1 0.3.
4. Place a disabled input indicator on each affected alarm window to indicate an input to that alarm has been disabled.
5. Sign Form OPDP-4-1, Item 8, Performed By and submit to a qualified individual to sign verification requirements.
6. If desired to use for tracking, log alarm disablement on Form OPDP-4-2, Disabled Alarm Index Sheet.
7. Log alarm disablement in the narrative log for the affected unit(s) when alarm disabled. The narrative log entry shall include alarm location, method used to disable alarm, date and time removed, justification for disablement, and Tech Spec action requirements, if applicable.
8. File the disabled alarm Form OPDP-4-1 (with Technical Evaluation and 50.59 review attached, if applicable) in Disabled Annunciator Book.
9. Notify each affected Unit and Radwaste Operator of disabled alarm for:
a. Alarms representing unit-shared systems (example: Radwaste).
b. Common annunciators.

3.3 Enabling an Alarm Employees Enabling an Alarm A. Obtain the applicable Form OPDP-4-1 from the Disabled Annunciator Book, and Review Item 1.

B. Prepare enabling steps on Form OPDP-4-1, page 2, Item 9.

C. Sign as preparer.

D. Submit Form OPDP-4-1 to the SM or Unit Supervisor for review and approval.

SM/Unit Supervisor E. Review Form OPDP-4-1, Item 9 as necessary.

F. Approve restoration of the alarm in accordance with Form OPDP-4-1.

G. Designate a qualified individual to restore alarm and another individual to perform verification in accordance with SPP-10.3

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004

, Procedure Page9of2l 3.3 Enabling an Alarm (continued)

Emjlovees Enabling Alarms H. Restore alarm in accordance with applicable operating instruction or as described in Form OPDP-4-1, Item 9.

I. Remove disabled input indicator from alarm windows which have been enabled, UNLESS there are other inputs to the affected window which remain disabled by OPDP-4 or another approved plant procedure.

J. Verify associated problem is corrected, and sign Form OPDP-4-1, Item 10.

K. Ensure a qualified individual signs verification requirements.

L. Log the enabled alarm in the affected unit(s) narrative log.

M. If used for tracking, log alarm returned to service on Form OPDP-4-2, Disabled Alarm Index Sheet.

N. Ensure Compensatory Monitoring is terminated, if applicable, and sign Form OPDP-4-1, Item 11. Attach completed Compensatory Monitoring forms (Form OPDP-4-3) to Form OPDP-4-1.

0. Transfer Form OPDP-4-1, including Technical Evaluation (Form OPDP-4-5),

IOCFR5O.59 review, and Compensatory Monitoring (Form OPDP-4-3) to Management Services 3.4 Identification of Out-of-Service Annunciators NOTES

1) This section applies to annunciators out of service due to maintenance, disabled and or nuisance alarms, or performance of ongoing maintenance or surveillance activities that are affecting the plants annunciators. Annunciators that are in alarm because of equipment malfunctions should not have indicators placed until the troubled alarm is actually being worked.
2) If a clearance is being hung to work a troubled alarm or the clearance will cause an annunciator to alarm, then an indicator should be placed in conjunction with the clearance.
3) This section does not negate the requirement to complete Form OPDP-4-1 as specified in Section 3.2.

Emrloyees Performing Activities That will Bring in Alarms A. Provide a list of affected alarms to the Unit Operator before starting work.

B. IF the annunciator is out of service due to maintenance or other abnormal condition, THEN

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 10 of 21 3.4 Identification of Out-of-Service Annunciators (continued)

Verify WO written which identifies out-of-service annunciator.

C. Ensure out-of-service indicator is placed on each applicable annunciator window.

Emiloyees Performing Activities That will Bring in Alarms D. When maintenance or surveillance activities are complete, then notify Operations to remove out-of-service indicator from affected annunciator windows.

Unit Olerator/Designee E. Remove out-of-service indicator on alarm windows which have been enabled, UNLESS there are other inputs to the affected window which remain disabled by OPDP-4 or another approved plant procedure.

3.5 Review and Audit A. The Disabled Annunciator Book is reviewed during shift turnover (OPDP-1) to ensure disabled alarms are documented as required.

B. On a monthly basis, the Disabled Annunciator Book should be audited to verify that 10CFR5O.59 reviews have been completed as required. A 10CFR50.59 review shall be completed for any annunciators disabled for maintenance which will exceed 90 days prior to the next review.

C. Every 90 days operations will conduct a critical review of the justification of the disabled alarms to challenge the following:

1. Technical adequacy
2. Monitoring plan
3. Length of time the alarm is disabled 4.0 RECORDS 4.1 QA-Records A. Disabled Alarm Checklist OPDP-4-1 B. Annunciator Disablement Technical Evaluation OPDP-4-5 4.2 Non-QA Records A. Disabled Alarm Index Sheet OPDP-4-2 B. Disabled Alarm Compensatory Measures OPDP-4-3

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 11 of 21 5.0 DEFINITIONS Disabled Input Indicator

  • BEN -A blue magnetic border labeled Disabled Alarm Input.
  • SQN-A blue dot (sticker) attached to the window with the SER point written on it.
  • WBN-An orange plastic lens cover labeled Disabled Alarm which snaps over the affected window and a blue plastic lens cover labeled Disabled Input.

Out-of-Service Indicator

  • BEN -A white magnetic border labeled Testing/Maintenance.
  • SQN-An orange sticker attached to the window.
  • WBN-A green plastic lens cover labeled Maintenance which snaps over the affected window.

Maintenance Activities Activities that restore components to their as-designed condition, including activities that implement approved design changes. Maintenance activities are not subject to 10 CFR 50.59. Maintenance activities include troubleshooting, calibration, refurbishment, maintenance-related testing, identical replacements, housekeeping and similar activities that do not permanently alter the design, performance requirements, operation or control of equipment. Maintenance activities also include temporary alterations to the facility or procedures that directly relate to and are necessary to support the maintenance. Examples of temporary alterations that support maintenance include jumpering terminals, lifting leads, placing temporary lead shielding on pipes and equipment, removal of barriers, and use of temporary blocks, bypasses, scaffolding and supports.

Nuisance Alarm An alarm that comes in repetitively due to an instrumentation problem, or maintenance activity that detracts from the operators ability to monitor and control the plant.

Valid Alarm An alarm that is actuated when the monitored parameter exceeds the setpoint or meets the intent of a setpoint (e.g. if a high pressure alarm occurs at 580# and the alarm setpoint is 600# but pressure is normally zero or close to zero, that is a valid alarm. In a similar scenario, if pressure is normally 550#, the alarm may not be valid).

6.0 REQUIREMENTS AND REFERENCES Requirements and References are contained in the OPDP-4 REQ & REF document.

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 12 of 21 Appendix A (Page 1 of 2)

Technical Evaluation and 50.59 Applicability A. When an annunciator window/input is disabled as directed/allowed in an approved plant procedure (excluding maintenance or surveillance activities, a separate 50.59 review and Technical Evaluation are not required since the procedure has ajready been reviewed and approved. The following example would be an alarm disablement per an approved plant instruction:

A system operating instruction directs or allows an alarm disablement due to abnormal conditions which are addressed (and restored) by that instruction.

NOTE The initiation and processing of a work order does NOT constitute in-process maintenance.

Refer to Section 5.0 Definitions.

B. If an annunciator window/input is disabled in support of maintenance or surveillance activities, a 50.59 review is not required UNLESS the annunciator will remain disabled for more than 90 days. If 90 days will be exceeded, a 50.59 review shall be completed prior to exceeding 90 days. A Technical Evaluation is required prior to disablement if alarm functions will be disabled for equipment remaining in service (not removed from service/inoperable for the maintenance activity).

1. The following example would be considered necessary to support maintenance activities and requires a Technical Evaluation:

. A pump is tagged with a clearance for maintenance. Its suction pressure switch will be depressurized and disabling the associated low pressure alarm will disable the alarm function for other equipment that must remain in service.

2. The following examples would be considered necessary to support maintenance activities and do not require a Technical Evaluation provided the parameter is the only input to the alarm:
  • A pump is tagged with a clearance for maintenance. Its suction pressure switch will be depressurized and the associated low pressure alarm disabled.
  • An instrument is declared inoperable, and any required LCO action(s) are entered for calibration in accordance with an approved maintenance instruction. The alarm from this instrument is disabled.

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 13 of 21 Appendix A (Page 2 of 2)

Technical Evaluation and 50.59 Applicability C. When an annunciator window/input must be disabled due to degraded or inoperable equipment with maintenance NOT in progress, a 50.59 review is required prior to disabling the alarm EXCEPT when covered by an approved plant procedure (item A). A Technical Evaluation is also required EXCEPT when covered by an approved plant procedure (item A) OR when the affected alarm function is only monitoring equipment which is inoperable/out-of-service and the alarm will be restored prior to declaring the affected equipment operable or returning it to service. The following excerpt from NEI 96-07 is an example of a degraded condition affecting multiple alarm inputs:

. A level transmitter for one Reactor Coolant Pump (RCP) lower oil reservoir failed while at power. The transmitter provides an alarm function, but not an automatic protective action function. The transmitter and associated alarm are described in the UFSAR as protective features for the RCPs, but no technical specification applies. Loss of the transmiffer does not result in the loss of operability for any technical specification equipment. The transmitter fails in a direction resulting in a continuous alarm in the control room. The alarm circuitry provides a common alarm for both the upper and lower oil reservoir circuits, so transmitter failure causes a hanging alarm and a masking of proper operation of the remaining functional transmitter. Precautionary measures are taken to monitor lower reservoir oil level as outlined in the alarm manual using available alternate means. An interim compensatory action is proposed to lift the leads (temporary change) from the failed transmitter to restore the alarm function for the remaining functioning transmitter. Lifting the leads is a compensatory action (temporary change) that is subject to 10 CFR 50.59. The 10 CFR 50.59 screening would be applied to the temporary change itself (lifted leads), not the degraded condition (failed transmitter) to determine its impact on other aspects of the facility described in the UFSAR. If screening determines that no other UFSAR-described SSCs would be affected by this compensatory action, the temporary change would screen out, i.e., not require a 10 CFR 50.59 evaluation.

D. If an annunciator window or input must be disabled for other reasons (e.g. due to actual plant parameters which are known/suspected to be at or exceeding the alarm setpoint), then a 50.59 review and Technical Evaluation are required prior to disabling the alarm, EXCEPT when covered by an approved plant procedure (item A).

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 14 of 21 Appendix B (Page 1 of 1)

RPV Flange Leak Case Study On initial restart after a 22-year idle period, BEN Ui started experiencing high Drywell (D/W) temperature alarms. These were attributed to changes in the ventilation system that occurred during the idle period. The alarm setpoints were raised to clear the alarm.

The Unit also experienced an RPV Flange leakage pressure high alarm. This was attributed to water trapped between the RPV Flange 0-rings heating up. It was actually due to a leaking inner 0-ring.

The Unit continued to experience high DIW temperature alarms and again the setpoints were raised. The high temperature alarms were not correlated to a known leaking inner RPV seal 0-ring and the possibility of an outer leaking 0-ring.

The RPV seal high pressure alarm was disabled using this procedure. The person completing the evaluation believed there were no other indications that could be used to warn the operator of degrading conditions so there were no compensatory monitoring actions specified.

The leaking RPV Flange 0-rings resulted in increased DJW unidentified leakage. The station responded to increasing leakage by forming a high impact team. Although the team made four D/W entries to find the source of the leak, the key piece of information that would have helped them, the RPV Flange seal high pressure alarm, had been disabled.

The alarm disablement process should not degrade the operators (stations) ability to detect degrading plant conditions due to conditions getting worse or detecting additional failures (the RPV seal high pressure alarm did not detect the outer 0-ring failure) and there was no monitoring to look for it.

Plant personnel did not connect the high D/W temperatures to the RPV seal high pressure or the unidentified leakage because setpoints had been raised to clear alarms and an alarm was disabled without additional monitoring.

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 15 of 21 Attachment I (Page 1 of 2)

OPDP-4-1 - Disabled Alarm Checklist DISABLED ALARM CHECKLIST DISABLED ALARM CHECKLIST ALARM LOCATION Site Unit Window Number Panel Number Node!Mux/Pt or SER/Sensor

1. Describe the function ofthis alarm (e.g. provide indication of abnormal operation, equipment failure, indication of an automatic trip, indication of loss of function):

2, Describe reason for disabling alarm/input: (Include procedure orWO number, if applicable)

3. Describe how this alarm/alarm input will be disabled:

Yes No

4. Is a 10CFR5O.59 Review required prior to disabling alarm? (Refer to Appendix A). Li Li
5. Is a 10CFR5O.59 Review required prior to exceeding 90 days (alarm disabled for Li Li maintenance)?
6. Is a Technical Evaluation (Form OPDP-4-5) required prior to disabling alarm? (Refer to Li Li Appendix A).

Prepared By:

Signature Print Name Date

7. Approval for annunciator disablement:

Yes No N/A If required, is 10CFR5O,59 Review attached? Li Li Li If required, is Technical Evaluation (Form OPDP-4-5) attached? Li Li Li If a Technical Evaluation was performed, is Compensatory Monitoring required and acceptable? Li Li Li Are steps to enable the alarm provided in the controlling work document? Li Li Li Signature (SM/US) Print Name Date This alarm must be returned to service by: N/A if not an LCO.

Date Time TVA 40745 [02-20091 Page 1 of 2 OPDP-4-1 [02-02-2009]

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 16 of 21 Attachment I (Page 2 of 2)

OPDP-4-1 - Disabled Alarm Checklist DISABLED ALARM CHECKLIST DISABLED ALARM CHECKLIST ALARM LOCATION Site Unit Window Number Panel Number Node/MuxfPt or SER/Sensor

8. This alarm has been disabled as described in Item 1 of this form and Disabled Alarm Indicators have been placed on affected alarm window(s).

Performed by:

Signature Print Name Date Time Verified By:

Signature Print Name Date Time

9. Describe actions necessary to restore annunciator to normal including post-restoration testing.

Prepared by:

Signature Print Name Date Time Reviewed &

Approved by: SM)US Signature Print Name Date Time 10 This alarm has been restored to normal and tested in accordance with Item 8 of this form and Disabled Alarm Indicator(s) associated with this alarm have been removed.

Performed by:

Signature Print Name Date Time Verified By:

Signature Print Name Date Time

11. Compensatory Monitoring of this alarm is terminated and Unit Supervisor notified. N/A if no Compensatory Monitoring required.

Signature Print Name Date Time TVA 40745 [02-2009J Page 2 of 2 OPDP-4-1 [02-02-2009]

  • NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004

. Procedure Page 17 of 21 Attachment 2 (Page 1 of 1)

OPDP-4-2 - Disabled Alarm Index Sheet (Optional)

DISABLED ALARM INDEX SHEET (OPTIONAL)

Page of ALARM Removed from Required Back in Return to ALARM Compensatory Monitoring & Service Service Service Disabled Freauencv Time Date Initials Time Date Date TVA 40746 [03-2004] Pag of I OPOP-4-2 [03-01-2004]

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 18 of 21 Attachment 3 (Page 1 ofl)

OPDP-4-3 Disabled Alarm Compensatory Monitoring DISABLED ALARM COMPENSATORY MONITORING Compensatory Monitoring required, including instrument used and frequency of action:

TIME READING INIT TIME READING INIT NOTE Attach completed Compensatory Monitoring forms to Form OPDP-4-1.

TVA 40747103-20041 Page 1 of 1 OPDP-4-3 [03-01-2004]

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 19 of 21 Attachment 4 (Page 1 of 3)

OPDP-4-5 Alarm Disablement Technical Evaluation ALARM DISABLEMENT TECHNICAL EVALUATION ALARM LOCATION Site Unit Window Number Panel Number Node/MuxIPt or SER/Sensor Describe the function of this alarm (e.g. provide indication of abnormal operation, equipment failure, indication 1

of an automatic trip, indication of loss of function):

2. Is the alarm due to:

LI Instrument malfunction LI Valid signal 3.

Describe reason for disabling alarm: (List procedure or work document number)

4. Describe how this alarm will be disabled:

What other direct or inferred indications are available to support recognition of the alarming condition?

(e.g. if a low flow alarm was disabled a pump trip alarm would be a direct indication. A component cooled by the flow high temperature alarm would be an inferred indication. If a vibration probe is faulty, a portable vibration monitor would be a direct indication. Other vibration probes on the same component would be an inferred indication):

If there are no direct or inferred indications available, are there supplemental related indications (N/A if 6

direct available) that could be used to detect degrading conditions? (e.g. if a low pressure alarm is bypassed could a high level or pressure in an interconnected system indicate a problem. If a low level alarm is bypassed, could chemistry sample of drainage paths be used to indicate a tank leak):

7. How will the operator know:
a. If the condition occurs?(for instrument problems only)
b. If the condition worsens or chanaes? (for valid sirinalst TVA 40950 [02-2009] Page 1 of 3 OPDP-4-5 [02-02-2009]

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004

. Procedure Page 20 of 21 Attachment 4 (Page 2 of 3)

OPDP-4-5 Alarm Disablement Technical Evaluation ALARM DISABLEM ENT TECHNICAL EVALUATION ALARM LOCATION Site Unit Window Number Panel Number Node/Mux/Pt or SER/Sensor Yes No N/A

8. Can Compensatory Monitoring be performed with current staffing levels LI LI LI and without impacting other required actions under normal, abnormal, or accident conditions (as applicable)? Explain.
9. Does Compensatory Monitoring require use of local indications or portable LI LI LI equipment?

If YES, identify and evaluate the potential hazardous environmental conditions expected during accident or abnormal conditions (including high radiation levels).

10. What is the frequency of monitoring and how will it be controlled? (e.g. LI recurring WiO, change to operator rounds, system engineer monitoring on a weekly bases).
11. For YES responses above, discuss why disabling the affected alarm and safety standpoint TVA 40950 [02-20091 Page 2 of 3 OPDP-4-5 [02-02-2009)

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004

. Procedure Page 21 of 21 Attachment 4 (Page 3 of 3)

OPDP-4-5 - Alarm Disablement Technical Evaluation ALARM DISABLEMENT TECHNICAL EVALUATION ALARM LOCATION Site Unit Window Number Panel Number Node/Mux/Pt or SER/Sensor

12. Identify other compensatory actions (e.g., swapping running equipment or Caution Order clearances that need to be performed to support disabling the alarm.
13. If the alarm will be disabled by lifting leads, evaluate the circuit and the proposed lift location. Discuss any adverse impacts or safety concerns identified.
14. Identify applicable FSAR sections reviewed.

15 Identify the affected annunciator response procedure(s) and other applicable procedures.

16 Are temporary revisions to existing procedures required (system operating, ARP, surveillance, maintenance) to address the disabled alarm? U YES Li NO If YES, list procedures and required revisions.

Performed By:

Signature (STA or Engineering) Print Name Date Reviewed By:

Signature (SM or US) Print Name Date TVA 40950 [02-2009] Page 3 of 3 OPDP-4-5 [02-02-2009]

OPDP-4 E NPG Standard Department Annunciator Disablement Rev. 0004 Procedure Page 15 of 21 Attachment I (Page I of2)

OPDP-4-1 - Disabled Alarm Checklist DISABLED ALARM CHECKLIST ALARM LOCATION DISABLED ALARM CHECKLIST Site Unit b I Window Num:er I-MI S9_ ZZ.

Panel Number Node/Mux/Pt or SEPJSensor operation, equ pment failure. indication Describe the function of this alarm (e g provide indication of abno-rna!

of an automatic trip, indication of loss of function):

-L] LLtv1\ C\

Tc1\ csL r

I-kvtc -Lr - c,\ic kcs Zji rp Qfr cto +\L number, if app icable)

Describe reason for disabIng alarm/input: (Include procedure or WO c o4oc cC (cLr ti 1 t Describe how this alarm/alarm input viill b disabled:

Sw 32Z J\\ c-o Yes No Is a 10CFR5O.59 Review required prior to disabling alarm? (Rea to Appendix A) LI Is a 100FR50.59 Review required prior to exceeding 90 days (alarm disabled for LI maintenance)?

Is a Technical Evaluation (Form OPDP-4-5) required prior to disabiing alarm? (Refe to LI Appendix A).

Prepared By \&

C.L T\1 1 Date Signature Print Name

7. Approval for annunciator disablement. Yes No N/A If required, is 1 OCFR5O.59 Reviev attached LI LI LI If required, is Technical Evaluation (Form OPDP-4-5) attached required and If a Technical Evaluation was performed, is Compensatory Moni:oring LI acceptable LI LI dccument? LI LI LI Are steps to enable the alarm provided in the controlling work Print Name Date Signature (SM/US)

N/A if not an LCO This alarm must be returned to service by.

Date Time Page 1 of 2 OPDP-4-1 [02-02-2009]

TVA 40745 (02-2009]

NPG Standard Annunciator Disablement OPDP-4 Department Rev. 0004 Procedure Page 16 of 21 Attachment I (Page 2 of 2)

OPDP-4-1 - Disabled Alarm Checklist DISABLED ALARM CHECKLIST DISABLED ALARM CHECKLIST ALARM LOCATION Site Unit Window Number Panel Number Node/Mux./Pt or SER/Sensor

8. This alarm has been disabled as described in Item 1 of this form and Disabled Alarm Indicators have been placed on affected alarm window(s).

Performed by:

Signature Print Name Date Time Verified By:

Signature Print Name Date Time

9. Describe actions necessary to restore annunciator to normal including post-restoration testing.

Prepared by:

Signature Print Name Date Time Reviewed &

Approved by: SM/US Signature Print Name Date Time 10 This alarm has been restored to normal and tested in accordance with Item 8 of this form and Disabled Alarm Indicator(s) associated with this alarm have been removed.

Performed by:

Signature Print Name Date Time Verified By:

Signature Print Name Date Time

11. Compensatory Monoring of this alarm is terminated and Unit Supervisor notified. N/A if no Compensatory Monitoring required.

Signature Print Name Date Time TVA 40745 [02-20091 Page 2 of 2 OPDP-4-1 [02-02-2009]

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ANNUNCIATOR RESPONSE I -AR-M4-B NIS/ROD CONTROL I-XA-55-4B Revision 28 QUALITY RELATED PREPARED/PROOFREAD BY: CECIL DYER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J. K. WILKES EFFECTIVE DATE: 07/24/09 LEVEL OF USE: CONTINOUS USE REVISION DESCRIPTION: Added notes to windows A-7, B-7 and D-4 that if LEFM is inoperable rod insertion limit alarms and ICS display are not automatically adjusted. (PER 171355 & PCR 09000845)

PERFORMANCE OF THIS PROCEDURE COULD IMPACT REACTIVITY

22 (D-1)

Source Setpoint SER 322 XIS-68-387 XIS-68-387 +/- 0.4 cubic inch of fluid REAC LEVEL CH-I HYDRO ISOLATOR TROUBLE Probable 1. Loss of water or pressure in intermediate or primary reference leg Causes of RVLIS system.

NOTE I Amber light indicates a possible leak on the transmitter side of the isolator.

NOTE 2 Red light indicates a possible leak on the RCS side of the isolator.

Corrective [1] DISPATCH operator to local panel in 690 penetration room to Actions check for leakage.

[2) EVALUATE LCO 3.3.3.7.

[3] INITIATE WO as necessary.

References 45N655-04B0, 47N668-2, 47W600-287, 47W610-68-7 SQN I-AR-M4-B Page 29 of 46 I Rev. 28

JPM A.1.a Page 1 of 6 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE ROISRO A.1.a Evaluate Overtime Restrictions

JPMA.1.a Page 2 of 6 ROISRO JOB PERFORMANCE MEASURE Task: Evaluate Overtime Restrictions Task #: (RO) 1190030301; (SRO) 3430050302 ; (SRO) 0001650302 Task Standard: The candidate identifies the need for an Overtime Limitation Exception Report on 2 occasions:

On 05/30/10 to allow exceeding 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.

On 06/04/10 to allow exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days.

Time Critical Task: YES: NO: X KIA ReferencelRatings: G 2.1.5 (2.9*/3.9)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: /

Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 10 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

JPM A.1 .a Page 3 of 6 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
2. Any UNSAT requires comments
3. Ensure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.

Tools/EquipmentlProcedures Needed:

SPP-1 .5, Fatigue Management and Work Hour Limits, Rev. 8

References:

Reference Title Rev No.

1. SPP-1 .5 Fatigue Management and Work Hour Limits 0008
2. 0-PI-OPS-000-027.0 Shift Manager Clerk Duty Station Shift Relief and 0038 Office Round Sheets.

JPMA.1.a Page 4 of 6 READ TO OPERATOR DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

You are a Licensed Operator that has worked the following schedule:

Date Hours Status Notes 05/26/10 OFF 05/27/10 OFF 05/28/10 OFF 05/29/10 0630 -2230 Normal Off Day Worked on an Off day and stayed over 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until relief arrived 05/30/10 1830-0700 Normal Work Day 30 minute turnover 05/31/10 1830-0645 Normal Work Day 15 minute turnover 06/01/10 1830-0715 Normal Work Day 45 minute turnover 06/02/10 1830-0730 Normal Work Day 60 minute turnover 06/03/10 OFF Normal Off Day 06/04/10 0630-1 845 Normal Off Day Called in to cover shift (15 minute turnover) 06/05/10 1300-1900 Normal Off Day Called in to cover shift to relieve a sick operator. (30 minute turnover) 06/06/10 A/L Normal Work Day Took Annual Leave for the shift 06/07/10 0630-1 845 Normal Work Day 15 minute turnover 06/08/10 0630-1 930 Normal Work Day 60 minute turnover 06/09/10 OFF Normal Off Day INITIATING CUES:

Determine the date(s), if any, that would exceed the Fatigue Rule and would require an Overtime Limitation Exception Report to be completed prior to you completing the identified working hours and the reason(s) for the report(s) being required.

JPMA.1.a Page 5 of 6 Job Performance Checklist:

STEP I STANDARD SAT I UNSAT STEP 1.: EvalJafé the bours ok aga1ist the requiremehts. SAT UNSAT STANDARD: Candidate identifies an Overtime Limitation Exception Report is required prior to completing the 05/30/10 shift to aVow exceeding 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> in a 48 Critical Step hour period. (shaded portion)

Shaded portion is critical because the worker would exceed 26 hrs in a 48 hr period if allowed to complete the shift on 05130110.

COMMENTS:

STEP 2 Evaluate the hours worked against thejequirements SAT UNSAT STANDARD: Candidate identifies an Overtime Limitation Exception Report is required prior to completing the 06/04/10 shift to allow exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period. Critical Step (shaded portion)

Shaded portion is critical because the worker would exceed 26 hrs in a 48 hr period if allowed to complete the shift on 05130I10.

This completes the JPM.

COMMENTS:

Stop Time

READ TO OPERATOR DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

You are a Licensed Operator that has worked the following schedule:

Date Hours Status Notes 05/26/10 OFF 05/27/10 OFF 05/28/10 OFF 05/29/10 0630 -2230 Normal Off Day Worked on an Off day and stayed over 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until relief arrived 05/30/10 1830-0700 Normal Work Day 30 minute turnover 05/31/10 1830-0645 Normal Work Day 15 minute turnover 06/01/10 1830-0715 Normal Work Day 45 minute turnover 06/02/10 1 830-0730 Normal Work Day 60 minute turnover 06/03/10 OFF Normal Off Day 06/04/10 0630-1845 Normal Off Day Called in to cover shift (15 minute turnover) 06/05/10 1300-1900 Normal Off Day Called in to cover shift to relieve a sick operator.

(30 minute_turnover) 06/06/10 NL Normal Work Day Took Annual Leave for the shift 06/07/10 0630-1845 Normal Work Day 15 minute turnover 06/08/10 0630-1930 Normal Work Day 60 minute turnover 06/09/10 OFF Normal Off Day INITIATING CUES:

Determine the date(s), if any, that would exceed the Fatigue Rule and would require an Overtime Limitation Exception Report to be completed prior to you completing the identified working hours and the reason(s) for the report(s) being required.

TITLE SPP-1.5 Fatigue Management and Rev. 0008 Work Hour Limits Page 1 of 52 Quality Related E Yes 0 No NPG Standard Programs and Processes Effective Date 06-28-2010 Responsible Peer Team/Working Group: Licensing R. M. Cook for R. M. Krich 6/18/2010 Approved by:

Corporate Functional Area Manager Date

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 14 of 52 3.2 Requirements 3.2.1 10 Code of Federal Regulations (CFR) 26 Overtime Limits A. The following limits apply to covered individuals regardless of unit status:

1. No more than 16 work hours in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period
2. No more than 26 work hours in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period
3. No more than 72 work hours in any 7 day period
4. At least a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> break between successive work periods, or an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> break when a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is necessary to accommodate a crews scheduled transition between work schedules or shifts.
5. At least a 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> break in any 9 calendar day period.

B. Online Requirements

1. During online operations and without issuance of a waiver, an individuals required average minimum days off shall adhere to the requirements listed in Table I below (averaged over the shift cycle):

Table 1. Required Average Minimum Days Off for Various Shift Cycle Schedules Group 8 Hour Shift 10 Hour Shift 12 Hour Shift Maintenance 1 day off/week 2 days off/week 2 days off/week Operations, Radiation Protection, 1 day off/week 2 days off/week 2.5 days off/week Chemistry Security 1 day off/week 2 days off/week 3 days off/week

2. For the purposes of calculating an average number of days off the duration of the shift cycle may not exceed six weeks nor be less than one week.
3. Online rules will be applied for a shift when any portion of the shift where the unit is defined to be online.

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 15 of 52 3.2.1 10 Code of Federal Regulations (CFR) 26 Overtime Limits (continued)

C. Outage Requirements

1. While working on an outage unit, and without issuance of a waiver, an individuals required days off shall adhere to the requirements listed in Table 2 below (not an average):

. Table 2. Required Minimum of Days Off for Outages Group 8 Hour Shift 10 Hour Shift 12 Hour Shift Days Off Days Off Days Off Maintenance 1 day off per week 1 day off per week 1 day off per week Operations, Radiation Protection, 3 days off in each 3 days off in each 3 days off in each Chemistry successive (i.e., successive (i.e., successive (i.e.,

non-rolling) 15 day non-rolling) 15 day non-rolling) 15 day period period period Security 4 days off in each 4 days off in each 4 days off in each successive (i.e., successive (i.e., successive (i.e.,

non-rolling) 15 day non-rolling) 15 day non-rolling) 15 day period period period

2. Table 2 applies to the first 60 days of a unit outage; after this 60 day period expires normal online work hour limits will apply.

The 60 day period may be extended seven days on an individual basis for each 7 day block during which they worked 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or less. Multiple 7 day extensions may be given to an individual as long as the 7 day blocks are not overlapping.

3. An operator who is on outage work-hour limitations should not provide relief to the operator at the controls or the senior operator in the control room for an operating unit, unless another operator who has been on non-outage work hours Is not immediately available and the operator has had 2 days off in the preceding 7 day period, If the operator has not had 2 days off in the preceding 7 day period and no other operator who has had 2 days off is immediately available, the operator may provide short-term relief (up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) to the operator at the controls or the senior operator in the control room for an operating unit or long-term relief (more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) under a waiver of the Minimum Days Off (MDO) requirement that is applicable to the shift schedule (i.e., 8, 10, or 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts) for personnel assigned to the operating unit.
4. Contractors/vendors are responsible for tracking and reporting their hours to their supervisors between outages. The NPG is not responsible for accounting for contractor/vendor work hours prior to supporting an outage unless the contractor/vendor is coming directly from another NPG site.
5. Minimum days off may be scheduled throughout the week, or 15 day period, without restraint (i.e., does not have to be one (1) day off every five (5) days).

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 16 of 52 3.2.1 10 Code of Federal Regulations (CFR) 26 Overtime Limits (continued)

6. A new shift cycle will be used at the completion of an outage. Post-outage transitions are in compliance if the unplanned outage schedule for the shift cycle would have provided for the required average days off.
7. If the interval between outages for a worker is less than nine (9) days, then the individual shall have a 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> break period and shall not exceed the following limits:
a. 16 work hours in any 24-hour period,
b. 26 work hours in any 48-hour period, and
c. 72 work hours in any 7-day period.
8. The option of keeping workers on normal online work hour restrictions is still available during outages.

3.2.2 Calculating Work Hours A. Work hour limits and the associated calculation and tracking of work hours apply to the individuals who perform covered work. This calculation includes both covered and non-covered work since the latter also contributes to fatigue.

B. Work hour accounting practices may be different from record keeping for payroll purposes or gate times.

C. Work hour records should show the number of hours worked each calendar day. Work period start and stop times should be recorded and documented in a consistent manner.

D. Included In Work Hour Calculation

1. All work, both covered and non-covered work, performed by the individual for the licensee (including hours worked while working from home)
2. Non-incidental duties (i.e., incidental duties exceeding the nominal, cumulative 30 minutes) performed off-site. The time between leaving the station and the non-incidental duty are also included if that time is less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> in duration
3. Any break time during the work period
4. Time spent at lunch
5. Call-ins (when an individual is called in to work) are considered an addition to the normal work schedule and, therefore, shall be included. The time between leaving the station and the call-in work period are also included if that time is less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> in duration
6. Shift holdovers to cover for late arrivals of incoming shift members

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 17 of 52 3.2.2 Calculating Work Hours (continued)

7. Early arrivals of individuals for licensee required meetings, training, or pre-shift briefings for special evolutions (these activities are not considered shift turnover activities)
8. Holdovers for interviews needed for event investigations E. Excluded From Work Hour Calculation
1. Either on-coming or off-going shift turnover
2. Only that portion of a break or rest period during which there is a reasonable opportunity and accommodation for restorative sleep (e.g., a nap of at least 30 minutes)
3. Incidental duties performed off-site (e.g., technical assistance by telephone from home), provided the cumulative duration of the work does not exceed a nominal 30 minutes during any single break period, may be excluded and are not considered a work period/work shift. Exceeding the nominal 30 minutes results in that time period counting as a workday.
4. Hours worked above the normal scheduled work hours for the purpose of participating in the actual conduct of an unannounced emergency preparedness exercise or drill may be excluded from the calculation of an individuals work hours. If an individual is on a day off, it is still considered a day off.
5. Paid hours during which the individual is not expected to perform work (e.g.,

vacation time, sick days, personal leave).

6. Waivers for changing to/from daylight savings time are not required 3.2.3 Work Hour Scheduling A. Work hours for covered individuals shall be scheduled with the objective of preventing impairment from fatigue due to duration, frequency, or sequencing of successive shifts.

B. Consider the following factors when establishing schedules:

1. Work hour limits defined in 10 CFR 26, Subpart I
2. Consistent start/stop times for work periods
3. Impact of backward shift rotation
4. Training requirements
5. Vacation scheduling

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 18 of 52 3.2.3 Work Hour Scheduling (continued)

NOTE To determine if an individual is eligible for a call-in work period use the guidelines from Steps 3.2.3C and 3.2.3D.

C. Evaluation of periodic overtime for covered individuals work hours should be performed with respect to an expected average of 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> per week.

D. Hours worked should be evaluated to determine if any limit will be exceeded based on the work schedule by a backward look at the number of hours that have or will have been worked based on a time in the future (i.e., if the individual works at time T, how many hours will he/she have worked in the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s/48 hours/7 days preceding time T relative to 10 CFR 26 work hour limits as well as minimum days off and break requirements).

E. When entering an unplanned outage, unplanned security outage or increased threat condition, compliance with 10 CFR 26 work hour limits is met if the schedule for the shift cycle would have provided the required average days off.

F. Deviations from 10 CFR 26 overtime limits may occur as the result of administrative errors or unforeseen circumstances. A PER shall be initiated, in accordance with SPP-3.1, Issue Identification and Screening Process, for each individual when this occurs.

G. An individual is considered reset from deviation, whether under a waiver or otherwise, when they meet the hours worked and break requirements and have met the minimum days off requirement in the last seven (7) day period.

H. Refer to eSOMS related guidance for use of the software to perform work hour calculating and scheduling.

3.2.4 Transitions A. Non-shift workers transitioning onto a shift (e.g., non-shift SRO standing proficiency watch) shall adhere to 10 CFR 26 overtime limits and have all work (including non-covered work performed before joining the shift) included in the calculation of their work hours. If the individual joins a shift after the start of a shift cycle, they shall meet the average days off requirement going forward and the minimum days off requirement for the shift from which they have transitioned.

B. If an individual is transitioning to a different shift schedule for a long period of time, the applicable day off requirement is found by calculating the average duration of the shifts worked and to be worked during a period not more than six (6) weeks that encompasses the schedule transition. If the average shift duration is not more than nine (9) hours, then the minimum day off requirements for 8-hour shift schedules would apply. If the average shift duration is more than 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> but not more than 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> then the requirements for a 10-hour shift would apply, and so forth.

NPG Standard Fatigue Management and SPP..1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 19 of 52 3.2.4 Transitions (continued)

C. If an individual is transitioning to a temporary shift schedule, then the individuals MDOs shall be evaluated against the average shift hours.

D. When an individual works during two or more successive outages and the interval(s) between successive outages is less than nine (9) days, then the individual must have had a 34-hour break period and have not exceeded the following limits: 16 work hours in any 24-hour period, 26 work hours in any 48-hour period, and 72 work hours in any 7-day period.

3.2.5 Accounting A. Accounting practices may be different from record keeping for payroll purposes. Work periods should be rounded consistently. Also, it should be noted that gate or payroll times may not be an appropriate measure of 10 CFR 26 compliance since these measures may not be representative of work activities.

B. Work hour records should show the number of hours worked each calendar day. Work period start and stop times should be recorded and documented in a consistent manner. Hours worked and start/stop times are per the scheduled shift times unless a change to work times is entered and approved.

C. The cognizant supervisor will ensure any hours worked in excess of the schedule are included into eSOMS prior to the beginning of the individuals next shift.

D. The periods of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, and 7 days are considered rolling time periods.

Rolling means the period is not re-zeroed or reset following a day off or after obtaining authorization to exceed 10 CFR 26 overtime limits. The 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, and 7 days periods do not restart after a day off; the period continues to roll.

3.2.6 Waivers A. Waivers shall be granted on an individual basis and only to address circumstances that could not have been reasonably controlled. Waivers may be granted if both of the following requirements are met:

1. The Site Vice President determines that the waiver is necessary to mitigate or prevent a condition adverse to safety, or to maintain site security, and approves the waiver.

The cognizant supervisor shall perform a face-to-face fatigue assessment on the individual and determine if there is reasonable assurance that the individual will be able to safely and competently perform assigned duties during the additional work period for which the waiver will be granted. The supervisor performing the assessment shall be trained in accordance with the requirements of 10 CFR 26.29 and 10 CFR 26.203(c) (ATIS 00074642) and shall be qualified to oversee the work (or related work) to be performed by the individual.

Fatigue assessments prior to the individual performing any work under the waiver shall be performed no more than four hours before the work activity.

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 20 of 52 3.2.6 Waivers (continued)

B. If there is no supervisor on-site who is qualified to oversee the work, the assessment may be performed by another trained supervisor who is qualified to oversee the work being performed.

C. The documented basis for a waiver must include the circumstances that necessitate the waiver, a statement of the scope of work, a time period for which the waiver is approved, and the bases for the approval of the waiver.

D. Examples of instances that would most likely meet the threshold for a waiver:

1. Risk significant SSC fails placing the unit in a shutdown LCO and maintenance crews must be held over or called in for repairs.
2. At the onset of an unplanned outage an individual, who is part of the minimum shift complement, must be held over due to relief not available.
3. Severe weather that requires hold-over of personnel.

E. Cognizant supervisors must track waivers by initiating a PER. See Attachment 2 for waiver process.

3.2.7 Fatigue Assessments A. Conditions Requiring a Fatigue Assessment

1. ForCause In response to an observed condition of impaired individual alertness creating a reasonable suspicion that an individual is not fit for duty.
a. Conduct fatigue assessment in response to an observed condition of impaired individual alertness creating a reasonable suspicion that an individual is not fit to safely and competently perform their duties, except if the condition is observed during an individuals break period.
b. A fatigue assessment need only be conducted when the observed condition is reasonably believed to be due to impaired alertness with no other behaviors or physical conditions creating a reasonable suspicion of possible substance abuse.
c. The individual who observed the condition may not conduct the fatigue assessment.
2. Self-Declaration In response to an individuals self-declaration to their supervisor that they are not fit to safely and competently perform their duties for any part of a work shift because of fatigue.
  • NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 21 of 52 3.2.7 Fatigue Assessments (continued)
a. It is the responsibility of each individual to communicate a clear self-declaration of fatigue to their cognizant supervisor. This may be verbally initiated, when necessary, by using the statement below. A casual statement to a supervisor or fellow employee that an individual is tired is not a self-declaration. Any individual covered by the FFD program can self-declare.

By the requirements of 10 CFR 26, I believe I am too fatigued to perform the duties assigned to me and would like to make a self-declaration of fatigue.

Once an individual has made a verbal self-declaration, they must be removed, as soon as practicable, from duty and given the opportunity to complete Attachment 1, Section Il. The individual must ensure their cognizant supervisor reeives the form prior to the end of shift. The self-declaration is formal once an individual has submitted it to the supervisor; the cognizant supervisor completes Attachment 1, Sections Ill and IV.

b. Self-declarations of fatigue should be encouraged to facilitate a healthy safety conscious work environment.
c. If an individual is performing or being assessed for work under a waiver and makes a self-declaration of fatigue, the cognizant supervisor, as soon as practicable, shall stop the individual from performing any covered work and allow that individual to complete Attachment 1,Section II.
d. A self-declaration fatigue assessment shall be performed as soon as possible.
e. If the individual must continue performing the covered work until relieved, then the supervisor shall take immediate action to relieve the individual and provide oversight of the individual.
f. Following the self-declaration or relief from performing the covered work, as applicable, the cognizant supervisor:

(1) May reassign the individual to duties other than covered work, but only if the results of a fatigue assessment indicate the individual is fit to safely and competently perform those other duties.

(2) May permit or require the individual to take a break of at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> before the individual returns to performing any covered work and ensure the individual is provided safe transportation home.

(3) Conduct a fatigue assessment in response to an individuals self decla ration to their supervisor that they are not fit to safely and competently perform their duties for any part of a work shift because of fatigue.

  • NPG Standard Fatigue Management and SPP-1 .5 Programs and Work Hour Limits Rev. 0008

. Processes Page 22 of 52 3.2.7 Fatigue Assessments (continued)

g. If an individual disagrees with the results of a fatigue assessment, then the individual may request a second assessment by another trained FFD assessor. The individual may also pursue other management and oversight paths for resolution.
3. Post-event In response to events requiring post-event drug and alcohol testing as specified in 10 CFR 26.31(c).
a. Conduct a fatigue assessment in response to events requiring post-event drug and alcohol testing. (SPP-1.2)
b. Necessary medical treatment shall not be delayed in order to conduct a fatigue assessment.
c. The individual who conducts the fatigue assessment may not have:

(1) Performed or directed (on-site) the work activities during which the event occurred, (2) Performed, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before the event occurred, a fatigue assessment of the individuals who were performing or directing (on-site) the work activities during which the event occurred, and (3) Evaluated or approved a waiver of the limits for any of the individuals who were performing or directing (on-site) the work activities during which the event occurred, if the event occurred while such individuals were performing work under that waiver.

4. Follow-up To follow up after a for cause fatigue assessment or before an individual returns to work after a self-declaration resulting in a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
a. Conduct a follow-up fatigue assessment and determine the need to implement controls and conditions before permitting the individual to resume performing any duties if:

(1) A fatigue assessment was conducted for cause, or (2) After a self-declaration, the individual returned to duty following a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

(3) If no break occurs, only one assessment is required.

5. Waiver As required by Section 3.2.6, Waivers.

NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 23 of 52 3.2.7 Fatigue Assessments (continued)

B. Fatigue assessments shall, at a minimum, address:

1. Acute and cumulative fatigue considering the individuals work history for at least the past 15 days. Fatigue may not be assessed solely based on the fact that an individual has not exceeded any work hour limits and has met all minimum day off requirements.
2. Potential degradations in alertness and performance due to circadian variations (particularly with respect to time of day when assessing for a waiver).
3. Potential degradations in alertness and performance to affect risk significant functions.
4. Whether any controls and conditions must be established under which the individual will be permitted to perform work.

C. Conducting a Fatigue Assessment

1. Only supervisors and FFD program personnel who are trained under 10 CFR 26.29 and 10 CFR 26.203(c) (ATIS Training Course 00074642) may conduct fatigue assessments. The fatigue assessor shall limit inquiries of the individual to information necessary to assess the required factors and review the individuals performance, if applicable.
2. Individuals shall provide complete and accurate information that may be required to address the required factors. The fatigue assessor shall limit inquiries of the individual to information necessary to assess the required factors and review the individuals performance, if applicable.
3. Fatigue assessments shall not conclude an individual is fit-for-duty solely based on the fact that the individuals work hours have not exceeded any of the work hour limits or that the individual has had the minimum breaks or minimum days off, as applicable.
4. Following a fatigue assessment, the cognizant supervisor shall determine and implement the controls and conditions, if any, which are necessary to permit the individual to resume the performance of their duties for the licensee, including the need for a break.
5. Individuals sent home in lieu or as a result of a fatigue assessment should be evaluated to determine if alternate transportation is appropriate. Personnel safety should be considered in any decision to send someone home due to fatigue.
6. Cognizant supervisors shall document the circumstances that necessitated the fatigue assessment and any controls and conditions that were implemented in Attachment 1. A copy of this record will be forwarded to and maintained by the Site Subject Matter Expert. Cognizant supervisors must track fatigue assessments by initiating a PER coded as Fatigue Rule and ensure the use of appropriate anonymity in the PER.
  • NPG Standard Fatigue Management and SPP-1.5 Programs and Work Hour Limits Rev. 0008 Processes Page 24 of 52 3.2.7 Fatigue Assessments (continued)
7. Each site shall maintain fatigue assessment records for covered individuals for three years. These records shall include:
a. The conditions under which each fatigue assessment was conducted (i.e.,

self-declaration, for cause, post-event, follow-up).

b. Documentation of whether or not the individual was working on outage activities at the time of the self-declaration or condition resulting in the fatigue assessment.
c. The category of duties the individual was performing, if the individual was performing covered work at the time of the self-declaration or condition resulting in the fatigue assessment.
d. The management actions, if any, resulting from each fatigue assessment.

3.3 Fatigue Management A. Fatigue management requirements, with the exception of work hour controls, are part of the FED Program requirements and apply to all individuals (i.e., NPG employees and contractors/vendors) who:

1. Have unescorted access to protected areas (even if their current location is not on-site), or
2. Are required to physically report to the Technical Support Center or an Emergency Operations Facility, in accordance with site Emergency Plans and procedures (even if their current location is not on-site or they do not have unescorted access). Except for covered individuals in this group, the work hour limits discussed in Step 3.2 are not applied to all emergency response personnel.

B. Personnel are required to be fit for duty. Getting sufficient rest is required to ensure a person is not subject to fatigue.

C. Personnel who make choices that result in less than adequate sleep to remain alert and avoid fatigue are not meeting their obligations.

3.4 Conflict Resolution NOTE If the individual was determined to be fit-for-duty and disagrees with this finding, the cognizant supervisor needs to consider the impact of the individual working under distress. The cognizant supervisor should engage their management to discuss options and trending.

A. All applicable individuals have the right to self-declare. Self-declarations of fatigue should be encouraged and respected.

JPM SROA.1.B Page 1 of 9 Rev. 0 SEQUOYAH NUCLEAR PLANT September2010 NRC Exam SRO A.1.B Review ECP Calculation

JPM SRQA.1.B Page 2 of 9 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Review ECP Calculation Task # 0010020101 (SRO)

KIA Ratings: 2.1.25 (3.9/4.2)

Task Standard: Prior to taking the reactor critical, verify estimated critical position calculation in accordance with 1-Sl-NUC-000-001.0, Estimated Critical Conditions.

Time Critical Task: YES: NO: X Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: /

Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 25 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

JPM SRO A.1 .B Page 3 of 9 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical Steps are identified in step SAT/UNSAT column by bold print Critical Step.
2. Any UNSAT requires comments
3. Ensure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.

Tools/EquipmentlProcedures Needed: NDR 0-Sl-NUC-000-001 .0 TI-33

REFERENCES:

Reference Title Rev No.

A 0-Sl-NUC-000-O01 .0 Estimated Critical Conditions 5 B NDR Nuclear Design Report for Sequoyah Cycle 17 Unit 1 Cycle 17 C Tl-33 Xenon Worth Calculation 25

JPM SRO A.1 .B Page 4 of 9 Rev. 0 READ TO OPERATOR Directions to Trainee:

I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. All steps shall be performed for this task When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is in Mode 3 and preparations are in progress to start up and take the reactor critical.
2. Core Average Burnup is 4000 MWD/MTU.
3. The present RCS Boron concentration is 1600 ppm.
4. Unit 1 tripped from full power at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on 09/20/2010.
5. Unit 1 had been at 100% power for 2 weeks prior to the trip.
6. The ECP procedure will be applicable from 0100 until 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on 09/27/201 0.
7. ECC bias is not applicable.

INITIATING CUES:

You are the Unit SRO and the Reactor Engineer has requested you to review 0-Sl-NUC000-001 .0, Estimated Critical Conditions, Appendix B, Data Sheet 2, ECC Calculation Using NDR Data.

1. Identify any and all errors and verify the estimated critical rod position for current conditions as applicable.

JPM SRO A.1 .B Page 5 of 9 Rev. 0 Job Performance Checklist:

STEPISTANDARD SATIUNSAT STEP 1: Determine boron concentration, core burnup, shutdown time and SAT power fraction entries are correct.

U N SAT STANDARD: SRO uses the turnover page cue sheet and verifies data correct.

COMMENTS: Start time STEP 2 btermjnephanjnsamanumf3iutoriiurnworth from cudi1Jijij topeak. SAT UNSAT STANDARD: SRO references the NDR Table 6-39 for 4000 MWD/MTU to identify that the samarium change is incorrect and identifies the Critical Step correct number to be a -385 pcm samarium change.

This step is critical to ensure ECP calculation integrity.

COMMENTS:

STEP 3: jçuIaterthechapgeinSmU corn ied woith SAT U N SAT STANDARD: SRO notes the calculation is incorrect due to the values used in Critical Step previous step and determines the corrected change in Sm/Pu worth to be -164 pcm. (+ or2 pcm)

This step is critical to ensure ECP calculation integrity.

COMMENTS:

Note: The NDR table 6-40 only shows time after trip values to 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. At 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> the value is -13 pcm.

JPM SRO A.1 .B Page 6 of 9 Rev. 0 Job Performance Checklist:

STEPISTANDARD SATIUNSAT STEP 4: Calculate Xenon worth using Tl-33 SAT UNSAT STANDARD: SRO references Tl-33 or the NDR.

COMMENTS:

STEP 5: From the NDR, determine the design critical boron concentration SAT for the cycle burnup value 4000 MWD/MTU.

UNSAT STANDARD: SRO references the NDR table 6-1 and verifies the concentration given in the reactor engineers data is correct.

COMMENTS:

STEP 6: SAT fdrje cur ebun4 and born pgtionyedçI UNSAT STANDARD: SRO uses the NDR table 6-8 to determine the Reactor Engineer read the table incorrectly. The correct worth is -6.765 pcm . Critical Step This step is critical to ensure ECP calculation integrity.

COMMENTS:

STEP 7: Determine if ECC bias is applicable. SAT UNSAT STANDARD: SRO will N/A this step per the intial conditions.

COMMENTS:

JPM SRO A.1 .B Page 7 of 9 Rev. 0 Job Performance Checklist:

STEPISTANDARD SATIUNSAT STEP 8 be en Critical and, SAT UNSAT STANDARD: SRO will determine the reactor engineerss calculation is incorrect due to incorrect differential boron worth used in the Critical Step equation. He should arrive at 737 pcm (+ or 1)

This step is critical to ensure ECP calculation integrity.

COMMENTS:

STEP 9: SAT UNSAT STANDARD: SRO will determine that the entry is incorrect based on incorrect Critical Step data input and arrive at the correct value of -573 pcm (+ or 1)-

This step is critical to ensure ECP calculation integrity.

COMMENTS:

STEP 10: Record the HZP peak Xe worth at for the current cycle burnup. SAT U N SAT STANDARD: SRO will use Table 6-38 of the NDR and determine the Reactor Engineers value is correct.

COMMENTS:

JPM SRO A.1 .B Page 8 of 9 Rev. 0 Job Performance Checklist:

STEPISTANDARD SATIUNSAT STEP 11: SAT UNSAT STANDARD: SRO interpolates data using NDR table 6-32 to determine the Reactor Engineers ECP is incorrect. The correct ECP is 138 Critical Step steps on Control Bank D. (+ or 2 steps)

This step is critical to ensure ECP calculation integrity. Stop time COMMENTS:

End Of JPM

READ TO OPERATOR Directions to Trainee:

I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit I is in Mode 3 and preparations are in progress to start up and take the reactor critical.
2. Core Average Burnup is 4000 MWD/MTU.
3. The present RCS Boron concentration is 1600 ppm.
4. Unit 1 tripped from full power at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on 09/20/2010.
5. Unit I had been at 100% power for 2 weeks prior to the trip.
6. The ECP procedure will be applicable from 0100 until 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on 09/27/2010.
7. ECC bias is not applicable.

INITIATING CUES:

You are the Unit SRO and the Reactor Engineer has requested you to review 0-SI-NUC-000-001 .0, Estimated Critical Conditions, Appendix B, Data Sheet 2, ECC Calculation Using NDR Data.

1. Identify any and all errors and verify the estimated critical rod position for current conditions as applicable.

LJOtK

-°?-1 SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-00l .0 0 Rev5 Page 22 of 42 APPENDIX B Page 5 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions

[1] Unit ECC applicable from I to Date Time Date Time

[2] DETERMINE THE FOLLOWING INFORMATION A. Present RCS Boron concentration B. Core average burnup_____________ MWDIMTU C. Date and time of shutdown.. /

Date Time D. Record average fraction of rated power for last 4 days before shutdown.

Power fraction =

E. Record the change in samarium/plutonium worth from equilibrium to peak from the HZP samarium/plutonium worth table in the NDR at the cycle burnup recorded in step 6.1.2[2JB.(Table 6-39)

Sm Worth = pcm Pu Worth = pcm

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 23 of 42 APPENDIX B Page 6 of 10 DATA SHEET 2 ECC CALCULAT ION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued F. Calculate the change in samarium/plutonium worth from equilibrium using values recorded instep 6.1.2[2jE above and the equation below. There are examples of this calculation in Appendix D.

The change in samarium/plutonium worth = [Average fraction of rated power for the last 4 days, step 6.1 .2[2]D] x

[(change in samarium worth from equilibrium to peak, step 6.1 .2[2jE) x (1 e PM 149t) + (change in plutonium worth from equilibrium to peak, step 6.1.2[2jE) x (1 e NP239

- )j t

PM149 .01305 hours 1

NP239 = .01229 hours 1

t = time since shutdown in hours = hrs

[ ] * *

(1 e°° 1305 ) + ( ) *

(i e°° 1 )j Change in Sm/Pu Worth =

Change in Sm/Pu Worth = pcm G. Calculate the Xenon worth at time t recorded in step 6.1 .2[2]F using TI-33.

Xenon worth = pcm H. From NDR determine the design critical boron concentration (ARO, HZP, No Xe, HFP Eq Sm and Pu) at the cycle burnup recorded in step 6.1.22]B.(Table 6-1)

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 24 of 42 APPENDIX B Page 7 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued)

I. From NDR determine the ARO, HZP Differential boron worth at the cycle burnup recorded in step 6.1.2[2jB and the boron concentration recorded in step 6.1.2[2]A.(Table 6-8) pcm/ppm J. Based upon the unit cycle experience with previous ECCs or deviations of predicted RCS boron with burnup, adjustments between -100 ppm and +100 ppm may be necessary to reflect any nuclear design bias due to calculational methods or B-i 0 depletion. (Refer to Appendix E for bias calculation)

ECC bias = ppm (if applicable)

NOTEI If the results of Step 6.1 .2[2]K are Negative, criticality can NOT be attained and the present RCS boron concentration needs to be reduced.

K. Calculate reactivity worth of difference between Critical Boron Concentration (ARO, HZP, No Xe, HFP Eq Sm and Pu) and present RCS boron concentration.

Present Critical boron ARO,HZP Boron Differential Difference Concentration + ECC Bias x BoronWorth B oron C oncen.

Reactivity ARO, HZP, No Xe Step 6.1.2[2]J Eq Sm (Step 6.i.2[2jH) Step6.1.2[2jl Worth STEP 6.1.2[2]A

= ppm - ppm + ppm x pcm I ppm Step 6.1.2(2)A Step 6.1.2[21H Step 6.1.2[2]J Step 6.1.2[2I

=

SON ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 25 of 42 APPENDIX B Page 8 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued)

NOTE2 Results should be negative. If results are positive, boron concentration is still too high.

L. Calculate necessary inserted reactivity worth of control banks at the present RCS boron concentration.

Inserted Control Boron Duff. Xenon Difference from Bank Reactivity =

Worth Reactivity Worth + Worth + Sm / Pu Worth (Step 6.1.2[21K) Step 6.1.2[2jG) (Step 6.1.2[2]F)

= pcm + pcm + pcm Step 6.1.2[2]K Step 6.1.2[2]G Step 6.1.2[2]F pcm M. Record HZP peak Xe worth at the cycle burnup recorded in step 6.1 .2[2jB from the NDR table of HZP equilibrium and peak Xe worth.(Table 6-38)

N. Calculate ECP rod position by interpolating between the NDR HZP integral rod worth tables with peak and no Xe using the peak Xe worth recorded in step 6.1 .2[2jM and the Xe worth recorded in step 6.1 .2[21G. Interpolate within the tables based on the integral rod worth recorded in step 6.1.2[2]L and the cycle burnup recorded in step 6.1.2[2]B.(Tables 6-32 and 6-33) steps=____________________

CO.cXac4L -

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-00l .0 0 Rev5 Page 22 of 42 APPENDIX B Page 5 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions nit I ECC applicable from 9121110i olbo to2ilL6! cOO Date Time Date Time

.DETERMINE THE FOLLOWING INFORMATION Present RCS Boron concentration \ oO 0 ppm Core average burnup j 000 MWD/MTU Date and time of shutdown. .9 Ii 0 DO Date Time Record average fraction of rated power for last 4 days before shutdown.

Power fraction = 00 Record the change in samarium/plutonium worth from equilibrium to peak from the HZP samarium/plutonium worth table in the NDR at the cycle burnup recorded in step 6.1.2{2]B.(Table 6-39)

Sm Worth = pcm Pu Worth = 2° pcm

ccck k_

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-00l .0 0 Rev5 Page 23 of 42 APPENDIX B Page 6 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA

&t2 ECC, Unit Conditions (Continued Calculate the change in samarium/plutonium worth from equilibrium using values recorded in step 6.1 2[2]E above and the equation below. There are examples of this calculation in Appendix D.

The change in samarium/plutonium worth [Average fraction of rated power for the last 4 days, step 6.1 .2[2jD] x

[(change in samarium worth from equilibrium to peak, step

- ) + (change in plutonium worth 6.1 .2[2]E) x (1 e PM149 t

from equilibrium to peak, step 6.1.2[21E)x (1 t - eNP23

) ] 9 XPM149 = .01305 hours 1

NP239 = .01229 hours 1

t = time since shutdown in hours = 1 hrs

[1 c ] [( 1_I

) *

(i e001305 [) + ( Z o9 ) *

(i e001 Change in Sm/Pu Worth =

Change in Sm/Pu Worth = S pcm Calculate the Xenon worth at time t recorded in step 6.1.2[2jF using TI-33.

Xenon worth = 0 pcm From NDR determine the design critical boron concentration (ARO, HZP, No Xe, HFP Eq Sm and Pu) at the cycle burnup recorded in step 6.1.2[2]B.(Table 6-1) fl09 ppm

Cct.

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 24 of 42 APPENDIX B Page 7 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued)

From NDR determine the ARO, HZP Differential boron worth at the cycle burnup recorded instep 6.i.2[2jB and the boron concentration recorded instep 6.1.2[2]A.(Table 6-8) pcm/ppm Based upon the unit cycle experience with previous ECCs or deviations of predicted RCS boron with burnup, adjustments between -100 ppm and +100 ppm may be necessary to reflect any nuclear design bias due to calculational methods or B-i 0 depletion. (Refer to Appendix E for bias calculation)

ECC bias = ppm (if applicable)

NOTEI If the results of Step 6.1 .2[2jK are Negative, criticality can NOT be attained and the present RCS boron concentration needs to be reduced.

Calculate reactivity worth of difference between Critical Boron Concentration (ARO, HZP, No Xe, HFP Eq Sm and Pu) and present RCS boron concentration.

Present Boron Critical boron Difference Concentration + ECC x

= Boron Concent. ARO, HZP, No Xe Step Reactivity Worth Eq Sm (Step 6.1.2[2]H)

STEP 6.1.2[2jA ftp 0 0 ppm I ppm +

A 1x ppm pcm Ippml

=

Step Step 6.1.2[21A 6.1.2[2)H Step 6.1.2[2]J Jj [Step 6.1.2[2)I j

= pcm

KEN!

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 22 of 42 APPENDIX B Page 5 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions

[1] Unit ECC applicable from 9\ZlItoi Olc to 9\v1lio I oOO Date Time Date Time

[2] DETERMINE THE FOLLOWING INFORMATION A. Present RCS Boron concentration 1D00 ppm B. Core average burnup LkDO MWD!MTU C. Date and time of shutdown. 9\t°

. o / ooQ Date Time D. Record average fraction of rated power for last 4 days before shutdown.

Power fraction = 00 E. Record the change in samarium/plutonium worth from equilibrium to peak from the HZP samarium/plutonium worth table in the NDR at the cycle burnup recorded in step 6.1 .2[2]B.(Table 6-39)

Sm Worth = 3S pcm Pu Worth = ZOI pcm

ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 SQN Rev5 0

Page 23 of 42 APPENDIX B Page 6 of 10 DATA SHEET 2 ECC CALCULATION USING NOR DATA 6.1.2 ECC, Unit Conditions (Continued F. Calculate the change in samarium/plutonium worth from equilibrium using values recorded in step 6.1.2[2]E above and the equation below. There are examples of this calculation in Appendix D.

The change in samarium/plutonium worth [Average fraction of rated power for the last 4 days, step 6.1 .2[2]D] x

[(change in samarium worth from equilibrium to peak, step 6.1 .2[2}E) x (1 e PM 149t) + (change in plutonium worth from equilibrium to peak, step 6.1 .2[2]E) x (1 e NP239

- )j t

PM149 = .01305 hours NP239 = .01229 hours 1

t = time since shutdown in hours = to hrs

[.oo j [(-38c*

) * (1_e01305

) + (2 OL ) *

(1 e001229 Change in Sm/Pu Worth =

Change in Sm/Pu Worth = 4 0

1t pcm G. Calculate the Xenon worth at time t recorded in step 6.1 .2[21F using TI-33.

Xenon worth = C pcm H. From NDR determine the design critical boron concentration (ARO, HZP, No Xe, HFP Eq Sm and Pu) at the cycle burnup recorded in step 6.1.2[2jB.(Table 6-1) ppm

\,

KY ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 SQN Rev5 0

Page 24 of 42 APPENDIX B Page 7 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued)

From NDR determine the ARO, HZP Differential boron worth at the cycle burnup recorded in step 6.1.2[2jB and the boron concentration recorded in step 6.1.2[2]A.(Table 6-8)

-cp.9t,S pcm/ppm J. Based upon the unit cycle experience with previous ECCs or deviations of predicted RCS boron with burnup, adjustments between -100 ppm and +100 ppm may be necessary to reflect any nuclear design bias due to calculational methods or B-IC depletion. (Refer to Appendix E for bias calculation)

ECC bias = N. 1 ppm (if applicable)

NOTEI If the results of Step 6.1 .2[2]K are Negative, criticality can NOT be attained and the present RCS boron concentration needs to be reduced.

K. Calculate reactivity worth of difference between Critical Boron Concentration (ARO, HZP, No Xe, HFP Eq Sm and Pu) and present RCS boron concentration.

I

= resent ARO, HZP Boron Critical boron ntial Difference Concentration + ECC Bias xDiffere BoronWorth Boron Concent. -

ARO, HZP, No Xe Step Reactivity Step6.1 .2[2]l Worth Eq Sm (Step 6.1.2[2]H)

STEP 6.1.2[2}A

+ 0 m] x pcmlppm

= ppm -

ppm Step 6.1.2[2H Step 6.1.2[2]J Step 6.1 .2[2)I Step 6.1.2[2]A

= 739 pcm

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT TECHNICAL INSTRUCTION TI-33 XENON WORTH CALCULATION Revision 25 QUALITY RELATED PREPARED BY: KATHRYN ALLEN RESPONSIBLE ORGANIZATION: Reactor Engineering APPROVED BY: MICHAEL R. HOWARD EFFECTIVE DATE: 4/22/09 VERIFICATION DATE: N/A LEVEL OF USE: REFERENCE USE

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev25 Page 2 of 29 REVISION DESCRIPTION Revised to update the Point Model Uncertainty Factors for Unit 1 Cycle 17.

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev25 Page 3of29 TABLE OF CONTENTS Page 1 of 1 Section Title Page TABLE OF CONTENTS 3

1.0 INTRODUCTION

4 1.1 Purpose 4 1.2 Scope 4

2.0 REFERENCES

4 2.1 Performance References 4 2.2 Developmental References 4 3.0 THEORY OF XENON-I 35 REACTIVITY ON CORE 5 4.0 INSTRUCTIONSIGUIDANCE 13 4.1 Methods of Obtaining Xenon 13 4.2 Xenon for Estimated Critical Boron (ECB) or Estimated Critical Condition (ECC) 14 4.3 Xenon for Shutdown Margin Calculation (SDM) 16 4.3.1 Obtain Xenon From REACTF to Use in SDM Calculation 16 4.3.2 Obtain Xenon From lCS to Use in SDM Calculation 18 4.3.3 Obtain Xenon From NDR to Use in SDM Calculation 19 4.3.4 Corrections to Xenon Worth Used in SDM Calculation 20 4.4 Xenon for Use in Reactivity Balance of 0-SO-62-7 23 5.0 RECORDS 23 APPENDIXES APPENDIX A: XENON CALCULATION DATA SHEET FOR ECB OR ECC 25 APPENDIX B: XENON CALCULATION DATA SHEET FOR SDM 26 APPENDIX C: XENON MANAGEMENT NEAR END OF CYCLE 27 APPENDIX D: UNIT 1 AND 2 POINT MODEL UNCERTAINTY FACTORS 28 APPENDIX E: CORRELATION OF XENON SOURCES TO XENON USES AND THE ASSOCIATED CORRECTIONS 29

r SQN XENON WORTH CALCULATION Tl-33 1,2 Rev25 Page 5 of 29 3.0 THEORY OF XENON-I 35 REACTIVITY ON CORE The reactivity effect of xenon (Xe)-I35 and samarium (Sm)-149 are things which occur relatively slowly and their influence is felt over periods of time ranging from hours to days and years.

- Xe-I 35 is but one of the _200 possible fission products. Its importance is a result of the fact that its microscopic absorption cross section, cYa IS 3,500,000 barns. It is of note that most isotopes, excepting the small group considered along with Xe-i 35 as nuclear poisons, have values of Ga in the range of 0.01 to 10 barns. The fact that Ga for Xe 135 is high would be of no particular consequence if there were little or no atoms of this isotope formed.

However, Xe-135 is one of the most common of all fission products. It is formed to a small extent (0.3%) as a direct fission product. The percentage indicates the number of Xe-I 35 nuclei formed per 100 fissions. The major source of Xe-135 however, is the decay by remission of iodine (l)-135, an isotope which is 1 The half-life of 1-135 is 6.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. The formed in 5.9% of all fissions .

combination of these two sources makes the total effective fission yield of Xe 135 equal to 6.2%. That is, an average of 6.2 atoms of Xe-i 35 result from each 100 fissions.

(1) Actually, tellurium-135 (Te-135), not 1-135 is the direct fission product. Te-135 decays by 1 emission to 1-135 with a two minute half-life according to the equation:

135 Te 52 531135 + f3 Since the half-life of Te-i 35 is so short, the effect of its presence is of little consequence, and most analyses assume that 1-135 is the direct fission product.

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev 25 Page 7 of 29 3.0 THEORY OF XENON-I 35 REACTIVITY ON CORE (Continued)

[1] Startup from the Xe free condition A reactor which has never run at power before, or a reactor which has been shutdown for several days is said to be in the Xe free condition.

Figure 3.2 shows the reactivity effect of xenon as such a reactor is quickly brought to full power.

EQUILIBRIUM XENON AT RATED POWER 0

z uJ 30 40 0 10 20 TIME (HOURS r

Figure 3.2: Xenon Transient after Startup from Zero Power to Full Power of a Reacto which was Initially Xenon Free

SQN XENON WORTH CALCULATION TI-33 1,2 Rev25 Page 9 of 29 3.0 THEORY OF XENON-I 35 REACTIVITY ON CORE (Continued)

The buildup of xenon to its equilibrium value from the xenon free condition at startup can be explained by referring to the diagram of xenons life history. It can be seen that most of the xenon is formed by the decay of 1-135. Although creation of significant quantities of 1-135 commences immediately upon attainment of full power, the xenon appears at a more gradual rate due to the half-life of 1-135. Then, as the amount of xenon in the core increases, the rate at which it is removed also increases (the rate at which the xenon absorbs neutrons is proportional to the quantity of xenon present as is the rate at which it decays radioactively) until finally it catches up with the rate of production and equilibrium is reached. Actually, from a theoretical standpoint, xenon equilibrium is never reached. From figure 3-2 it can be seen that xenon worth approaches its equilibrium value asymptotically. For practical purposes, xenon is so close to equilibrium after 30 or 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> that it can be considered at equilibrium.

[2] Reactor shutdown from equilibrium xenon If a reactor is shut down after having run long enough to reach equilibrium xenon, the behavior shown in figure 3-4 occurs. Sometime between 8 and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after shutdown the amount of xenon in the core, or equivalently its reactivity worth, increases to a peak value and then decays away to the xenon free condition with a half-life that eventually approaches the 9.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> half-life of Xe-I 35.

PEAK XENON EQUILIBRIUM XE AT RATE POWER 0

z w

30 40 0 10 20 TIME (HOURS)

Figure 3-4: Xenon Behavior Following Reactor Shutdown from Full Power, Equilibrium Xenon condition

SQN XENON WORTH CALCULATION TI-33 1,2 Rev 25 PaQe 11 of 29 3.0 THEORY OF XENON-135 REACTIVITY ON CORE (Continued)

[3] Reactor startup with xenon in the core Let us further pursue the case of a startup after a shutdown from power with xenon in the core. This behavior is shown in Figure 3-5. Between the time the reactor is shutdown and reaches power again, the first portion of the xenon buildup curve after shutdown (Figure 3-4) can be seen. Just as soon as the reactor returns to power, the xenon inventory begins to drop. This is due to the fact that once the reactor reaches power, xenon again begins to be removed because of neutron capture (as well as by decay). However, its rate of production has fallen off from the equilibrium value because decay during the shutdown time has depleted the 1-135 inventory. Temporarily, therefore, the rate of xenon removal exceeds the rate of production. The 1-135 inventory starts to recover immediately upon the return to power. Its half-life, however, introduces a lag of several hours before the xenon begins to recover.

Eventually, the xenon also returns to the equilibrium value for the power level in question. The initial drop in xenon inventory following a return to power is often called xenon burnout.

PEAK XENON EQUILIBRIUM XE AT RATED POWER 0

z ILl x

0 10 20 30 40 TIME (HOURS)

Figure 3-5: Xenon Behavior for Reactor Startup with Xenon in the Core

SQN XENON WORTH CALCULATION TI-33 1,2 Rev 25 Page 13of29 4.0 INSTRUCTIONS/GUIDANCE NOTE Refer to Appendix E for a correlation of xenon sources, xenon uses and necessary corrections to the xenon worth.

4.1 - Methods of Obtaining Xenon NOTE The xenon worth and/or xenon percent of full power concentration can be obtained from the sources provided below.

A. Use of REACTF REACTF is located on PC computers in the Control room or in the Reactor Engineering office. Familiarization with the Users Guide for REACTF will allow proper utilization of Xenon Calculations.

Select windows icon for REACTF or go to the appropriate directory and execute the appropriate executable file and perform calculations.

B. Use of plant computer (lOS).

Familiarization with the Operators Manual will allow proper utilization of calling up values.

Computer points of interest:

U2108-Xenon Worth pcm U2107-Xenon Concentration %

U2106-lodine Concentration %

C. Use of Nuclear Design Report (NDR)

Choose the correct value from the appropriate table based on burnup and Reactor Power, interpolation may be required. The NDR can only be used for either equilibrium reactor power or trips from equilibrium reactor power conditions. To obtain xenon percent of full power concentration, divide the xenon worth in question by the 100% reactor power xenon worth (which can be found from REACTF or the NDR).

SQN XENON WORTH CALCULATION TI-33 1,2 Rev25 Page 15 of 29 4M INSTRUCTIONS/GUIDANCE (continued) 4.2 Xenon for Estimated Critical Boron (ECB) or Estimated Critical Condition (ECC) (continued)

A. Obtain the best estimate value of xenon percent concentration of full power by either:

1. Using the value at time of trip or subcriticality from the lOS (this value can be compared to the value generated by REACTF).
2. Using REACTF by modeling the power history prior to unit going subcritical (using an initial xenon worth from steady state conditions).

B. If using REACTF to calculate ECB and/or ECC then N/A or discard Appendix A. If not using REACTF to calculate FOB and/or ECC then document xenon worth or xenon %

concentration of full power for an ECB or ECC on Appendix A.

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev 25 Page 17 of 29 4.0 INSTRUCTIONS/GUIDANCE (continued) 4.3 Xenon for Shutdown Margin Calculation (SDM) (continued) 4.3.1 Obtain Xenon From REACTF to Use in SDM Calculation (continued)

NOTE It is unlikely that the following step would be performed since if REACTF is operating one would use it to perform the SDM calculation rather then performing it by hand.

B. If xenon is taken from REACTF and used in a hand calculation for SDM using the SDM procedure then perform the following steps:

1. Execute the appropriate portion of REACT F to obtain the xenon worth for each end of the surveillance interval that calculation is being performed for.
2. Determine if PUF and/or 10% reduction in xenon worth is necessary by referring to section 4.3.4 and then find the minimum xenon worth.
3. Complete Appendix B and include with the performance of SDM procedure.

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev25 Page 19 of 29 4.0 INSTRUCTIONS/GUIDANCE (continued) 4.3 Xenon for Shutdown Margin Calculation (SDM) (continued) 4.3.3. Obtain Xenon From NDR to Use in SDM Calculation NOTE I Use of the NDR for xenon values is for equilibrium-based plant conditions.

NOTE 2 Xenon values from the NDR require no corrections (i.e. no corrections for PUF and no corrections for transient conditions).

NOTE 2 Use NDR table 6-40, 6-41, or 6-42 for the appropriate burnup to obtain the Xenon worths.

A. If xenon is taken from NDR and used in a hand calculation for SDM using the SDM procedure then perform the following steps:

1. Obtain the minimum xenon from the appropriate table of NDR (interpolation may be necessary) at plant conditions, burnup, time after plant trip or unit went subcritical, surveillance interval, and boron concentration.
2. Write the xenon worth in Appendix B and identify the method used. There is no PUF reduction or 10% reduction since the data is from equilibrium conditions, refer to section 4.3.4, thus N/A step A.3 of Appendix B.

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev25 Page 21 of29 4.0 INSTRUCTIONS/GUIDANCE (continued) 4.3 Xenon for Shutdown Margin Calculation (SDM) (continued) 4.3.4. Corrections to Xenon Worth Used in SDM Calculation (continued)

NOTE 3 Equilibrium power history is considered operating within +/-5% about a power level for the past three days. If not at equilibrium power history then it is considered a transient power history. It is important to distinguish between the two since it impacts the correction factor applied to the SDM for conservatism.

A. No correction to xenon is required for values taken from the NDR since the NDR values are calculated from a three-dimensional (3-D) model and are for equilibrium reactor conditions.

NOTE The SDM option of REACTF performs the appropriate reduction of xenon, if needed, in the program.

B. If using the computer code REACTF (refer to Flowchart

1) then:
1. If the 3-D model (equilibrium conditions/steady state tables) is being used then no corrections are required.
2. For the point model case, if the time since shutdown is less than or equal to 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> and the reactor shutdown from unsteady conditions, the calculated xenon worth will include the standard 10% FCF xenon reduction and the corresponding PUF factor if any one or more of the following conditions exist:
a. Boron dilution is expected within the surveillance interval

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev25 Page 23 of 29 4.0 INSTRUCTIONS/GUIDANCE (continued) 4.4 Xenon for Use in Reactivity Balance of 0-SO-62-7

- NOTE No corrections are applied to the Xenon used in O-SO-62-7 since a best estimate value instead of a conservative value is needed.

A. Obtain the Xenon worth from ICS or REACTF and write these values into the appropriate location of O-SO 7.

5.0 RECORDS Appendix A and/or B (with computer printouts) becomes a QA record when used and is attached to the appropriate Data Package.

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev 25 Page 25 of 29 APPENDIX A Page 1 of 1 XENON WORTH CALCULATION DATA SHEET FOR ECB OR ECC UNIT A. Mark method used and write Xenon worth or Xenon %

Concentration of Full Power and attach to ECB or ECC printout.

1. Method used:

El REACTF El Plant computer (ICS)

El Nuclear Design Report (NDR)

2. Xe worth or Xenon % Concentration of Full Power DATA BY

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev 25 Page 27 of 29 APPENDIX C Page 1 of 1 XENON MANAGEMENT NEAR END OF CYCLE Management of xenon near the end of an operating cycle (that is, RCS boron concentration 50 ppm or less) can present special challenges. Guidance for operation near end of cycle is contained in Section E (Power Coastdown at End of Life) of 0-GO-5, Normal Power Operation. The purpose of this appendix is to provide additional discussion of some of the potential difficulties associated with reactivity control and xenon management near the end of cycle (EOC).Reactor power level at any time is directly related to the reactivity balance. The primary influences on reactivity near EDO are ROS average temperature (moderator feedback) which is a function of reactor power when ROS temperature is on program, reactor power level (doppler feedback), control rod insertion, xenon worth, and RCS boron concentration until reduced near zero by dilution and demineralization. Another aspect of xenon management near EDO involves axial power stability decrease late in core life. Hence, it is important to dampen any axial flux difference oscillations early with minimal control rod motion. It is especially important near EDO to maintain as steady a reactor power level as possible (or to make any required power changes as slowly as possible, for example less than or equal to one percent per hour) in order to avoid inducing large xenon worth changes. For example, as shown in Figure 3-7, a power decrease transient causes excess xenon build in for the first few hours after the power change. Near EOC that negative reactivity might be difficult to offset with control rod motion or boron dilution which could result in further power decrease until the reactor shuts down. Thus, reactor operation can be constrained near EDC following too large or too fast a power change. Dperating Experience report DE7023 reported two large axial flux deviations at EDO following two rapid down power maneuvers that resulted in reactor shutdown in one case and reduction to 26% power for 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> in the other case to dampen xenon-induced axial power oscillations. Similarly, reactor restart following a trip near EDO (or especially during power coast down) is difficult because boron is likely to have been added to the ROS to maintain shutdown margin as xenon decays off and large dilution volumes would be needed to reduce an already low ROS boron concentration. Even after restarting, it may not be possible to reach the same reactor power as before the trip because of excess samarium build in (see Figure 3-2 of Tl-34) and difficulty removing RCS boron. Oonsequently, reactor restart following a trip during power coast down might not be advisable and should be carefully evaluated by management.

SQN XENON WORTH CALCULATION Tl-33 1,2 Rev25 Page29of29 APPENDIX E Page 1 of 1 CORRELATION OF XENON SOURCES TO XENON USES

- AND THE ASSOCIATED CORRECTIONS The following tables are to assist the user in correlating the xenon sources to xenon uses and necessary corrections to the xenon worth.

Xenon Value Sources Xenon Value Uses

1. NDR Tables A. ECB/ECC (REACTF or Hand Caic)
2. REACTF Xenon CaIc B. REACTF SDM CaIc
3. lOS Point [C. SDM Hand CaIc CORRELATION/CORRECTION MATRIX Xenon Source - Correction By Reason Reference Xenon Uses User? Section I A -

No Best Estimate Desired 4.2 2 A -

No Best Estimate Desired 4.2 3 A -

No Best Estimate Desired 4.2 IB* N/A N/A N/A 2-B No REACTF does necessary 4.3.1 .A corrections 3-B No REACTF does necessary 4.3.2.A corrections I - C No NDR is steady state, 3-D 4.3.3.A model,_Section_4.3.4.A 2 - c **

Yes (if required) Section 4.3.4.B.1, .2 and .3 4.3.1 .B 3 C - Yes (if required) Section 4.3.4.0.1 and .2 4.3.2.B

  • Not a viable option.
    • lt is unlikely that this option would be used since, if REACTF is up and running there is no need to perform a hand calculation, use REACTF.

20004-015 (09302008)

PROPRIETARY A R E IA AREVA NP Inc a, an AREVA and Siemens com pany TECHNICAL DOCUMENT Document No: 61 - 9103163 - 000 Nuclear Design Report for Sequoyah Unit 1, Cycle 17 AREVA NP INC. PROPRIETARY (AREVA NP) and is to be This document and any information contain ed herein, is the property of AREVA NP Inc.

reproduced nr copied in whole or in part. Nor may it be considered proprietary and confidential and may not be in any t and permission of AREVA NP. nor may it be used furnished to others without the express written consen been made must document and any copies that may have way that is or may be detrimental to AREVA NP. This be returned to AREVA NP upon request.

Page 1 of 161

4; AR EVA Document No.: 61-9103163-000 AREVA NP Inc.,

an ARE VA arid Siemens company PROPRIETARY NDR S1017 Tabe 6-1 ARC Critical Boron Concentration at HZP and HFP Conditions Crit.ica! BDron n, ppm Concentratio HFP Cyok Life HZP HFP (HEP EquiHbrium Xenon, (No Xenon) (HEP Egui1um Xenont vth Max. B Depletion) 0 1770 152C 150 1752 lid 11.23 500 1750 1101 1107 1000 1729 102 1093 2000 1724 1382 1104 4000 1709 1076 1120 6000 1715 1000 1157 8000 1677 10-7 1134 10000 1579 98 1025 12000 1423 7:9 844 14000 1233 530 610 16000 1033 321 377 16201 1013 300 23 18000 835 1.7 140 19180 722 0 0 21223 524 0 0 Tahe Notes:

1. *_ncXe
2. ARC
3. Eq Sm and Pu conc.ennions
4. Da:a caned on be3t est.ate EQL 16 bumup of 19300 MWdrntU (490.6i EE2I. A +/--2 ppm adjustment may be applied for each EFPD that cycle 16 ength is different from the best estimate VE!ue.
5. I-iFP Boron a 0 ppm at anproximatelu 19150 MWdmlU.
6. Critical Loron concentrations with B1C depletion are illusirative only. Tue actuai extent of B depletion is dependent upon the reactor operating history. including previous borations.

Page 79

A Document No.: 61-9103163-000 AR EVA AREVA NP Inc., PROPRIETARY anAREVA and Siemens Con Jpc7ny NDRS1C17 Table 6-8 HZP DifFerential Boron Worth HZP Differential Boron Worth, pcm/pprn Boron Burnup, ivlWd/mtU Conc 10000 12000 14000 16000 18000 19180 21223 500 1000 2000 4000 6000 8000 ppm 0

-7.707 -7.886 -8.078 -8.281 -8.408 -8.646

-7.167 -7.158 -7.188 -7.271 -7.392 -7.540 0 -7.197 -7.180 -8.000 -8.199 -8.324 -8.556

-7.086 -7.120 -7.204 -7.325 -7.472 -7.636 -7.813 200 -7.120 -7.104 -7.093 -7.928 -8.123 -8.245 -8.473

-7.058 -7.114 -7.265 -7.410 -7.571 -7.745 400 -7.051 -7.036 -7.027 -7.022 -8.170 -8.394

-7.088 -7.209 -7.352 -7.511 -7.681 -7.860 -8.051 600 -6.989 -6.975 -6.967 -6.963 -7.002 -8.319

-7.156 -7.297 -7.453 -7.620 -7.796 -7.982 -8.099

-6.932 -6.920 -6.912 -6.910 -6.950 -7.037 800 -7.245 -7.398 -7.561 -7.733 -7.916 -8.031 -8.248

-6.868 -6.861 -6.860 -6.901 -6.987 -7.105 1000 -6.879 -7.344 -7.504 -7.673 -7.852 -7.965 -8.179

-6.812 -6.812 -6.854 -6.940 -7.056 -7.193 1200 -6.830 -6.819 -7.448 -7.613 -7.790 -7.901 -8.112

-6.766 -6.809 -6.894 -7.009 -7.143 -7.291 1400 -6.783 -6.772 -6.766 -7.729 -7.839 -8.049

-6.765 -6.849 -6.962 -7.094 -7.239 -7.393 -7.555 1600 -6.738 -6.728 -6.722 -6.723 -7.780 -7.988

-6.805 -6.916 -7.045 -7.188 -7.339 -7.499 -7.671 1800 -6.695 -6.685 -6.679 -6.680 -6.722 -7.931

-6.871 -0.098 -7.138 -7.287 -7.445 -7.615 -7.723

-6.654 -6.614 -6.639 -6.639 -6.681 -6.762 2000 Table Notes:

1. HZP
2. NoXe
3. HFP Eq Sm and Pu concentrations
4. ARO Page 86

A DoDument No.: 61-9103163-000 AR EVA AREVA NP Inc.,

an ARE VA and Siemens company PROPRIETARY NDR S1C17 Table 6-32 HZP Integral Rod Worth as a Function of Steps Withdrawn and Burnup for Banks CD, CC, and CB in Overlap Steos Withdrawn HZP Inteoral Rod Worth. ocm Bank Bank Bank - Cycle Burnup, MWd/mtU CB CC CD 0 4000 10000 j 16000 21223 228 228 228 0 0 0 0 0 228 228 220 -16 -12 -13 -29 -39 228 228 212 -67 -53 -62 -130 -168 228 228 204 -129 -105 -133 -264 -323 228 228 196 -191 - -163 -217 -411 -481 228 228 188 -254 -223 -307 -557 -632 228 228 130 -314 -282 -397 -691 -766 228 228 172 -371 -340 -482 -805 -877 228 228 164 -426 -397 -562 -899 -968 228 228 156 -479 - -452 -636 -978 -1042 228 228 148 -532 -508 -705 -1042 -1102 228 228 140 -584 -563 -768 -104 -1143 228 228 132 -636 -618 -827 -1133 -1162 228 228 124 -687 -673 -880 -110 -1203 228 228 116 -737 -727 -928 -1175 -1213 228 228 108 -787 -779 -971 -11S4 -1219 228 228 100 -633 -829 -1011 -1194 -1228 228 220 92 -917 -917 -1063 -1241 -1280 228 212 84 -989 -992 -1149 -1332 -1385 228 204 76 -1056 -1000 -1216 -1451 - -1521 228 196 68 -1126 -1130 -1289 -1581 -1665 228 188 60 -1203 -1203 -1374 -1705 -1795 228 180 52 -1288 -1291 -1466 -1819 -1907 228 172 44 -1374 -1376 -1561 -1918 -2000 228 164 36 -1458 -1458 -1653 -2002 -2075 228 156 28 -1536 -1535 -1737 -2068 -2134 228 148 20 -1608 -1605 -1815 -2121 -2180 228 228 140 132 12 4

I -1672

-1729

-1669

-1728

-1884

-1945

-2163

-2197

-2216

-2244 228 128 0 -1758 -1759 -1975 -2209 -2253 228 120 0 -1790 -1795 -2005 -2217 -2258 228 112 0 -1824 -1835 -2037 -2222 -2260 228 104 0 -1859 -1876 -2070 -2229 -2265 Table Notes:

1. NoXe
2. HEP Eq Sm and Pu concentrations
3. HZP, ARO, no Xe, crMcal boron concentration for the indicated bumup
4. Rod worths based on sequential insertion with overlap Page 104

A Document No.: 61-91031 63-000 AR EVA AREVA NP Inc., PROPRIETARY an .4REVA and Siemens company NDR S1C17 on of Steps Withdrawn and Table 6-33 HZP Integral Rod Worth with Peak Xenon as a Functi Burnup for Banks CD, CC, and CB in Overlap Sleps Withdrawn HZP Integral Rod Worth, ccm Bank Bank Bank Cycle Burnup, MWdimtU CS CC CD 0 4000 J 10030 16000 21223 228 0 0 0 0 0 228 228

-23 -21 -21 -34 -46 28 228 220

-99 -90 -96 -150 -191 228 228 212

-187 -177 -199 -295 -359 228 228 204

-276 -268 -316 -443 -523 228 228 196

-361 -359 -437 -596 -674 228 228 188

-440 -444 -552 -728 -804 228 228 180

-511 -521 -655 -838 -911 228 228 172

-576 -591 -747 -928 -997 228 228 164

-635 -654 -829 -1001 -1064 228 228 156

-690 -712 -901 -1051 -1118 223 228 148

-741 -765 -964 -1108 -1158 228 223 140

-790 -814 -1016 -1143 -1187 228 228 132

-836 -860 -1058 -1166 -1204 228 228 124

-879 -902 -1089 -1178 -1211 228 228 116

-919 -941 -1114 -1185 -1215 228 228 108

-957 -977 -1136 -1194 -1223 228 228 100

-1028 -1045 -1187 -1242 -1277 228 220 92

-1094 -1111 -1257 -1339 -1388 228 212 84

-1150 -1179 -1341 -1465 -1531 223 234 76

-1231 -1252 -1435 -1593 -1679 228 196 68

-1310 -1334 -1533 -1722 -1808 223 188 60

-13j6 -142 -1531 -1829 -1913 228 180 52

-163 -152 -1724 -1921 -1998 223 172 44

-15E9 -1600 -3D9 -1995 -2065 225 164 35

-1649 -1652 -1364 -2053 -2116 226 156 28

-1722 -1756 -1949 -2099 -2155 228 148 20

-1787 -1821 -2004 -2135 -2186 228 140 12

-1341 -1577 -2ü51 -2164 -2210 228 132 4

-1866 -1902 -270 -2174 -2218 228 123 0

-1890 -1927 -2086 -2179 -2220 120 0 228 -1915 -933 -2531 -2182 -2219 228 112 0

-1941 -199 -2115 -2187 -2223 226. 104 0 Ta5le Notes:

1. Peak Xe
2. HEP Eq Sm and Pu concentrations
3. HZP, ARC no Xe, crMcai boron concentratbn for the indicated burnup
4. Rod worths based on sequential ins Drtion with overlap Page 105

A Document No.: 61-9103163-000 AR EVA AREVA NP Inc., PROPRIETARY an ARE VA and Siemens company NDR S1C17 Table 6-38 HZP Equilibrium and Peak Xenon Worth Cycle Life HZP Xenon Worth. pcm MWd/mtU Eauflibrium_________ Pcak L -3963 0 -2678 150 -2682 -3965 500 -2365 -39

-2679 -377 1000

-2675 .374 2000 4000 -2375 -3980 6000 -2695 -024 8000 -2730 -4094 10000 -2779 -4222 12000 -2838 -4391 14000 -2833 -4527 16000 -2913 -4593 16201 -2i5 -4593 18000 -2932 -4639 19180 -2948 -4580 21223 -3001 -

-4898 Table Notes:

1. ARO
2. HFP ARO critical boron concentration
3. HEP Eq Sm and Pu concertratons n resuhin3
4. Eouikbriurn is the Xe worlh. ot HZP conditions, with a Xe corce.ntmtio from HP sec, s:a;e operahon 1 e., HP Eq Xe ccncentraio: i).

n resu!tng

5. Peak s the wocn f Ye a HP conditions and a poak Xe c cr,:atio frDm the d;ay at HP condhiccs of the HFP Eq Xe concen ticuci.

Page 109

A Document No.: 61-9103163-000 AR EVA AREVA NP Inc., PROPRiETARY an AREVA and Siemens company NDR S1CI7 Table 6-39 HZP Samarium and Plutonium Worth HZP Samarium Worth, HZP Plutonium Worth, Peak Equilibrium Peak Equilibrium Cycle Life pcm MWd/mtU pcm 0 0 0 150 150 -237

-327 202 500

-346 207 1000

-357 205 2000

-385 204 4000

-415 204 6000

-435 198 8000 189 10000 -446

-476 189 12000

-512 190 14000 188 16000 -531

-531 186 15201 184 18000 -545

-552 162 19180 190 21223 -600 Table Notes:

1. ARC
2. HZP ARC critical boron concentration Page 110

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SURVEILLANCE INSTRUCTION 0-SI-N UC-000-001 .0 ESTIMATED CRITICAL CONDITIONS Revision 5 QUALITY RELATED PREPARED BY: GREGORY KNIEDLER RESPONSIBLE ORGANIZATION: REACTOR ENGINEERING APPROVED BY: GARY BAIR EFFECTIVE DATE: 11/9/2000 VERIFICATION DATE: N/A LEVEL OF USE: CONTINUOUS USE

SQN ESTIMATED CRITICAL CONDITIONS O-SI-NUC-000-OO1 .0 0 Rev5 Page 2 of 42 REVISION DESCRIPTION This revision is an intent change. Revised to allow the ECC to be terminated if ECC is off by +/->750 pcm (this is below the +/-1000 pcm Tech Spec Limit) and revised App. D to perform a Sm/Pu calculation like it is performed in App. B.

SQN ESTIMATED CRITICAL CONDITIONS O-SI-NUC-000-OO1.O 0 Rev5 Page 3 of 42 TABLE OF CONTENTS Page 1 of 2 Section Title Page TABLE OF CONTENTS 3 1.0 - INTRODUCTION 5 1.1 Purpose 5 1.2 Scope 5 1.2.1 Surveillance Tests to be Performed 5 1.2.2 Requirements Fulfilled 5 1.2.3 Modes 6 1.3 Frequency and Conditions 6

2.0 REFERENCES

6 2.1 Performance References 6 2.2 Developmental References 6 3.0 PRECAUTIONS AND LIMITATIONS 7 4.0 PREREQUISITE ACTIONS 8 5.0 ACCEPTANCE CRITERIA 9 6.0 PERFORMANCE 9 6.1 ECB and ECC Calculation 10 6.1.1 ECB, Unit Conditions 10 6.1.2 ECC, Unit Conditions 11

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 4 of 42 TABLE OF CONTENTS Page 2 of 2 Section Title Page 7.0 - POST SURVEILLANCE ACTIVITIES 13 8.0 RECORDS 13 APPENDIXES APPENDIX A: ECC CALCULATION FOLLOWING A REFUELING OUTAGE 14 APPENDIX B: DATA SHEET 1 ECB CALCULATION USING NDR DATA 18 APPENDIX C: MONITORING THE APPROACH TO CRITICALITY 28 APPENDIX D: SAMARIUM/PLUTONIUM WORTH 38 APPENDIX E: ECC AND ECB BIAS CALCULATION 42

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 RevS Page 5 of 42

1.0 INTRODUCTION

1.1 Purpose This Surveillance Instruction (SI) provides detailed steps for predicting the rod position and/or boron concentration at which core criticality will be achieved. It also provides guidance for monitoring the approach to criticality.

1.2 Scope 1.2.1 Surveillance Tests to be Performed A. Section 6.1.1 of this SI is used to Calculate the estimated critical boron concentration using data from Nuclear Design Report (NDR).

B. Section 6.1.2 of this SI is used to calculate the estimated critical rod position using data from Nuclear Design Report (NDR).

C. Appendix C of this SI is used to monitor the approach to criticality. This section will be used in conjunction with General Operating Instruction 0-GO-2, Plant Startup from Hot Standby to Reactor Critical. For initial startups following a refueling outage, Restart Test Instruction 0-RT-NUC-000-003.0, Initial Criticality will be used in lieu of Appendix C.

D. Appendix A of this SI is used to calculate the acceptance limits for a startup following a refueling outage.

1.2.2 Requirements Fulfilled A. Performance of this SI completely fulfills Technical Specifications (TS)

Surveillance Requirements (SR) 4.1 .1.1 .1 .c.

B. This SI may be used to completely fulfill TS SR 4.1.1.1.1 .b during the transition from mode 3 to mode 2 and immediately following criticality by verifying the estimated and/or actual critical condition is above the zero power rod insertion limit.

SQN ESTIMATED CRITICAL CONDITIONS O-SI-NUC-000-OO1.O 0 Rev5 Page 6 of 42 1.2.3 Modes Plant operating modes for which the surveillance requirement covered in this Instruction must be satisfied (applicable modes) and during which this Instruction can be performed (performance modes) are:

A. Applicable Modes: 2, and 3 (with shutdown banks (SID) withdrawn).

B. Performance Modes: Sections 6.1.1, 6.2.1 all Appendix C 2 and 3 (SID banks withdrawn)

Appendix A all 1.3 Frequency and Conditions A. This SI must be performed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before achieving criticality.

B. This SI may be used to verify adequate shutdown margin while withdrawing control banks by ensuring that the predicted critical control rod position is within the limits of TS LCO 3.1.3.6.

2.0 REFERENCES

2.1 Performance References A. O-GO-2, Plant Startup from Hot Standby to Reactor Critical B. O-RT-N UC-000-003.O, Initial Criticality C. TI-28, Curve Book D. TI-33, Xenon Worth Calculation E. Tl-34, Samarium Worth Calculation F. TI-44, Boron Tables G. Nuclear Design Report for the applicable Unit/fuel cycle.

H. SPP-1O.4, Reactivity Management Program I. SPP-2.4, Records Management 2.2 Developmental References A. SQN Technical Specifications B. Framatome Technical Document 64-1245312-00.

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 7 of 42 3.0 PRECAUTIONS AND LIMITATIONS A. For reactor startup, if criticality is not achieved within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the performance of this SI, another ECC calculation must be performed or existing calculation reverified. If additional performance(s) are required, the applicable section(s) must be reperformed and attached to this SI. Reperformance is not required for the first ECC calculation following a refueling outage or when the core is xenon free and the boron concentration and RCS temperature are essentially unchanged. In these cases the ECC calculation must be verified every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This procedure assumes a HZP temperature for criticality. If temperature varies greatly from HZP temperature then recover temperature before criticality.

B. Adequate shutdown margin during plant operation in mode 3 is normally verified by performing 0-SI-NUC-000-038.0, Shutdown Margin. If control bank withdrawal is anticipated (i.e., an approach to criticality), an ECC calculation is used to verify adequate shutdown margin by ensuring that the predicted critical control rod position is within the limits of TS LCO 3.1 .3.6. If this Instruction is being used to verify adequate shutdown margin, it must normally be performed at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except for the first ECC calculation following a refueling outage or when the core is xenon free and the boron concentration and RCS temperature are essentially unchanged; in these situations the ECC calculation can be verified at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> rather than reperformed.

C. When using a verified and validated computer program to calculate estimated critical rod positions or estimated critical boron concentrations, the calculative inputs should be verified to ensure the computer outputs are correct. This action may be accomplished by comparing the computer inputs with the data tables in the Nuclear Design Report to ensure they are within the range of the tables. The same method (e.g., computer calculations) should be used to determine both previous and current parameters (e.g., xenon worth) to ensure accurate estimates of reactivity changes.

D. This Instruction references data from the Nuclear Design Report (NDR). Care must be exercised to ensure the data used is for the applicable unit and is applicable to the current fuel cycle. If the NDR for the current fuel cycle is not available, other applicable vendor data may be used provided that it is documented. Care must be exercised in all cases to preserve the signs and units when reading the figures and performing the calculations. Xenon, control rods, boron, and samarium are neutron poisons and the reactivity change due to adding a poison is always negative.

E. When calculating the Estimated Critical Rod Position (ECP), the rod position must be above the HZP Rod Insertion Limits and below the Administrative Rod Withdrawal Limits (if applicable) for criticality.

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-OO1.0 0 Rev5 Page 8 of 42 3.0 PRECAUTIONS AND LIMITATIONS (Continued)

F. If the approach to criticality is suspended for an extended period of time near the point of criticality, the reactor core shall be made sufficiently subcritical to avoid an inadvertent criticality.

G. In the event of an unexplained change in reactivity during an approach to criticality, the approach to criticality shall cease and the reactor core shall be made sufficiently subcritical to prevent an inadvertent criticality. Approval of the Plant Manager or his designee is required to resume the approach to criticality.

H. Substantial Boron 10 depletion can occur after long continuous runs (i.e. 200 days or longer). Therefore, boron letdown curves should be evaluated for this phenomenon and adjustments made, particularly for fast restarts of the reactor when boron dilution would be necessary to account for xenon buildup.

I. An ECC Upper Termination Limit (UTL) of +750 pcm and an ECC Lower Termination Limit (LTL) of -750 pcm are calculated. These values are within the Upper and Lower Allowable Limits, Tech Spec limits, of +/-1000 pcm. The UTL and LTL shall be used by Reactor Engineering and Operations to determine whether an approach to critical should be terminated and a new ECC calculated. The ECC must be terminated if the Upper and Lower Allowable Limits are approached.

4.0 PREREQUISITE ACTIONS NOTE I During performance of this instruction, any IF/THEN statement may be marked N/A when the corresponding stated condition does not occur.

NOTE 2 Shutdown Banks are withdrawn per 0-GO-2 before control rod pull to critical.

[I] ENSURE Instruction to be used is a copy of the effective version, and RECORD necessary information on STS Cover Sheet.

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-0O1 .0 0 Rev5 Page 9 of 42 4.0 PREREQUISITE ACTIONS (Continued)

[2] ENSURE NDR (or other applicable vendor data) for the current fuel cycle is available.

[3] ENSURE sufficient copies of applicable sections and appendices are available. E 5.0 ACCEPTANCE CRITERIA A. The actual critical rod position must be equal to or further withdrawn than the zero power rod insertion limit and less withdrawn than the rod position that ensures a negative moderator temperature coefficient.

B. The absolute difference between the estimated critical conditions and the actual critical conditions must be less than 1000 pcm.

C. If either criteria stated above is not satisfied, the Shift Manager (SM) shall be notified and the applicable action requirement of LCO 3.1.1.1, 3.1.1.3, or 3.1 .3.6 must be satisfied.

D. If the absolute difference between the estimated critical condition and the actual critical condition is 750 pcm or greater, the basis for termination of startup or for proceeding shall be recorded on Data Sheet 0-2.

E. If the absolute difference between the estimated critical condition and the actual critical condition is greater than 500 pcm, the Reactor Engineering section shall initiate an evaluation to understand the reason for the difference and an entry shall be made into the Reactivity Management database.

6.0 PERFORMANCE NOTE I The Test Director will determine if Section 6.1.1 or 6.1.2 or Appendix A will be performed.

Appendix A performs an ECC calculation for plant startup following a refueling outage.

Only the section that is performed must be included in the data package.

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001.0 0 Rev5 Page 10 of 42 6.1 ECB and ECC Calculation NOTE 2 This section must be reperformed if criticality is not achieved within the four-hour time interval recorded in 6.1.1 [1] or 6.1.2 [1]. However, if the core is xenon free and the RCS boron concentration and RCS temperature are essentially unchanged, then the ECC calculation can be verified within the four-hour time interval recorded in step 6.1.1 [1] or 6.1.2

[1] rather than reperforming this section.

[1] PERFORM the computer program REACTF provided that the tables in the NDR (or other applicable vendor data) are used to verify the inputs to the program are within the range of the Tables, use Appendix E to determine the ECB/ECC bias,and ATTACH the output to the STS Cover Sheet, OR CONTINUE performing by hand.

6.1.1 ECB, Unit Conditions

[1] RECORD on Appendix B, Data Sheet 1 the unit and applicable time period for which the ECB calculation is being performed (four hours or less).

[2] RECORD on Appendix B, Data Sheet 1, the following parameters. LI A. RCS present boron concentration.

B. Core Average Burnup.

C. Date and Time of shutdown.

D. Average fraction of rated power for the past 4 days before shutdown.

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 11 of 42 6.1.1 ECB, Unit Conditions (Continued)

E. Record the change in samarium/plutonium worth from equilibrium to peak from the HZP Sm and Pu worth table in the NDR.(Table 6-39)

F. ECB bias(Refer to Appendix E)

G. Calculate samarium/plutonium worth in pcm from NDR. Examples in Appendix D.

H. Xenon predicted worth.

I. ARO, HZP, No Xe, HFP Eq Sm +Pu Concentration critical boron concentration from NDR at cycle burnup recorded in step 6.1.1{2]B.(Table 6-1)

J. ARO, HZP differential boron worth from NDR at cycle burnup recorded in step 6.1.1[2]B and the boron concentration recorded in step 6.1 .2[2]A(Table 6-8).

K. Desired critical control bank position.

L. Peak Xenon worth from NDR.(Table 6-38)

M. Reactivity worth of inserted rods.(Table 6-32 and 6-33)

N. Reactivity worth of combined reactivities.

0. Estimated boron equivalent of reactivity worth.

P. ECB calculated value.

Q. Make-up water or boric acid change required.

6.1.2 ECC, Unit Conditions

[1] RECORD on Appendix B, Data Sheet 2, the unit and applicable time period for which the ECC calculation is being performed (four hours or less).

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 12 of 42 6.t2 ECC, Unit Conditions (Continued)

[2] RECORD on Appendix B, Data Sheet 2, the following parameters.

A. Present RCS boron concentration.

B. Core Average Burnup.

C. Date and Time of shutdown.

D. Average fraction of rated power for the last 4 days before shutdown.

E. Record the change in samarium/plutonium worth from equilibrium to peak from the HZP Sm and Pu worth table in the NDR.(Table 6-39)

F. Calculate samarium/plutonium worth in pcm from NDR. Examples in Appendix D.

G. Xenon predicted worth.

H. ARO, HZP, No Xe, HFP Eq Sm and Pu, design critical boron concentration from NDR at cycle burnup recorded in step 6.1.2.[2]B.(Table 6-1)

I. ARO, HZP differential boron worth from NDR at cycle burnup recorded in step 6.1 .2[2]B and the boron concentration recorded in step 6.1.2[2]A.(Table 6-8)

J. ECC bias.(Refer to Appendix E)

K. Calculate boron difference worth.

L. Calculate necessary inserted rod reactivity worth.

M. Record peak HZP Xenon worth from NDR.(Table 6-38)

N. Calculate rod position from NDR.(Tables 6-32 and 6-33)

0. Determine allowable window.

P. Determine limits on control rods.

Q. Acceptance Criteria.

SQN ESTIMATED CRITICAL CONDITIONS O-SI-NUC-000-OO1 .0 0 Rev5 Page 13 of 42 6.1.2 ECC Unit Conditions (Continued)

[3] PERFORM Appendix C during the approach to criticality.

I Initials Date 7.0 - POST SURVEILLANCE ACTIVITIES

[1] COMPLETE applicable sections of STS Cover Sheet. I Initials Date 8.0 RECORDS All records shall be maintained per SPP-2.4.

SQN ESTIMATED CRITICAL CONDITIONS O-SI-NUC-000-00i.0 0 Rev5 Page 14 of 42 APPENDIX A Page 1 of 4 ECC CALCULATION FOLLOWING A REFUELING OUTAGE NOTE I The SQN ECC administrative limit of +/- 500 pcm is addressed in 0-RT-NUC-000-008.0 by the review criteria of +/- 50 ppm for the measured ARO critical boron concentration.

[I] RECORD expected date of criticality on Data Sheet A-i.

[2] RECORD on Data Sheet A-i the estimated Critical Boron Concentration (CB) and D bank position from 0-RT-NUC-000-003.0. El

[3] RECORD on Data Sheet A-i the inserted control bank D rod worth using Table 6-32 from the NDR, control bank D position in Step [2] and cycle burnup of zero. El

[4] CALCULATE on Data Sheet A-i the Upper Allowable Limit (UAL) and the Lower Allowable Limit (LAL) using the following equations:

UAL = Step [3] + 1000 pcrri LI LAL = Step [3] - 1000 pcrn LI NOTE2 If the UAL is positive then the UAL for control rod position is ARO.

[5] RECORD on Data Sheet A-i the UAL and LAL control bank D position using Table 6-32 of NDR, cycle burnup of zero, and pcm from Step [4].

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001.O 0 Rev5 Page 15 of 42 APPENDIX A Page 2 of 4 ECC CALCULATION FOLLOWING A REFUELING OUTAGE NOTE3 The following steps may be signed off during the performance of 0-RT-NUC-000-003.0.

[6] OBTAIN approval, on Data Sheet A-i, of ECP from unit ROorSRO.

[7] ENSURE all data in this section has been verified accurate within four hours of achieving criticality. LI NOTE4 These steps are performed once criticality has been achieved and Operations has stabilized reactor power.

[8] RECORD on Appendix A, Data Sheet A-i, the following conditions at time of criticality. LI A. Date and Time of criticality B. Core Average Temperature C. Control Bank position D. Boron concentration

[9] CHECK appropriate box on Appendix A, Data Sheet A-i, to indicate whether the following acceptance criteria is satisfied:

Acceptance Criteria Actual criticality control bank position step [8]C is within the +/- 1000 pcm limits of step [5]?

[10] IF acceptance criteria in step [9] was not satisfied, THEN IMMEDIATELY NOTIFY the SM that the action requirement of LCO 3.1 .1.1 must be satisfied.

SQN ESTIMATED CRITICAL CONDITIONS O-SI-NUC-000-0O1.O 0 Rev5 Page 16 of 42 APPENDIX A Page 3 of 4 ECC CALCULATION FOLLOWING A REFUELING OUTAGE Unit DATA SHEET A-I ECC CALCULATION FOLLOWING A REFUELING OUTAGE ECC UPPER AND LOWER TS ACCEPTANCE LIMITS

[I] Criticality expected Date

[2] ECC CB = ppm with D bank at steps.

[3] Inserted control bank D Rodworth (Negative Value) pcm

[4] UAL = Step [3] + 1000 pcrn= + 1000 pcm UAL = pcm LAL = Step [3] -1000 pcm = -1000 pcm =

LAL = pcm

[5] UAL control bank D position = steps.

LAL control bank position = steps.

[6] Approval of ECC I

Unit RO or SRO Date

[7] ECC verified accurate within four hours of criticality.

I Test Director Date

SQN ESTIMATED CRITICAL CONDITIONS O-SI-NUC-000-OO1.O 0 Rev5 Page 17 of 42 APPENDIX A Page 4 of 4 ECC CALCULATION FOLLOWING A REFUELING OUTAGE Unit_______________

DATA SHEET A-I (Continued)

ECC CALCULATION FOLLOWING A REFUELING OUTAGE ECC UPPER AND LOWER TS ACCEPTANCE LIMITS NOTE 5 These steps are performed after criticality.

[8]

A. Date and Time of criticality Date Time B. Core average Temperature C. Control Bank Position C/D at / steps D. Critical Boron Concentration CB

[9] CHECK appropriate box to indicate whether the following acceptance criteria is satisfied.

Acceptance Criteria Actual Critical control bank position step [8]C is within the +/- 1000 pcm limits, step [5]? LlYes LINo

/

Test Director Date

[10] IF acceptance criteria in step [9] was not satisfied, THEN IMMEDIATELY NOTIFY the SM that the action requirement of LCO 3.1.1.1 must be satisfied.

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001.0 0 Rev5 Page 18 of 42 APPENDIX B Page 1 of 10 DATA SHEET I ECB CALCULATION USING NDR DATA 6.1.1 ECB, Unit Conditions

[1] Unit ECB applicable from I to I Date Time Date Time

[2] DETERMINE THE FOLLOWING INFORMATION A. Present RCS Boron concentration B. Core average burnup MWDIMTU C. Record Date and time of shutdown. /

Date Time D. Average fraction of rated power for the last 4 days before shutdown.

Power Fraction =

E. Record the change in samarium! plutonium worth from equilibrium to peak from the HZP samarium/plutonium worth table(Table 6-39)in the NDR at the cycle burnup recorded in step 6.1.1[2]B.

SM Worth = pcm PU Worth = pcm F. ECB bias adjustments between -100 ppm and +100 ppm may be necessary to reflect any nuclear design bias due to calculational methods or B-b depletion.(Referto Appendix E for bias calculation)

ECB bias = applicable)

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001.0 0 Rev5 Page 19 of 42 APPENDIX B Page 2 of 10 DATA SHEET I ECB CALCULATION USING NOR DATA 6.1.1 ECB, Unit Conditions (Continued)

G. Calculate the change in samarium/plutonium worth from equilibrium using values recorded in step 6.1.1[2]E above and the equation below. There are examples of this calculation in Appendix D.

The change in samarium/plutonium worth = [Average fraction of rated power for the last 4 days, step 6.1 .1[2]D] x [(change in samarium worth from equilibrium to peak, step 6.1 .1[2jE) x (1 e PMI49t) + (change in plutonium worth from equilibrium to peak, step 6.1.1{2]E) x (1 e NP239

- )]

t Where: xPM149 = .01305 hours 1

NP239 = .01229 hours 1

t = time since shutdown in hours =

Change in Sm/Pu Worth =

) ( )

{___________

(i e°° 1305 +

e°° )j Change in Sm/Pu Worth = pcm H. Calculate the Xenon worth at time t recorded in step 6.1.1[2}G using TI-33.

Xenon worth = pcm ARO, HZP, No Xe, HFP Eq Sm and Pu critical boron concentration from NDR at the cycle burnup recorded in step 6.1.1.[2]B.(Table 6-1) ppm J. From NDR determine the ARO, HZP Differential boron worth at the cycle burnup recorded in step 6.1.1 .[2]B and the boron concentration recorded in step 6.1 .1[2]A.(Table 6-8) pcm/ppm

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 20 of 42 APPENDIX B Page 3 of 10 DATA SHEET I ECB CALCULATION USING NDR DATA 6.1.1 ECB, Unit Conditions (Continued)

NOTEI The selected bank D position should normally be between 140 and 160 steps withdrawn to minimizes RPI inaccuracy, depending on Xenon transient and other factors.

K. Select desired critical control bank position:

steps withdrawn on Control bank D.

L. Record HZP peak Xe worth at the cycle burnup recorded in step 61 .1 [2}B from the NDR table of HZP equilibrium and peak Xe worth.(Table 6-38) pcm M. Calculate reactivity worth of inserted rods by interpolating between the NDR HZP integral rod worth tables with peak and no Xe using the peak Xe worth recorded in step 6.1.1 [2]L and the Xe worth recorded in step 6.1.1 [2]H.

Interpolate within the tables based on the control rod position recorded in step 6.1.1[2]K and the cycle burnup recorded in step 6.1.1[2]B.(Tables 6-32 and 6-33)

Inserted Control Bank Worth = pcm N. Calculate combined reactivity worth of Xenon (step 6.1.1[2]H), samarium/plutonium worth (step 6.1.1[2]G) and desired critical control bank position 6.1 .1 [2]M):

Combined Xe Reactivity Samarium! Inserted Control Reactivity = Worth + PlutoniumWorth + Bank Worth Worth Step 6.1 .1[2]H Step 6.1 .1[2]G Step 6.1 .1[2]M

= + +

=

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 21 of42 APPENDIX B Page 4 of 10 DATA SHEET I ECB CALCULATION USING NDR DATA 6.1.1 ECB, Unit Conditions (Continued)

0. Calculate the estimated boron equivalent of the combined reactivity worth:

Combined Reactivity Worth Estimated Step 6.1.1[2]N Boron =

Equivalent Differential Boron Worth Step 6.1.1[2]J ppm P. Calculate estimated critical RCS boron concentration (ECB):

Design ARO,HZP, Critical Estimated ECB = Boron Concentration Boron Equivalent STEP 6.1.1[2}I STEP 6.1.1[2]O ECB = ppm + ppm - ppm ECB = ppm Q. Determine amount of makeup water or boric acid to change the RCS boron from the boron concentration of step 6.1.1 {2]A to the ECB of Step 6.1.1 [2]P using TI-44 or REACTF program.

Water/boric acid gal circle one Calculated by Date/Time Verified by Date/Time

SQN ESTIMATED CRITICAL CONDITIONS 0-Sl-NUC-000-001 .0 0 Rev5 Page 22 of 42 APPENDIX B Page 5 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions

[1] Unit ECC applicable from / to Date Time Date Time

[2] DETERMINE THE FOLLOWING INFORMATION A. Present RCS Boron concentration B. Core average burnup____________ MWDIMTU C. Date and time of shutdown.. /

Date Time D. Record average fraction of rated power for last 4 days before shutdown.

Power fraction =

E. Record the change in samarium/plutonium worth from equilibrium to peak from the HZP samarium/plutonium worth table in the NDR at the cycle burnup recorded in step 6.1.2[2]B.(Table 6-39)

Sm Worth = pcm Pu Worth = pcm

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 23 of 42 APPENDIX B Page 6 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued F. Calculate the change in samarium/plutonium worth from equilibrium using values recorded in step 6.1.2[21E above and the equation below. There are examples of this calculation in Appendix D.

The change in samarium/plutonium worth = [Average fraction of rated power for the last 4 days, step 6.1 .2[2}D] x

[(change in samarium worth from equilibrium to peak, step 6.1 .2[2]E) x (1 e PM 149t) + (change in plutonium worth from equilibrium to peak, step 6.1 .2[2]E) x (1 e NP239

- )j t

XPM149 = .01305 hours 1

NP239 = .01229 hours 1

t = time since shutdown in hours =

[ ) ( ) )]

j (i e°° 1305 + (i e°° 1

Change in Sm/Pu Worth =

Change in Sm/Pu Worth = pcm G. Calculate the Xenon worth at time t recorded in step 6.1 .2[2jF using TI-33.

Xenon worth = pcm H. From NDR determine the design critical boron concentration (ARO, HZP, No Xe, HFP Eq Sm and Pu) at the cycle burnup recorded in step 6.1.2[2]B.(Table 6-1) ppm

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-00l .0 0 Rev5 Page 24 of 42 APPENDIX B Page 7 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued)

I. From NDR determine the ARO, HZP Differential boron worth at the cycle burnup recorded in step 6.1 .2[2]B and the boron concentration recorded instep 6.1.2[2}A.(Table 6-8) pcm/ppm J. Based upon the unit cycle experience with previous ECCs or deviations of predicted RCS boron with burnup, adjustments between -100 ppm and +100 ppm may be necessary to reflect any nuclear design bias due to calculational methods or B-i 0 depletion. (Refer to Appendix E for bias calculation)

ECC bias ppm (if applicable)

NOTEI If the results of Step 6.1 .2[2]K are Negative, criticality can NOT be attained and the present RCS boron concentration needs to be reduced.

K. Calculate reactivity worth of difference between Critical Boron Concentration (ARO, HZP, No Xe, HFP Eq Sm and Pu) and present RCS boron concentration.

Present Boron Critical boron ARO,HZP Difference Concentration + ECC Bias Differential Reactivity B oron c oncen -

ARO, HZP, No Xe Step 6.1.2[2jJ BoronWorth Worth Eq Sm (Step 6.l.2[21H) Step6.l.2[2}l STEP 6.1.2[2}A

= ppm - ppm + ppm x pcm I ppm Step 6.1.2[2]A Step 6.1.2[2]H Step 6.1.2[2]J Step 6.1.2[2]I

=

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001.0 0 Rev5 Page 25 of 42 APPENDIX B Page 8 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued)

NOTE2 Results should be negative. If results are positive, boron concentration is still too high.

L. Calculate necessary inserted reactivity worth of control banks at the present RCS boron concentration.

Inserted Control Boron Duff. Xenon Difference from Bank Reactivity =

Worth Reactivity Worth + Worth + Sm I Pu Worth (Step 6.1 .2[21K) Step 6.1 .2[2]G) (Step 6.1 .2[2]F)

= pcm + pcm + pcm Step 6.1.2[2jK Step 6.1.2[2jG Step 6.1.2[2]F pcm M. Record HZP peak Xe worth at the cycle burnup recorded in step 6.1 .2[2]B from the NDR table of HZP equilibrium and peak Xe worth.(Table 6-38)

N. Calculate ECP rod position by interpolating between the NDR HZP integral rod worth tables with peak and no Xe using the peak Xe worth recorded in step 6.1 .2[2]M and the Xe worth recorded in step 6.1 .2[2]G. Interpolate within the tables based on the integral rod worth recorded in step 6.1.2[2]L and the cycle burnup recorded in step 6.1 .2[2]B.(Tables 6-32 and 6-33) steps=____________________

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 26 of 42 APPENDIX B Page 9 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued)

0. Calculate inserted control bank reactivity worth window for:

UPPER ALLOWABLE LIMIT (UAL), Upper Termination Limit (UTL), and Administrative Limit Upper (ALU) for criticality.

Inserted control UAL = Bank Worth (Step 6.1.2[2] L) + 1000 pcm

= +l000pcm Inserted control UTL = Bank Worth (Step 6.1 .2[2] L) + 750 pcm

= + 750 pcm Inserted control ALU = Bank Worth (Step 6.1 .2[2] L) + 500 pcm

= + 500 pcm

2. LOWER ALLOWABLE LIMIT (LAL), Lower Termination Limit (LTL), and Administrative Limit Lower (ALL) for criticality.

Inserted control LAL = Bank Worth (Step 6.1.2[2] L) - 1000 pcm

= -1000 pcm Inserted control LTL = Bank Worth (Step 6.1.2[2} L) -750 pcm

= - 750 pcm Inserted control ALL = Bank Worth (Step 6.1.2[2] L) -500 pcm pcm - 500 pcm pcm

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 27 of 42 APPENDIX B Page 10 of 10 DATA SHEET 2 ECC CALCULATION USING NDR DATA 6.1.2 ECC, Unit Conditions (Continued)

P. Use inserted reactivity worth window of Step 6.1 .2[2]O to determine the control bank position limits from NDR, interpolating as necessary.

UAU = steps withdrawn on control bank UTL =___________ steps withdrawn on control bank ALU =___________ steps withdrawn on control bank LAL =___________ steps withdrawn on control bank LTL = steps withdrawn on control bank ALL steps withdrawn on control bank Q. ACCEPTANCE CRITERIA

1. Estimated critical rod position step 6.1 .2[2}N is further withdrawn than the zero power insertion limit of T.S.

3.1.3.6.

Yes/No /

2. Estimated critical rod position step 6.1 .2[2]N is further inserted than the negative MTC withdrawal limits of TI-28.

Yes/No/N/A

3. IF Acceptance Criteria in Step 1 or 2 is no, THEN REPERFORM Section 6.1.2 with adjusted plant conditions.

/

Calculated byNerified and Approved by:

Calculated By________________________ Date/Time SRO or UO Verify/Approval___________________ Date/Time

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001.0 0 Rev5 Page 28 of 42 APPENDIX C Page 1 of 10 MONITORING THE APPROACH TO CRITICALITY This Appendix is used in conjunction with General Operating Instruction 0-GO-2, Plant Startup from Hot Standby to Reactor Critical. For initial startups following a refueling outage Restart Test Instruction 0-RT-NUC-000-003.0 Initial Criticality will be used instead of this Appendix.

[1] PREPARE the appropriate Data Sheet C-I, ICRRs during rod withdrawal, for each source range channel to be used for monitoring ICRR by RECORDING:

A. Unit and Date.

B. Estimated critical boron concentration and rod position.

C. Draw upper/lower +/- 750 pcm ECC termination band limits onto the ICRR plot. (Refer to Section 6.1.2) LI

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-OO1.O 0 Rev5 Page 29 of 42 APPENDIX C Page 2 of 10 MONITORING THE APPROACH TO CRITICALITY NOTE I The Main Control Room Instrumentation GammaMetrics shutdown monitor can be used in place of the scaler timer on control room panel M-13 to obtain count rates. If Gamma-Metrics shutdown monitors are used then N/A total counts and intervals in the following step. Do not use source range meters on M-4. lOS could be used if Gamma-Metrics monitor not available.

NOTE 2 The counting interval used in the following step should be long enough to obtain at least 1000 counts. (Not applicable if using Gamma-Metrics shutdown monitor)

[2] OBTAIN five counts for each source range channel to be used and average count rate to determine baseline count rate C.

COUNT TOTAL INTERVAL COUNT RATE NO. COUNTS (SEC) (CPS)

N31 1 2

3 4

5 0

N31-C Average COUNT TOTAL INTERVAL COUNT RATE NO. COUNTS (SEC) (CPS)

N32 1 2

3 4

5 0

N32-C Average

SQN ESTIMATED CRITICAL CONDITIONS 0-Sl-NUC-000-001 .0 0 Rev5 Page 30 of 42 APPENDIX C Page 3 of 10 MONITORING THE APPROACH TO CRITICALITY

[3] RECORD on Data Sheet C-i, the baseline count rate C 0 for each source range channel.

NOTE I The remainder of this section is performed concurrently with 0-GO-2.

NOTE 2 Criticality should be anticipated whenever positive reactivity changes are made.

NOTE 3 The counting interval used when determining ICRRs may be adjusted to attain approximately 1000 count (not applicable if using Gamma-Metrics shutdown monitor) or more but count rates must be normalized to the same counting interval (e.g., CPS).

NOTE 4 If the approach to criticality is suspended for an extended period of time near the point of criticality, the reactor core shall be made sufficiently subcritical to reduce the possibility of an inadvertent criticality.

NOTE 5 In the event of an unexplained change in reactivity during an approach to criticality, the approach to criticality shall cease and the reactor core shall be made sufficiently subcritical to prevent an inadvertent criticality.

Approval of the Plant Manager or his designee is required to resume the approach to criticality.

NOTE 6 Step [4] will be repeated many times. Each performance is initialed on Appendix C, Data Sheet C-i.

NOTE 7 The SRO or Test Director may stop rod withdrawal and request an ICRR plot at any time but stopping points in below table are preferred.

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 31 of42 APPENDIX C Page 4 of 10 MONITORING THE APPROACH TO CRITICALITY CONTROL BANK STEP POSTION TOTAL STEPS CONTROL BANK A/B 150122 150 CONTROL BANK B/C 172/44 300 CONTROL BANK C/D 144/16 400 CONTROL BANK CID 194166 450 CONTROLBANKO 116 500 CONTROL BANK 0 166 550 CONTROL BANK D 216(IF NECESSARY) 600 CONTROL BANK 0 FULL OUT(IF NECESSARY) 615

[4] WHEN rods have been nominally withdrawn per table above or in accordance with 0-GO-2, THEN CALCULATE and PLOT ICRR using the following steps:

[a] STOP rod withdrawal and allow count rate to reach equilibrium (approximately 2 minutes or longer for stabilization) before taking counts data. El

[b] IF criticality has been achieved, THEN go to Step

{4][j] to record critical data. Li

[c] RECORD number of counts, counting interval (secs) and calculated count rate on Data Sheet C-I. LI

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001.0 0 Rev5 Page 32 of 42 APPENDIX C Page 5 of 10 MONITORING THE APPROACH TO CRITICALITY

[d] RECORD Controlling Bank and Controlling Bank position on Data Sheet C-i.

[eJ RECORD ICRR on Data Sheet I using the following equation:

=

CR ICRRn CRn Where CRo = Baseline count rage CRn = Individual count rate NOTE 8 The ICRR plot constructed in the following step is intended to monitor the approach to criticality and is not necessarily a prediction of criticality. However, the general trend of the plot should predict criticality between the upper and lower ECC termination limits drawn in step

[1].

[fJ PLOT ICRR value recorded in step [e] versus Control Bank position from step [d] on Data Sheet C-i. L

SQN ESTIMATED CRITICAL CONDITIONS O-SI-NUC-000-OO1.O 0 Rev5 Page 33 of 42 APPENDIX C Page 6 of 10 MONITORING THE APPROACH TO CRITICALITY

[g] EVALUATE ICRR plot to determine overall trend.

[h] IF overall trend of ICRR plot indicates an acceptable ECC, THEN CONTINUE Control Bank withdrawal in accordance with 0-GO-2. El

[I] IF overall trend of ICRR plot indicates actual critical conditions will fall outside ECC termination band, THEN NOTIFY appropriate Unit US, SM, Duty Plant Manager, and explain why startup should continue or ECC be recalibrated on Data Sheet C-2.

U] IF reactor is critical, THEN RECORD critical data on Data Sheet C-2. El

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SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001.0 0 Rev5 Page 36 of 42 APPENDIX C Page 9 of 10 MONITORING THE APPROACH TO CRITICALITY DATA SHEET C-2 UNIT CONDITIONS AT CRITICALITY

[1] Date/Time at criticality.

[2] Core Average Temperature.

[3] Control Bank Position: Bank D at Bank C at

[4] Critical boron concentration,

[5] ACCEPTANCE CRITERIA A. Actual critical rod position is further withdrawn than theZPILofTS3.1.3.6. LlYes ENo B. Actual critical rod position is further inserted than the negative MTC withdrawal limits of TI-28. LlYes LINo LINA C. Actual critical rod position is within the 1000 pcm limits. EYes EN0 D. Date/Time of criticality are within the applicable 4 hourtime span. LlYes LJNo E. Actual critical rod position is within the 750 pcm limits. LlYes EN NOTE 9 The following acceptance criteria is an administrative limit:

F. Actual critical rod position is within the 500 pcm limits. EYes EN0

[6] ACCEPTANCE CRITERIA VERIFICATION A. If acceptance criteria 5A was not satisfied, notify the SM that the action requirement of LCO 3.1.3.6 must be satisfied. EYes ENo ENA

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001.0 0 Rev5 Page 37 of 42 APPENDIX C Page 10 of 10 MONITORING THE APPROACH TO CRITICALITY DATA SHEET C-2 UNIT CONDITIONS AT CRITICALITY B. If acceptance criteria 5B was not satisfied, notify the SM that the action requirement of LCO 3.1.1.3 must be satisfied. LlYes LINo LINA C. If acceptance criteria 5C was not satisfied, notify the SM that the action requirement of LCO 3.1.1.1 must be satisfied. LlYes ENo LINA D. If acceptance criteria 5D was not satisfied, notify the SM that the action requirement of LCO 3.1 .1.1 must be satisfied (see TS 4.0.3). LlYes LINo LINA E. If acceptance criteria 5E was not satisfied, request Reactor Engineering to perform an evaluation of the reactivity differences. LlYes LiNo EN F. If acceptance criteria 5F was not satisfied, request Reactor Engineering to perform an evaluation of the reactivity differences. EYes ENo ENA Comments:

SQN ESTIMATED CRITICAL CONDITIONS O-SI-NUC-000-OOl.O 0 Rev5 Page 38 of 42 APPENDIX D Page 1 of 4 SAMARIUM/PLUTONIUM WORTH NOTE I The information below represent the minimum necessary to properly account for post-shutdown samarium and plutonium worth. As used herein, the terms Sm worth (or ASm worth), Pu worth (or z\Pu worth),

and Sm/Pu worth (or ASm/Pu worth) refer to the incremental worth due to the change in isotopic number density (i.e., peaking from the reference. The reference number density is defined as that resulting from depletion at HFP conditions (i.e., equilibrium).

FCF recommends a combined accounting for the incremental worth post-shutdown due to number density peaking of these two isotopes 149 and Pu (Sm ) due to the similarity in the half lives of their 239 respective precursors. Sm 149 results from beta decay of promethium 149 (Pm

) with half life of 53.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Pu 149 239 results from beta decay of neptunium 239 (Np) with a half life of 2.35 days (56.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />).

239 FCF has presented the information necessary to make an adjustment for Sm/Pu worth after shutdown for an ECB/ECC calculation for a number of utilities. An example of the presentation of this data is shown below:

NOTE 2 For actual calculations, use the NDR--not the table below.

TABLE I - SAMARIUM AND PLUTONIUM-239 WORTHS AT HOT ZERO POWER, CONTROL RODS FULLY WITHDRAWN, NO XENON Cycle Burnup, HZP Samarium Worth, HZP Pu-239 Worth, MWDIMTU Peak Equilibrium, pcm Peak Equilibrium, pcm 0 0 0 154 -215 137 963 -334 195 1925 -344 192 7700 -385 180 18249 -489 177

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 39 of 42 APPENDIX D Page 2 of 4 SAMARIUM/PLUTONIUM WORTH NOTE 3 Not accounting for Sm/Pu worth at BOO has less impact on the accuracy of a given EOP than at EOC. The incremental Sm/Pu worth (see first NOTE in this Section) contribution of interest results from the sum of the values in each column for a given burnup. Two other factors in using a table like Table 1 are provided below.

Using the 53.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (2.213 day) half life for the Sm 149 precursor, the following relationship applies to the percentage of the Sm/Pu worth correction that should be used assuming the pre-shutdown condition was nominal HFP operation for at least four days:

Sm/Pu Fraction = 1 -

where . = the decay constant of the Sm 149 precursor, in this case

= 0.693/2.213 = 0.313 days, and t = time after shutdown, days Table 2 results directly from this equation:

TABLE 2 FRACTION OF Sm/Pu WORTH Vs TIME SHUTDOWN Time After Shutdown (Days) Fraction of SmIPu Worth 2 0.465 4 0.714 6 0.847 8 0.918 10 0.956

>12 1.000

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 40 of 42 APPENDIX 0 Page 3 of 4 SAMARIUM/PLUTONIUM WORTH NOTE 4 Using the precursor half life for Sm 49 simplifies the calculations required if employing this method. It is acceptable to more precisely determine the Sm/Pu worth by separately treating Sm and Pu and adding together only after the separate decay factors are determined.

NOTE 5 If power level was not at 100% FP prior to shutdown, an additional reduction factor should be applied to account for the fact the HFP equilibrium values were not present prior to shutdown. An adequate approximation for this correction is to average the power level over four days prior to shutdown and use this fraction or power level as an additional factor applied to the worth in Table 1.

EXAMPLE #1 A reactor unit has been shutdown for five days, 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Criticality is scheduled 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from now. Prior to the shutdown, the unit operated at 100% FP, steady state for over a month and achieved a core burnup of 14130 MWD/MTU. Using Table 1, what is the Sm/Pu reactivity contribution for tomorrows startup?

The t\Sm Worth and APu Worth for 14130 MWD/MTU from Table 1 by linear interpolation is: ASm Worth = -448 pcm APu Worth = +178 pcm The time of shutdown is projected to be six days, 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, or 157 hours0.00182 days <br />0.0436 hours <br />2.595899e-4 weeks <br />5.97385e-5 months <br />. Use the following Equation to determine the Sm/Pu Worth:

Sm/Pu Worth = [Average fraction of rated power for the last 4 days] x

[(ASm Worth) x (1 e PMI49

- ) + (APu Worth) x (1 eX t t -

P239

) ]

Where: PM149 = .01305 hours NP239 = .0 1229 hours0.0142 days <br />0.341 hours <br />0.00203 weeks <br />4.676345e-4 months <br /> 1 t time since shutdown in hours = 157 hours0.00182 days <br />0.0436 hours <br />2.595899e-4 weeks <br />5.97385e-5 months <br /> Therefore, Sm/Pu worth is:

Sm/Pu Worth = [1.001 x [(448) x (1 1305X157))

+ (178) x (1 - 01229157))]

pcm Sm/Pu Worth = [1 .00] x [(-448) x (0.8711) + (178) x (0.8548)] pcm Sm/Pu Worth = -238 pcm

SQN ESTIMATED CRITICAL CONDITIONS 0-S!-NUC-000-0O1.0 0 Rev5 Page 41 of42 APPENDIX D PAGE 4 OF 4 SAMARIUMIPLUTONIUM WORTH EXAMPLE #2 A reactor unit has been shutdown for two days, 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />. Criticality is scheduled 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from now. Prior to the shutdown, the unit operated at the following daily average power levels: 38% FP, 56% FP, 93% FP, and 100% FP. The core burnup is 16794 MWD!MTU. Using Table 1, what is the Sm/Pu reactivity contribution for tomorrows startup?

The iSm Worth and APu Worth for 16794 MWD!MTU from Table 1 by linear interpolation is: ASm Worth -475 pcm APu Worth = +177 pcm The time of shutdown is projected to be three days, 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />, or 91 hours0.00105 days <br />0.0253 hours <br />1.50463e-4 weeks <br />3.46255e-5 months <br />. Use the following Equation to determine the Sm/Pu Worth:

Sm/Pu Worth = [Average fraction of rated power for the last 4 days] x

[(zSm Worth) x (1 e PM 149t) + (APu Worth) x (1 e t

- - P239

) ]

Where: PM149 = .01305 hours1 NP239 = .01229 hours1 t = time since shutdown in hours = 91 hours0.00105 days <br />0.0253 hours <br />1.50463e-4 weeks <br />3.46255e-5 months <br /> Therefore, Sm/Pu worth is:

Sm/Pu WorthI(.38+.56+.93+1 )14lx[(-475)x(1 (.O13O5)(91))÷(j 77)x(1 e(°l l))jpcm 9

X 229 Sm/Pu Worth = [.7175] x [(-475) x (0.69503) + (177) x (0.6731 9)] pcm Sm/Pu Worth = -151 pcm

SQN ESTIMATED CRITICAL CONDITIONS 0-SI-NUC-000-001 .0 0 Rev5 Page 42 of 42 APPENDIX E Page lof 1 ECC AND ECB BIAS CALCULATION NOTE: Engineering judgment(previous ECC history, time in core life, etc) should be used before ECC or ECB bias is applied. All or part of the bias can be used at test director discretion. Sign convention for Sequoyah is positive for measured RCS boron above the letdown curve and negative if below the letdown curve.

1. Run REACTF ECB for time of criticality with no bias.

ECB=

2. In FOLnnn.XLS, under the Correct Factors worksheet, Boron Addition Correction Factors Table, copy row and enter new column data with the date, cycle burnup, B-iD atom fraction, initial boron and final boron(Column O,P,Q,T and U); Reference B-iD Depletion Correction Factors Table, copy row and enter new column with cycle burnup (column AA) to calculate B-ID atom fraction in column Al.

Get B-iD Atom fraction (column A! at the correct burnup)= Atom fraction

3. Calculate B-iD depletion.

B-ID depletion=(1- /0.198) * ( ppm)

Step 2 Step I B-ID depletion = ppm

4. Obtain current design difference (AROCBC) from FOLnnn.XLS spreadsheet, Data worksheet, Delta AROCBC(design difference) column K for the correct burnup.

Design difference= ppm Note: Reverse the sign of design difference ppm by multiplying by -1 (This is applicable for both REACTF and a hand calculation).

5. Calculate Bias.

Bias = PPM +

Step 3 Step 4 after sign change Bias = PPM

6. Check calculated bias for general agreement with supplementary calculation in FOLnnn.XLS worksheet Correction Factors worksheet column AM after inputing ECB value into column AK.
7. Run the ECB with the bias, specifying control bank D height, to determine the ECB. Then run the ECC with the bias and ECB to determine control bank D height.

JPM ADMIN C Page 1 of 5 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam SRO ADMIN C Evaluate Worker Exposure

JPM ADMIN C Page 2 of 5 Rev. 0 SRO JOB PERFORMANCE MEASURE Task: Evaluate worker exposure and apply radiation and contamination safety procedures Task #: 1190100301 (RO); 3430290302 (SRO)

Task Standard: Candidate will calculate the three workers exposures and determine the required administrative actions.

Time Critical Task: YES: NO: X K/A Reference!Ratings: 2.3.4 (3.2/3.7)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 10 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

JPM ADMIN C Page 3 of 5 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
2. Any UNSAT requires comments
3. Ensure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.

ToolslEquipmentlProced ures Needed:

RCI-03

References:

Reference Title Rev No.

RCI-03 Personnel Monitoring 48

2. RCTP-105 Personnel Inprocessing and Dosimetry 0001 Administrative Processes READ TO OPERATOR DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Radiation surveys in the Auxiliary Building are as follows:
  • lA-A Charging Pump Room = 40 MR/hr
2. The lA-A Charging Pump is QOS for pump shaft replacement.
3. The shaft replacement is expected to take 3 workers 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to complete.
4. Annual exposure for each worker up to this time is as follows:
  • WorkerA= IOMR
  • WorkerB=300MR
  • Worker C = 720 MR INITIATING CUES:

Assuming all three workers will spend the entire 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in the charging pump room, determine the following:

1. Each workers projected exposures.
2. Any additional approvals required to perform the work, based upon the calculated exposure.

JPM ADMIN C Page 4 of 5 Rev. 0 Job Performance Checklist:

STEP I STANDARD SAT I UNSAT STEP 1.: Déterniineprójected reethéjob.*

Note: (40 mr/hr x 12 hrs = 480 mr each worker) UNSAT STANDARD: Operator calculates projected exposure of 480 MR for each Start Time:

worker.

This is a critical step necessary to determine overall exposure for job.

Critical Step COMMENTS:

STEP 2.: éjprojcted totj SAT U N SAT STANDARD: Worker A projected total annual exposure is calculated to be49OMR. (lOmr+480mr=490mr)

Worker B projected total annual exposure is calculated to Critical Step be 780 MR. (300mr + 480 mr = 780 mr)

Worker C projected total annual exposure is calculated to be 1200 MR. (720 mr + 480mr = 1200 mr)

This step is critical to determine which, if any, of the workers may need dose extensions.

COMMENTS:

Step 3 Determine any additional approvals reqred to perform thQriç SAT bad uppnthe prqjecteçi totalannuaiexposur%

UNSAT STANDARD: Worker C must receive authorization from the Site Radiation Critical Step Protection Manager/RSO to exceed an annual TEDE of 1.0 rem.

This is critical step to determine which, if any, worker(s) would need Stop Time:

authorization to exceed admin dose limit.

COMMENTS:

CUE: This completes the JPM

READ TO OPERATOR DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Radiation surveys in the Auxiliary Building are as follows:
  • IA-A Charging Pump Room = 40 MRJhr
2. The lA-A Charging Pump is QOS for pump shaft replacement.
3. The shaft replacement is expected to take 3 workers 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to complete.
4. Annual exposure for each worker up to this time is as follows:
  • Worker A = 10 MR
  • WorkerB=300MR
  • Worker C = 720 MR INITIATING CUES:

Assuming all three workers will spend the entire 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in the charging pump room, determine the following:

1. Each workers projected exposures.
2. Any additional approvals required to perform the work, based upon the calculated exposure.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT RADIOLOGICAL CONTROL INSTRUCTION RCI-03 PERSONNEL MONITORING Revision 48 QUALITY RELATED PREPARED BY: Terry F. Johnston RESPONSIBLE ORGANIZATION: Radiation Protection APPROVED BY: JOHN VINCELLI EFFECTIVE DATE: 02/24/05 VERIFICATION DATE: N/A LEVEL OF USE: INFORMATION ONLY REVISION DESCRIPTION This revision updates the references, includes organizational title changes, removes the previous requirement to list the SSN on TLD5 (PER #76092) and updates general information. This revision is an intent revision.

Attachment 01, Prenatal Radiation Exposure Program, is revised to include organizational title changes. This revision is an intent revision.

Attachment 03, Area TLD Monitoring Program, is revised to include organizational title changes. This revision is an intent revision.

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 2 of 16 1.0 PURPOSE The purpose of this Instruction is to provide guidelines for monitoring personnel external radiation exposures.

2.0 SCOPE This Instruction establishes the requirements for personnel dose monitoring (PCs, EDs, TLD5), extremity dose monitoring, Administrative Dose Levels (ADL5), emergency exposure guidance, details the prenatal radiation exposure program, provides the requirements for calculation of skin doses, and details the area TLD monitoring program.

3.0 REFERENCES

A. IOCFRI9, Notices, Instructions, and Reports to Workers; Inspection and Investigations B. IOCFR2O, Standards for Protection Against Radiation C. NUREG CR-4418, Dose Calculation for Contamination of the Skin Using the Computer Code VARSKIN D. NUREG CR-5569, Health Physics Position Database E. NUREG CR-5873, VARSKIN MOD2 and SADDE MOD2: Computer Codes for Assessing Skin Dose from Skin Contamination F. NUREG CR-6204, Questions and Answers Based on Revised IOCFR2O G. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with I OCFR5O, Appendix I H. Regulatory Guide 8.13, Instruction Concerning Prenatal Radiation Exposure I. NRC IE Notice 86-23, Excessive Skin Exposures Due to Contamination of Hot Particles J. NRC IE Notice 90-48, Enforcement Policy for Hot Particle Exposures K. SPP-2.3, Document Control L. SPP-5.1, Radiological Controls M. SPP-5.9, Radiological Control and Radioactive Material Shipment Augmented Quality Assurance Program N. ANSI N41 3-1974, Guidelines for the Documentation of Digital Computer Programs

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 3 of 16

3.0 REFERENCES

(Continued)

0. INPO 91-014, Guidelines for Radiological Protection at Nuclear Power Stations P. SQN Technical Specifications, Unit 1 and Unit 2 Q. EPIP-15, Emergency Exposure Guidelines R. RCI-01, Radiation Protection Program S. RCI-04, Radiological Respiratory Protection Program T. RCI-1 1, Bioassay Program U. RCI-15, Radiological Postings V. RCI-23, Radiation Protection Records W. RCI-24, Control of Very High Radiation Areas X. RCI-27, External Dosimetry Services (TEDS) Laboratory Quality Manual Y. RCI-28, Control of Locked High Radiation Areas Z. RCI-29, Control of Radiation Protection Keys AA. ANI/MAELU Engineering Bulletin 88-3A, Nuclear Liability Guidance for Hot Particle Contamination AB. Revision of Technical Basis for Skin Dose Assessment Process, RIMS L78 880209 800 AC. Counting Efficiencies for GM Detectors, RIMS L78 871105 800 AD. Revision of Factors for Calculating Skin Dose from Contamination, RIMS L09 891215 800 AE. Skin Dose Due to Beta Particles from Noble Gases, RIMS L78 870505 801 AF. Validation Testing of the Lotus 1-2-3 Application SKINDOSE.WKI, RIMS L78 0606 801 AG. Response of Panasonic Dosimeters to Submersion Exposure by Xe-I 33, Hoffman, J.M., and Catchen, G.L., Health Physics, Vol. 58, No. 1 AH. A Method of Adding Nuclides to VARSKIN and QUINCE Skin Dose Calculation Software, Radiation Protection Management, Vol. 4, No. 6 Al. RCTP-105, Personnel Inprocessing and Dosimetry Administrative Processes

RCI-03 SQN PERSONNEL MONITORING Revision 48

. Page4ofl6 4M DEFINITIONS/ABBREVIATIONS Calendar Quarter A calendar quarter is a normal 13 consecutive week period.

The first calendar quarter of each year shall begin in the first week of January, and subsequent calendar quarters shall be such that no day is included in more than one calendar quarter, or omitted from inclusion within a calendar quarter.

Committed Effective Dose Equivalent (CEDE) The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues.

Dose Equivalent The product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest. The units of dose equivalence are the rem and the Sievert (Sv).

Dose Estimate (as used in this Instruction) A written estimate of dose received during the current calendar quarter and/or year.

Dosimetry Personnel monitoring devices used to determine the occupational radiation dose received by an individual.

Electronic Dosimeter (ED) An electronic dose measuring device worn next to the TLD that is used to give the wearer immediate dose readout. The ED dose is the actual deep dose received and may be used as official dose in the event the TLD is lost.

Form 4 TVA Form 40763, Form-4 Equivalent, Cumulative Occupational Exposure History. This form is provided as RCTP-105-7.

Permanent TLD A TLD assigned to personnel whose assignment on site is greater than 90 consecutive days. Each TLD (front insert) will contain the employees name and TLD ID number.

Pocket Chamber (PC) An ion chamber radiation detection device that is used to give the wearer an immediate dose readout. The pocket chamber dose may be used as official dose in the event that the TLD is lost. A pocket chamber is sometimes called a dosimeter or a DRD (direct reading dosimeter).

Radiation Operations (Rad Ops) - New organizational title for the previous Field Operations section.

Radiation Protection (Rad Protection) New organizational title for the previous RADCON and Radwaste organizations.

Responsible Onsite Supervisor A supervisor who is responsible for a specific individual and is on the list of site supervisors authorized to admit personnel to the site.

. RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 5 of 16 4.0 DEFINITIONS/ABBREVIATIONS (Continued)

Temporary TLD A TLD assigned to personnel whose assignment on site is less than or equal to 90 consecutive days. Each TLD will contain an ID number.

Upon issuance, the employees name is recorded on the TLD.

Total Effective Dose Equivalent (TEDE) The sum of the deep dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).

Whole Body (or Total Body) For the purposes of external exposure, the head, trunk (including male gonads), arms above the elbow, or legs above the knee.

5.0 RESPONSIBILITIES 5.1 Radiation Operations Manager The Rad Ops Manager is responsible for ensuring that all requirements for personnel monitoring are maintained as specified in this Instruction.

5.2 Site Emergency Director (SED)

The SED is responsible for providing written authorization for all emergency radiation doses that may exceed the limits of IOCFR2O (Reference 3.B).

5.3 Site Section Supervisors The site Section Supervisors are responsible for ensuring that personnel under their supervision comply with all TVAN procedures and instructions concerning radiation dose control.

5.4 Radiation Protection Rad Protection is responsible for controlling, tracking, monitoring, reviewing, and reporting personnel radiation dose, to include:

A. Maintenance of employees radiation dose records. A Rad Protection computer-based records storage system shall be implemented to track and control worker radiation exposure.

B. Issuance of periodic employee exposure summary reports.

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 6 of 16 5.0 RESPONSIBILITIES (Continued)

Note Written estimates of current year exposure are provided to an employee upon request. Estimates of dose in the absence of finally determined personnel monitoring results must be clearly indicated as such.

C. Issuance of a written report regarding the radiation dose received at SQN during the current year to each individual having monitoring records at TVA. This report is provided annually to current employees and upon request to former employees.

D. Investigation of TLD, PC and/or ED reading discrepancies.

E. Ensuring that dosimetry values are correct, properly assigned, and entered into the appropriate Rad Protection records data base.

F. Maintaining dosimetry processing accreditation under the National Voluntary Laboratory Accreditation Program (NVLAP).

5.5 Individual Employee The individual employee is responsible for complying with all regulations concerning radiation exposure control. Employees are responsible for:

A. Properly wearing prescribed dosimetry.

B. Wearing only that dosimetry assigned to them.

C. Proper care and handling of dosimetry, equipment, and instrumentation.

D. Pick up and return of dosimetry.

E. Notifying Rad Ops in the event of lost or damaged dosimetry.

F. Processing through Rad Protection when arriving, transferring, or terminating at SQN.

G. Informing Rad Protection whenever radiation exposure or medical radionuclide injections have been, or will be received, from a source other than TVA.

6.0 REQUIREMENTS 6.1 Precautions and Limitations A. During normal operations, no individual or group of individuals shall be permitted to receive a radiation dose that exceeds the limits specified in this Instruction.

B. During emergency situations dose limitations will be as described in EPIP-15 (Reference 3.Q).

. RCI-03 SQN PERSONNEL MONITORING Revision 48

. Page7ofl6 6.0 REQUIREMENTS (Continued)

C. TLD results are used as the official record of radiation exposure.

In the event of a lost or damaged TLD, individuals are responsible for immediately reporting the condition to Rad Ops. In some instances, due to the loss or damage of a monitoring device or the inability of the monitoring device to measure certain types of radiation, it will be necessary to calculate an individuals dose. All calculations shall be documented and included in the employees personal exposure history record.

D. If a PC and/or ED is lost, damaged, or offscale, it shall be immediately reported to Rad Ops.

E. When a PC reads in excess of 3/4 scale, or an ED alarms, the wearer shall report to Rad Ops to have the reading recorded and the PC and/or the ED reset.

F. Individuals shall verify possession of their assigned dosimetry prior to entering a Radiologically Controlled Area (RCA).

G. Any individual who enters an RCA shall sign in on an appropriate active Radiation Work Permit (RWP) and be monitored for radiation exposure with a TLD and a secondary dosimeter (e.g., ED), unless waived by Rad Protection management.

H. Dosimetry shall normally be worn on the front of the person between the neck and belt line. It shall be in a clearly visible position. When worn in combination, a PC and/or ED should be located within six inches of the TLD. The beta window side of the TLD should normally face outward. When in a Radiation Area, High Radiation Area, or higher radiological zone classification, the PC and/or ED should be placed in a location that will allow the user to frequently read them.

Extremity doses shall be measured when an individuals extremity dose exceeds, or is expected to exceed, 10% of the annual limit as indicated in IOCFR2O. Extremity dosimetry will be issued when the whole body TLD is not an appropriate monitor of extremity dose.

J. If it is determined by Rad Ops that the portion of the body most likely to receive the greatest exposure is not in the area of the normal placement location of the TLD, the TLD will be moved to the more appropriate area, and/or multiple TLDs provided.

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 8 of 16 6.0 REQUIREMENTS (Continued)

K. Any employee whose radiation dose exceeds any established limits shall not be permitted to enter any RCA for the remainder of the specific monitoring period.

L. During a site emergency, storage, pickup and collection of dosimetry may be performed at alternate locations as conditions warrant.

6.2 General A. Dosimetry processing equipment, TLDs, PCs, and EDs shall be calibrated in accordance with approved procedures.

B. As a minimum, all assigned TLDs are read at least semi-annually.

Special TLD readouts are performed as necessary.

C. TLDs are not required to be stored in their specified storage location upon exiting the plant site each day. However, each individual is responsible for maintaining possession of their TLD and ensuring that it is worn in accordance with the requirements of this Instruction.

D. Any individual permitted to enter a posted High Radiation Area, Locked High Radiation Area, or Very High Radiation Area shall comply with the requirements of RCI-15 (Reference 3.U), RCI-24 (Reference 3.W), RCI-28 (Reference 3.Y), and/or RCI-29 (Reference 3.Z), as appropriate. [C.1][C.3]

E. Dosimetry may be issued by Rad Protection after a Form-4 (RCTP-1 05-7, TVA Form 40763), or equivalent, has been initiated and signed by the individual and all applicable requirements have been met (i.e., bioassay, training, etc.).

F. For individuals requiring an Administrative Dose Level (AOL) of less than 500 mrem per year, current year and lifetime dose estimates must be provided and signed by the individual. A Request for Dosimetry Issuance (RCTP-105-10, TVA Form 40823), or equivalent, will be used to document current year and lifetime estimates.

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 9 of 16 6.0 REQUIREMENTS (Continued)

G. All individuals who have a permanent/temporary TLD at SQN must checkout through Rad Protection prior to terminating work at SQN.

In addition, individuals who will visit another licensee or TVA plant, and require a TLD, must checkout prior to leaving SQN.

H. Area TLDs will be controlled in accordance with the requirements of Attachment 03, Area TLD Monitoring Program.

6.3 Assignment of Radiation Dose Limits A. If an employee is assigned to work at a non-TVA installation where an exposure to radiation is incurred, the employee shall inform Rad

- Protection of this assignment. The employee shall turn in their dosimetry, obtain any required bioassays, and complete any requested documentation. When the employee returns, they must report to Rad Protection to update their exposure records.

B. When visitor or contract personnel have more restrictive dose limits than TVA, the more restrictive limits will be used. It is the responsibility of the contractor to provide written notification to Rad Protection of any company administrative limit.

6.4 Administrative Dose Levels (ADLs)

In addition to the limits of IOCFR2O, ADLs shall be used. The following ADLs shall be observed for routine work:

A. To ensure that ADLs are not exceeded an administrative control system has been established (refer to Section 6.7).

B. ADLs are based on dosimeters used in determining the reported dose. Results which exceed an ADL, based on other dosimeter data, do not violate the ADL.

I RCI-03 SQN PERSONNEL MONITORING I Revision 48 PagelOofl6 6.0 REQUIREMENTS (Continued)

C. An individuals dose shall be controlled by the ADLs listed in the following table:

Table I Administrative Dose Level Program Dose Equivalent Authorization to Exceed (rem) Requirement (Signatures)

Up to 0.5 TEDE (or 1.5 LDE or Statement of current year dose and previous Not applicable 5.0 SDE) at 1VA years dose signed by the individual Up to 1.0 TEDE Form 4 (or equivalent) to document (or 3.0 LDE or current year and previous years Not Applicable 10 SDE) all sources dose equivalent To exceed 1.0 TEDE (or 3.0 LDE or Site Radiation Protection Same as above Manager! RSO 10 SDE) all sources To exceed 5.O Form 4 information must be verified Site Rad Protection Mgr! RSO, TEDE all sources and a Planned Special Exposure initiated , and Site VP Plant Manager 1 2 or SED, as appropriate To exceed IN4 Site Rad Protection Mgr! RSO, all sources Form 4 must be verified , and Site VP Plant Manager 1 2 or SED, as appropriate Legend I At non-nuclear plant sites, this will be the RSOs immediate supervisor.

2 At non-nuclear plant sites, this will be the applicable TVA VP.

3 Authorizations for a Planned Special Exposure will only be considered in an exceptional situation when alternatives that might avoid the dose estimated to result from the planned special exposure are unavailable or impractical.

4 TEDE should not exceed 1 N rem, where N equals the individuals age in years at their last birthday, without authorization signatures delineated.

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 11 of 16 6.0 REQUIREMENTS (Continued)

D. Individuals under the age of 18 shall not be granted RCA access.

E. Individuals whose lifetime accumulated TEDE is IN rem shall be limited to 1,000 mrem/yr. The administrative controls of previous Table I are applicable.

F. To authorize ADL increases, an Administrative Dose Level Extension (RCTP-1 05-1, TVA Form 40757) must be completed in accordance with SPP-5.I (Reference 3.L). At the discretion of the Rad Protection Manager, other methods may be utilized (i.e., a memo covering a group of people). Alternate methods shall include the information required on the RCTP-105-1. ADL extensions are tracked on an AOL Tracking Sheet (RCTP-105-6, TVA Form 40762).

G. Any personnel exposure received which is in excess of the limits of IOCFR2O shall be reported by the site Rad Protection Manager to the Radiation Effects Advisory Group (REAG) and the appropriate area chief physician for an examination. A medical examination and authorization from the Chief Nuclear Officer and Executive Vice President are required before resumption of duties in RCAs for individuals who have received five times the annual limit of I OCFR2O.

H. Prenatal exposure will be controlled as described in Attachment 01, Prenatal Radiation Exposure Program.

Employees shall be instructed during RADCON training to report to their local TVA medical facility and site Rad Protection whenever they receive medical external radiation therapy or internal radionuclides for diagnosis or treatment (routine diagnostic x-rays need not be reported). Rad Ops shall be contacted and requested to perform a radiation survey on the worker. Based on the results of this survey, the individual may be restricted from entry into the RCA. RCA access will be granted when it can be determined, through bioassay and direct surveys, that the medical treatment does not interfere with the ability to monitor the individuals occupational dose.

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 12 of 16 6.0 REQUIREMENTS (Continued)

J. Individuals who have or are undergoing therapeutic radiation exposures can have their ADL lowered to 500 mrem, absent other circumstances which warrant a higher or lower ADL, upon their written request. A Therapeutic Medical Radiation Exposure (RCTP-1 05-8, TVA Form 40764) can be used for this request. The ADLs for individuals receiving therapeutic medical radiation exposures and individuals with radiologically related medical restrictions should be evaluated on a case-by-case basis. It is recommended that the opinion and recommendations of the individuals treating specialist be solicited. The treating specialist would be most aware of the individual diagnosis, specific therapy, the attendant risks, as well as any unusual susceptibility or precautions necessary regarding workplace radiation exposure.

The individual and their supervisor will be counseled by Medical Services. A written record of this counseling shall be made and maintained along with all other supporting documentation. It will be included in the individuals personal history file. For individuals receiving therapeutic medical radiation exposures the individual should have risks clearly explained and be encouraged, but not required, to be placed on a lower ADL.

1. If the individual chooses to be placed on a lower ADL, the individual shall be informed that reasonable accommodations will be made to retain their present job status; however, their present job status cannot be guaranteed.
2. For individuals with radiologically related medical restrictions, Medical Services, in consultation with the Rad Protection Manager (or designee), will determine if occupational exposure should be administratively restricted.

6.5 Skin Dose From Contamination Skin dose calculations shall be performed in accordance with the requirements of RCTP-106, Special Dosimetry Operations.

RCI-03 SQN PERSONNEL MONITORING Revision 48 Pagel3ofl6 6.0 REQUIREMENTS (Continued) 6.6 Emergency Exposure Guidance A. It is consistent with the risk concept to accept exposures leading to doses in excess of those appropriate for routine operation when recovery from an accident or major operational difficulty is necessary. Saving of a life, measures to circumvent substantial exposure to the general public, or the preservation of valuable installations may be sufficient cause for accepting above normal exposures. Dose limits for an emergency cannot be specified, but they should be commensurate with the significance of the objective and held to the lowest practical level that the emergency permits.

B. Any decision to embark on emergency operations which would result in exposures in excess of IOCFR2O should be done in consultation with the most senior member of Rad Protection who is available on a timely basis. The guidelines that should be utilized when assigning administrative exposure limits for emergency conditions are listed below. Actual guidance for emergency situations is described in EPIP-15.

Table 2 Maximum Limiting Whole Body Dose Equivalent to Radiation Workers During Extreme Emergency Dose Equivalent Remarks 10 rem Taken only to prevent serious damage to the plant or hazard to personnel 25 rem Taken to save a life C. Personnel must be made aware of possible consequences of such an exposure and selected on a voluntary basis. Emergency team members who are expected to respond to a radiological emergency must be aware of the consequences of such exposure.

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 14 of 16 6.0 REQUIREMENTS (Continued) 6.7 Administrative Control of Radiation Exposure Note When deemed necessary, Rad Protection Support shall perform a special TLD analysis.

To minimize the potential for an overexposure, Rad Protection Support shall notify the responsible section supervisor in writing when an individual in that supervisors section is approaching Action Level 1, or has exceeded Action Level 2:

A. Action Level I An individual has exceeded 80% of the ADL. The responsible supervisor shall not use that individual in a posted Radiation Area, High Radiation Area, or higher radiological zone classification, unless no other qualified personnel with lower exposures are available.

B. Action Level 2 An individual has exceeded 90% of the ADL. The individual shall be restricted from the RCA.

C. Removal of either Action Level restriction requires the completion of an Administrative Dose Level Extension and approval of the Rad Protection Manager.

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 15 of 16 7.0 QUALITY ASSURANCE (QA) RECORDS 7.1 QARecords The following records are QA records and shall be completed, handled, and stored in accordance with RCI-23 (Reference 3.V):

Request for Dosimetry Issuance RCTP-105-10 TVA Form 40823 Form-4 Equivalent, Cumulative Occupational Exposure History RCTP-105-7 TVA Form 40763 Administrative Dose Level Extension RCTP-105-1 TVA Form 40757 Therapeutic Medical Radiation Exposure RCTP-105-8 TVA Form 40764 7.2 Non-QA Records The following records are non-QA records and shall be completed, handled, and stored in accordance with RCI-23:

ADL Tracking Sheet RCTP-105-6 TVA Form 40762 8.0 APPENDICES/ATTACHMENTS Attachment 01 Prenatal Radiation Exposure Program Attachment 02 Calculation of Skin Dose Attachment 03 Area TLD Monitoring Program SOURCE NOTES

RCI-03 SQN PERSONNEL MONITORING Revision 48 Page 16 of 16 Source Notes Implementing Requirements Requirements Statement Document Statement Revise RCI-3to indicate that each individual entering a high radiation area shall be equipped with a survey meter RIMS A02 871116 013 or alarming dosimeter unless the work c.1 RIMS S53 880208 994 is continuously monitored by a RADCON representative with an appropriate survey meter.

Annotated as a reference to indicate IE Notice #88-063 high radiation area controls are 2

NER 910813001 addressed in the implementation of this Instruction. Cancelled by Revision 44.

Transfer information denoted in Self-Assessment 3 previous Source Note C.1 to RCI-15 per

  1. SQ-RP-00-002 this Self-Assessment.

JPM SRO Admin D Page 1 of 9 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SROADMIND Classify the Event per the REP (SGTR with Failed SIG Safety)

JPM SRO Admin D Page 2 of 9 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Classify the Event per the REP (SGTR with Failed S/G Safety)

Task #: (SRO) 3440030302; (SRO) 3440190302 Task Standard: The event is classified as a GENERAL EMERGENCY based on Loss of 3 fission barriers (SGTR with Failed SIG Safety).

Time Critical Task: YES: X NO:

KIA ReferencelRatings: 2.4.38 (2.4/4.4) 2.4.44 (2.4/4.4)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

JPMSROAdmin D Page 3 of 9 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
2. Any UNSAT requires comments
3. Ensure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.

Tools/Equipment/Procedures Needed:

EPIP-1 thru EPIP-5, for each student in classroom FR Procedures Steam Tables, for each student in classroom Clock must be available in classroom that all examinees and evaluator can see

References:

Reference

1. EPIP-1 Title Emergency Plan Classification Matrix Rev No. 1 43
2. EPIP-5 General Emergency 39 READ TO OPERATOR DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All steps of this JPM shall be performed in a classroom or in the simulator (simulator will not be set up to match the scenario). The evaluator will provide initiating cues and any other data that may be needed. Time begins when directed by evaluator. When the declaration has been made, raise your hand, the evaluator will record the time, and then you may continue the procedure. Raise your hand again when you have completed the TVA Initial Notification Form, to the point of notifying the ODS. If during the performance of the JPM you have any questions raise your hand and the evaluator will assist you.

INITIAL CONDITIONS:

1. Unit 2 is at 100% RTP and stable.
2. Unit 1 has experienced a Reactor trip and Safety Injection.
3. Security reports that at the time of the trip, steam started blowing from the roof of the Unit I west valve vault and steam flow is still in progress at this time.
4. Steam Generator #1 is isolated per E-3, Steam Generator Tube Rupture.
5. CR0 has informed you that SG #1 pressure is slowly lowering.
6. Containment pressure is .5 psig.
7. RCS pressure is 1500 psig.
8. Core exit TCs 532 °F and slowly rising.
9. The most recent Chem Lab sample of RCS indicates that RCS activity has risen to 345 pCi/gm Equivalent Iodine-i 31.
10. Emergency Paging System (EPS) is not available in MCR.
11. There are no indications of an Onsite Security Event.

INITIATING CUES:

1. You are the Unit 1 US and have assumed the duties of the SED position, until the TSC is staffed.
2. You are to perform each of the following:
a. Classify this event per EPIP-1 and
b. Fill out WA Initial Notification Form and make Protective Action Recommendations, if any.

This is a time critical JPM, Time begins when directed by evaluator.

JPMSROAdmin D Page 4 of 9 Rev. 0 Job Performance Checklist:

STEP I STANDARD SAT I UNSAT STEP 1.: ReferS to EPIP-1 to detemijie level of event SAT UNSAT STANDARD: Operator refers to EPIP-1, Section 1, Fission Product Barrier Matrix. Operator determines that they have met the conditions of: Critical Ste I 1.1.2 Loss, Primary Coolant Activity Level Task Start 1.2.3 Loss, SGTR Time 1.3.4 Loss, Containment Bypass Declaration of event must be made in 15 minutes from the time the task was accepted.

Record Time of Declaration:_________________

Time from Task Acceptance to Declaration:____________

Utilizing Emergency Class Criteria, operator determines the need to declare a General Emergency based on Loss of all 3 barriers.

Time of declaration is recorded when the operator raises his/her hand.

This is a critical step to arrive at the correct classification within 15 minutes.

COMMENT:

STEP 2.: Implements EPIP-5 GENERAL EMERGENCY, section 3.1, SAT

[1] If TSC is OPERATIONAL, (SED transferred to TSC), THEN GOTO. UNAT STANDARD: Operator should recall that the TSC has not been manned per the initiating cues, N/As this step and moves on to the next step.

COMMENT:

STEP 3. [2] RECORD time of declaration. TIME SAT NOTE: Operator may have already stated time of declaration, but must enter UNSAT time properly in EPIP-5 form.

STANDARD: Operator enters proper time that declaration was made.

COMMENT:

JPM SRO Admin D Page 5 of 9 Rev. 0 Job Performance Checklist:

STEPISTANDARD SATIIJNSAT Evaluator Note: Candidate may choose to N/A entire step based on Initiating Cue of EPS not available, if so then N/A JPM steo 4 and no to JPM steo 4. If steo 3 is comoleted then the followina will aDolv.

STEP 4.: [3] Activate Emergency Paging System (EPS). SAT UNSAT STANDARD: Operator recalls from initial conditions, that EPS is not available from the control room, N/As step and continues on to next step.

COMMENT:

STEP 5.: [3] Activate Emergency Paging System (EPS). SAT

[a] IF EPS has already been activated, then go to step 4.

UNSAT STANDARD: Operator recalls from initial conditions, that EPS has not been previously activated and N/As step.

COMMENT:

STEP 6.: [3] Activate Emergency Paging System (EPS). SAT

[b] If ongoing onsite Security events may present risk to the emergency responders, Then consult with Security to determine if UNSAT site access is dangerous to the life and health of emergency responders.

STANDARD: Operator recalls from initial conditions, that there are no site security threats present and N/As step.

COMMENT:

STEP 7.: [3] Activate Emergency Paging System (EPS). SAT

[c] If ongoing events makes site access dangerous to the life and health of emergency responders, Then select staging area button UNSAT on the EPS terminal INSTEAD of the EMERGENCY button.

STANDARD: Operator recalls from initial conditions, that EPS system not available, so N/As step.

COMMENT:

JPM SRO Admin D Page 6 of 9 Rev. 0 Job Performance Checklist:

STEP I STANDARD SAT I UNSAT STEP 8.: [3] Activate Emergency Paging System (EPS). SAT

[ci ACTIVATE EPS using touch screen terminal. IF EPS fails to activate, THEN continue with step 4. UNSAT STANDARD: Operator recalls from initial conditions, that EPS system not available, so N/As step.

COMMENT:

STEP 9.: [ SAT UNSAT STANDARD: Operator determines from Appendix B, logic chart in EPIP-5, Note Critical Step 1: if conditions are unknown then answer is NO, that appropriate protective action recommendation is RECOMMENDATION 2.

This step is critical to arrive at the correct PAR recommendation COMMENT:

Evaluator Note: When candidate raises their hand to ask for MET tower data, hand them a copy of the MET TOWER LINK data sheet for their use in developing the affected sectors for Protective Action Recommendations.

JPM SRO Admin D Page 7 of 9 Rev. 0 Job Performance Checklist:

STEP I STANDARD SAT I UNSAT STEP 10.: SAT U N SAT STANDARD: Operator completes the Appendix C through step 8, using information from turnover sheet and EPIP-1, prior to Notifying Critical Step the ODS.

1. This is a Drill
2. This is [Their name, Shift Manager (SED) Sequoyah has declared a General Emergency affecting Unit 1.
3. EAL Designators: LOSS 1.1.2 and LOSS 1.2.3, and LOSS 1.3.4.
4. Brief description of incident: [Primary Coolant Activity Level, SGTR AND Containment Bypass].
5. Radiological Conditions [Release information not known]
6. Event Declared: [Time and Date]
7. Meteorological Conditions are: Wind direction at 46 meters

[Northeast at 17 degrees] AND wind speed at 46 meters [3.8 mph]

8. Protective Action Recommendation: [2 Evacuate 2 mile radius and 5 miles downwind A-I, B-I, C-I, D-I, C-2, D-2, and shelter remainder of 10 mile EPZ], consider issuance of POTASSIUM IODIDE in accordance with the State Plan.
9. Please repeat back the information you have received to ensure accuracy.
10. Fax information to ODS This is a critical step to ensure information is accurate.

COMMENT:

JPM SRO Admin D Page 8 of 9 Rev. 0 Job Performance Checklist:

STEP I STANDARD SAT I UNSAT STEP 11.: [6] Notify ODS. SAT UNSAT NOTE: Evaluator Enter time call is made to the ODS Critical Step Time from Declaration (step 1) to ODS Notification________

Stop Time:

STANDARD: Candidate raises their hand as signal that they have completed TVA initial Notification form and are ready to Notify the ODS.

ODS should be notified within 10 mm after declaration of the event.

This is a critical step to (complete forms within 10 mm) to ensure required notifications are completed within required time.

Cue: This completes the JPM.

COMMENTS:

READ TO OPERATOR DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All steps of this JPM shall be performed in a classroom or in the simulator (simulator will not be set up to match the scenario). The evaluator will provide initiating cues and any other data that may be needed. Time begins when directed by evaluator. When the declaration has been made, raise your hand, the evaluator will record the time, and then you may continue the procedure. Raise your hand again when you have completed the TVA Initial Notification Form, to the point of notifying the ODS. If during the performance of the JPM you have any questions raise your hand and the evaluator will assist you.

INITIAL CONDITIONS:

1. Unit 2 is at 100% RTP and stable.
2. Unit 1 has experienced a Reactor trip and Safety Injection.
3. Security reports that at the time of the trip, steam started blowing from the roof of the west valve vault and steam flow is still in progress at this time.
4. Steam Generator #1 is isolated per E-3, Steam Generator Tube Rupture.
5. CR0 has informed you that SG #1 pressure is slowly lowering.
6. Containment pressure is .5 psig.
7. RCS pressure is 1500 psig.
8. Core exit TCs 532 °F and slowly lowering.
9. The most recent Chem Lab sample of RCS indicates that RCS activity has risen to 345 pCi/gm Equivalent Iodine-I 31.
10. Emergency Paging System (EPS) is not available in MCR.

11 .There are no indications of an Onsite Security Event.

INITIATING CUES:

1. You are the Unit I US and have assumed the duties of the SED position, until the TSC is staffed.
2. You are to perform each of the following:
a. Classify this event per EPIP-I And
b. Fill out TVA Initial Notification Form and make Protective Action Recommendations, if any.

This is a time critical JPM, Time begins when directed by evaluator

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-5 GENERAL EMERGENCY REVISION 39 PREPARED BY: BILL PEGGRAM RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: RUSSELL THOMPSON EFFECTIVE DATE: 02/19/2010 LEVEL OF USE: REFERENCE USE QUALITY-RELATED

SEQUOYAH GENERAL EMERGENCY EPIP-5 1 Revision History Rev Date Reason for Revision 30 04/01/2003 General Revision to restructure EPIP for better flow. Moved ODS notification earlier in procedures. Added evacuation sectors to Initial Notification Appendix and to consider issuance of KI in accordance with the State Plan in the PAR. Intent Change.

31 06/25/2003 9, 14 Non intent change. Phone number correction. Changed title of Appendix B and added note o match Figure 10-1 of the WA REP.

32 10/23/2003 4, 8, 12, 13 Intent change. Added step to record time of declaration upon entry into the procedure. Steps concerning dose assessment, PAR, PAR changes, and announce GE to Plant Mgmt., NRC, SM/SED that notifications are complete.

Split step that had two actions in one step. Specified Security implement EPIP-1 I 33 04/22/2004 3, 6, 13 Intent Change: Made corrections to the Table of Contents making sections titles consistent with EPIPs 3,4 and sections within the procedure. Added SEDs Initials to Section 3.2. Clarified that MSS/V\RNM in the OSC is verifying ERO response and that SM is to ENSURE that this is in progress.

Added guidance to utilize EPIP-6 Apdx B to initially brief NRC using ENS line.

34 09/23/2004 6, 7, 8, 9, 13 Intent Change: Changed Bradley County EMA phone number, removed TEMA satellite phone numbers, added classification validation to Sect.3.2, moved transfer of PARs from Sect. 3.3 to Sect 3.2 App. A: added to GE announcement to staff TSC/OSC and corrected SAE to General Emergency.

35 06/10/2005 4, 14, 15, 16 Revision Change: replaced SSI-1 with SSI-7.1. Replaced the PAR Chart with the new PAR Chart, NRC Regulatory Issue Summary 2004-1 3. which addressed the range of protective actions that includes sheltering for the public.

36 04/28/2006 15,16 Revision summary: Changed App.C, Step 10 from being the time and date info was provided to the ODS to faxing App. C to the ODS. Made App. D consistent with App. C by putting THIS IS A DRILL before THIS IS A REAL EVENT.

Plan effectiveness determinations reviews indicate the following revisions do not 37 01/23/2007 6, 7, 8, 12, 13 reduce the level of effectiveness of the procedure of REP: Changed the phone number for Bradley County. Changed the call to request a dose assessment from Chemistry to Radiation Protection and changed the corresponding phone numbers so that calls are directed to the RP Lab and no longer the Chem Lab.

Changed to current organization titles, added to make Alert announcement on old plant PA and the x4800 bridge. Annual review. Revised responsibility of dose assessment from Chemistry to RP.

Plan effectiveness determinations reviews indicate the following revisions do not 38 12/15/2008 8, 11, 15 reduce the level of effectiveness of the procedure of REP. Annual Review.

Added a place keeping box in Sect. 3.3[1]. Clarified use of App C when a PAR is changed and CECC has not been activated. Changed SHELTER wording on App. C to match the PAR chart wording on recommendations 1&2.

39 02/19/2010 15 Revision Summary: Plan effectiveness determinations reviews indicate the following revisions do not reduce the level of effectiveness of the procedure of REP: Annual review. PER 162926-001, Revised Appendix C to change step 10 to say, When completed, FAX this information to the ODS or TEMA as required by Sections 3.1 or 3.2.

FORWARD COMPLETED PROCEDURE TO PAGE 2 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 Table of Contents 1.0 PURPOSE 4

2.0 REFERENCES

4 3.0 INSTRUCTIONS 4 3.1 General Emergency Declaration by the Main Control Room 4 3.2 General Emergency Declaration by the TSC 7 3.3 Monitor Conditions 8 3.4 Termination of the Event 10 4.0 RECORDS RETENTION 11 4.1 Records of Classified Emergencies 11 4.2 Drill and Exercise Records 11 5.0 ILLUSTRATIONS AND APPENDICES 11 5.1 Appendix A, Notifications and Announcements 12 5.2 Appendix B, Protective Action Recommendations 14 5.3 Appendix C, TVA Initial Notification of General Emergency 15 5.4 Appendix D, General Emergency Follow-up Information 16 FORWARD COMPLETED PROCEDURE TO PAGE 3 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 1.0 PURPOSE I .1 To provide a method for timely notifications of appropriate individuals or organizations when the Shift Manager (SM)/Site Emergency Director (SED) has determined by EPIP-1 that events have occurred that are classified as a GENERAL EMERGENCY (GE).

1.2 To provide the SED/SM a method for periodic reanalysis of current conditions to determine whether the GENERAL EMERGENCY should be terminated or continued.

2.0 REFERENCES

2.1 Interface Documents

[I] SPP-3.5 Regulatory Reporting Requirements

[2] EPIP-6, Activation and Operation of the Technical Support Center

[3] EPIP-7, Activation and Operation of the Operations Support Center, OSC

[4] EPIP-8, Personnel Accountability and Evacuation

[5] EPIP-lO, Emergency Medical Response

[6] EP I P-I 3, Dose Assessment

[7] EPIP-14, Radiation Protection Response

[8] EPIP-16, Termination and Recovery

[9] CECC EPIP-9, Emergency Environmental Radiological Monitoring Procedures

[10] SSI-7.1, Post Requirements and Responsibilities, Central and Secondary Alarm Stations 3.0 INSTRUCTIONS NOTE: IF there are personnel injuries, THEN IMPLEMENT EPIP-lO, Emergency Medical Response in parallel with this procedure.

NOTE: IF there are immediate hazards to plant personnel, THEN consider immediately implementing EPIP-8 Personnel Accountability and Evacuation in parallel with this procedure 3.1 GENERAL EMERGENCY DECLARATION BY THE MAIN CONTROL ROOM Upon classifying events as a GENERAL EMERGENCY, the SM/SED shall:

[1] IF TSC is OPERATIONAL, (SED transferred to TSC), THEN GO TO Section 3.2. El

[2] RECORD time of Declaration Time FORWARD COMPLETED PROCEDURE TO PAGE 4 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 3.1 GENERAL EMERGENCY DECLARATION BY THE MAIN CONTROL ROOM (Continued)

[31 ACTIVATE Emergency Paging System (EPS) as follows.

[a] IF EPS has already been activated, THEN GO TO Step 4. El

[b] IF ongoing onsite Security events may present risk to the emergency responders, THEN CONSULT with Security to determine if site access is dangerous to the life and health of emergency responders. El

[C] IF ongoing events makes site access dangerous to the life and health of emergency responders, THEN SELECT STAGING AREA button on the EPS terminal INSTEAD of the EMERGENCY button. El

[d] ACTIVATE EPS using touch screen terminal. IF EPS fails to activate, THEN continue with step 4. El

[4] EVALUATE Protective Action Recommendations (PARs) using Appendix B. El

[5] COMPLETE Appendix C (TVA Initial Notification for General Emergency). El NOTE: ODS should be notified within 5 minutes after declaration of the event.

[6] NOTIFY ODS.

Inital Time ODS: Ringdown Line or 5-751-1700 or 5-751-2495 or 9-785-1700

[a] IF EPS failed to activate from SQN, THEN DIRECT ODS to activate SQN EPS. IF ODS is also unable to activate EPS, THEN continue with step [5] [b]. El

[b] READ completed Appendix C to ODS. El

[C] FAX completed Appendix C to ODS.

5-751-8620 (Fax)

[di MONITOR for confirmation call from ODS that State/Local notifications complete: RECORD time State notified.

Notification Time FORWARD COMPLETED PROCEDURE TO PAGE 5 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 3.1 GENERAL EMERGENCY DECLARATION BY THE MAIN CONTROL ROOM (Continued)

[7] IF ODS CANNOT be contacted within 10 minutes of the declaration, THEN

[a] CONTACT Hamilton County Emergency Management Agency (EMA) AND READ completed Appendix C.

Initial Time 9-209-6900 or 9-622-7777 or 9-622-0022

[b] CONTACT Bradley County EMA AND READ completed Appendix C.

Initial Time 9-728-7289 or 9-728-7290

[c] NOTIFY Tennessee Emergency Management Agency (TEMA) AND READ completed Appendix C.

Initial Time 9-1-800-262-3300 or 9-1-615-741-0001

[d] FAX completed Appendix C to TEMA.

9-1-615-242-9635 (Fax)

[8] ENSURE MSSIWWM in the OSC (x6427 ) is monitoring Emergency Response Organization (ERO) responses using printed report available in the OSC.

[a] IF any ERO positions are not responding, THEN DIRECT MSS to CALL personnel to staff TSC/OSC positions. (Use REP Duty Roster and Call List.) U

[9] NOTIFY plant staff using Appendix A. (Delegate as needed.)

[10] GO TO Section 3.3 FORWARD COMPLETED PROCEDURE TO PAGE 6 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 3.2 GENERAL EMERGENCY DECLARATION BY THE TSC Upon classifying events as a GENERAL EMERGENCY, the SED shall:

NOTE: CECC Director should be notified within 5 minutes after declaration of the event.

[1] RECORD Time of Declaration

[2] RECORD EAL(s)

[3] VALIDATE time and EAL numbers with the Ops Mgr, Site VP or EP Mgr.

[4] IF PAR responsibility has NOT been transferred to the CECC Director,

[a] THEN REFER to Appendix B (Protective Action Recommendations) El

[b] FAX Appendix C (Notification of General Emergency) to CECC Director U

[5] CALL CECC Director and inform of escalation, time of declaration, EAL(s) declared, and description of events.

SEDs Initials Time Ringdown Line or 5-751-1614 or 5-751-1680

[6] IF CECC Director CANNOT be contacted within 10 minutes of the declaration, THEN

[a] COMPLETE Appendix C (TVA Initial Notification for General Emergency) using Appendix B to evaluate Protective Actions.

[b] NOTIFY Hamilton County EMA AND READ Appendix C.

SEDs Initials Time 9-209-6900 or 9-622-7777 or 9-622-0022

[c] NOTIFY Bradley County EMA AND READ Appendix C.

SEDs Initials Time 9-728-7289 or 9-728-7290 FORWARD COMPLETED PROCEDURETO PAGE 7 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 3.2 GENERAL EMERGENCY DECLARATION BY THE TSC

[d] NOTIFY TEMA AND READ completed Appendix C.

SEDs Initials Time 9-1-800-262-3300 or 9-1-615-741-0001

[e] FAX completed Appendix C to TEMA. LI 9-1-615-242-9635 (Fax) 3.3 MONITOR CONDITIONS

[1] MONITOR radiation monitors.

[2] WHEN indication exists of an unplanned radiological release, THEN ENSURE Dose Assessment is performed. LI

[a] IF the CECC has not assumed Dose Assessment responsibility, THEN NOTIFY Radiation Protection to perform a dose assessment using EPIP-13, Dose Assessment AND PROVIDE the following information:

1. Type Of Event (SGTR/L, LOCA, WGDT, Cntmt Bypass)
2. Release Path (SG/PORV, Aux, Shid, Turb, Serv, Cond)
3. Expected Duration (If unknown assume 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duration) LI 7865 (RP Lab) or 6417 (RP Lab) or Use Call List to Page RP Lead

[b] IF changes to PARs are necessary, THEN complete Appendix C (IF CECC has not assumed responsibility for PARs) and D.

CAUTION: Accountability should NOT be initiated at this time IF Assembly will present a danger to employees For example:

A severe weather condition exists or is imminent (such as a Tornado)

An onsite Security risk condition exists (Consult with Nuclear Security)

[3] IF personnel accountability has not been previously initiated, THEN ACTIVATE assembly and accountability by using EPIP-8, Appendix C (may be delegated). LI FORWARD COMPLETED PROCEDURE TO PAGE 8 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 3.3 MONITOR CONDITIONS (Continued)

[4] MONITOR plant conditions:

[a] EVALUATE conditions using EPIP-1:

[1] IF additional conditions satisfy criteria of other GENERAL EMERGENCY(s) THEN complete Appendix D. El

[2] IF conditions warrant a need for follow-up information, THEN complete Appendix D.

[b] IF Appendix D completed, THEN

[1] REPORT to CECC for State notification.

Initial Time CECC Director: Ringdown Line or 5-751-1614 or 5-751-1680 OR ODS: Ringdown Line or 5-751-1700 or 5-751-2495 or 9-785-1700

[2] FAX completed Appendix D to CECC.

CECC: 5-751-1 682 (Fax) OR ODS: 5-751-8620 (Fax)

[3] IF neither the CECC or ODS can be reached, THEN

[a] NOTIFY TEMA AND READ completed Appendix D.

Initial Time 9-1-800-262-3300 or 9-1-61 5-741-0001

[b] FAX completed Appendix D to TEMA. El 9-1-615-242-9635 (Fax)

FORWARD COMPLETED PROCEDURE TO PAGE 9 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERALEMERGENCY EPIP-5 3.4 TERMINATION OF THE EVENT

[1] IF the situation no longer exists, THEN

[a] TERMINATE emergency per EPIP-16, Termination and Recovery.

[b] COMPLETE Appendix D including Time and Date Event Terminated. LI

[ci FAX completed Appendix D to CECC Director. LI ODS: 5-751-8620 (Fax) OR CECC: 5-751-1682 (Fax)

[2] COLLECT documentation and FORWARD to Emergency Preparedness. El END OF SECTION FORWARD COMPLETED PROCEDURE TO PAGE 10 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 4.0 RECORD RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency classified as NOUE or higher are considered Lifetime retention Non-QA records. Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.

4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.

5.0 ILLUSTRATIONS AND APPENDICES 5.1 Appendix A - Notifications and Announcements Appendix A provides guidance for security threats, and for prompt notification of the NRC Resident and plant personnel.

52 Appendix B - Protective Action Recommendation Logic Diagram Appendix B, Protective Action Recommendation Logic Diagram, is used to determine the Protective Action Recommendation which is made to the State and is part of the initial notification made to the State. Protective Action Recommendations are the responsibility of the CECC Director after assuming the responsibility from the SED.

5.3 Appendix C - WA Initial Notification of General Emergency Appendix C, TVA Initial Notification of General Emergency, is the form used to initially notify the Operations Duty Specialist who notifies the Tennessee Emergency Management Agency.

5.4 Appendix D - General Emergency Follow-up Information Appendix D, General Emergency Follow-up Information is the form used to provide additional information concerning other General Emergencies or other information concerning additional conditions to the ODS for State notification and event termination.

FORWARD COMPLETED PROCEDURE TO PAGE 11 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 Appendix A NOTIFICATIONS AND ANNOUNCEMENTS (Page 1 of 2)

[1] IF there is a security threat, THEN

[a] NOTIFY Security Shift Supervisor to implement SSI-1, Security Instructions For Members Of The Security Force and EPIP-1 I Security and Access Control.

Initial Time 6144 or 6568

[b] DETERMINE if Security recommends implementing the Two Person Line of Sight Rule. D

[C] IF Nuclear Security recommends establishing the Two Person Line of Sight Rule, THEN INFORM the SM/SED.

(Two Person Line of Sight requires use of EPIP-8.)

Initial Time

[2] NOTIFY Radiation Protection Lead:

[a] STATE: A GENERAL EMERGENCY HAS BEEN DECLARED, BASED UPON (Describe the conditions),

AFFECTING UNIT(s)

Initial Time 7865(RP Lab) or 6417,(RP Lab)

Use Call List to Page RP Lead

[b] DIRECT Radiation Protection to implement EPIP-14, Radiation Protection Response.

[C] DIRECT Radiation Protection to implement CECC EPIP-9, Emergency Environmental Radiological Monitoring Procedures which includes activation of the radiological monitoring van. E

[3] NOTIFY personnel in the Chemistry Lab:

[a] STATE: A GENERAL EMERGENCY HAS BEEN DECLARED, BASED UPON (Describe the conditions),

AFFECTING UNIT(s)

Initial Time 7285 (Lab) or 6348 (Lab) or 20126 (Pager)

[b] DIRECT Chemistry to implement EPIP-14, Radiation Protection Response.

FORWARD COMPLETED PROCEDURE TO PAGE 12 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 Appendix A NOTIFICATIONS AND ANNOUNCEMENTS (Page 2 of 2)

[4] ANNOUNCE to plant personnel on old plant PA and x4800:

[a] ATTENTION PLANT PERSONNEL. ATTENTION PLANT PERSONNEL. A GENERAL EMERGENCY HAS BEEN DECLARED BASED ON ( Describethecondition ), AFFECTING UNIT(s) (if not already staffed, add) STAFF THE TSC AND OSC.I

[b] REPEAT Announcement. 0

[5] NOTIFY Plant Management in accordance with SPP-3.5 AND PROVIDE General Emergency Information.

Initial Time

[6] NOTIFY the On Call NRC Resident AND PROVIDE General Emergency Information.

Initial Time NOTE: NRC ENS notification should be made as soon as practicable, but within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of GENERAL EMERGENCY declaration. Whenever NRC requests, a qualified person must provide a continuous update to NRC Operations Center. Use EPIP-6, Appendix B as a briefing guide.

[7] NOTIFY NRC of plan activation via ENS phone Initial Time 9-1 -(301) 816-5100 (Main) 9-1 -(301) 951-0550 (Backup) 9-1 -(301) 816-5151 (Fax)

[8] NOTIFY the SM/SED that notifications are complete.

Initial Time FORWARD COMPLETED PROCEDURE TO PAGE 13 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

SEQUOYAH GENERAL EMERGENCY EPIP-5 Appendix B PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown utilizing the flowchart, then answer is NO.

Note 2: A short term release is defined as a release that does not exceed a 15 minute duration.

ERAL EMERGE CONTINUE ASSESSMENT

  • Modify protective actions based on available plant and field monitoring information.
  • Locate and evaluate localized hot spots.

Is there a sho rt term controlled NO release whereas near plant areas cannot be eva cuated before ume arrival?

Note 2)

YES NO YES SHELTER 10 mile EPZ 1 Jr RECOMMENDATION I RECOMMENDATION 2 EVACUATE 2 miles radius EVACUATE 2 miles radius and 10 miles downwind and 5 miles downwind AND AND SHELTER remainder of SHELTER remainder of 10 mile EPZ 10 mile EPZ 1 Jr Note: Unknown TABLE I Protective Action Guides (PAG) conditions are TYPE LIMIT assumed less than Measured 3.9 E-6 micro Ci/cc of Iodine 131 or listed conditions.

I REM per hour External Dose Projected 1 REM TEDE or 5 REM Thyroid ODE FORWARD COMPLETED PROCEDURE TO PAGE 14 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

GENERAL SEQUOYAH EMERGENCY EPIP-5 Appendix C WA INITIAL NOTIFICATION OF GENERAL EMERGENCY

1. El This is a Drill El This is an Actual Event - Repeat - This is an Actual Event
2. This is Sequoyah has declared a GENERAL EMERGENCY affecting: El Unit 1 El Unit 2 El Both Unit 1 and Unit 2
3. EAL Designator(s):
4. Brief Description of the Event:
5. Radiological Conditions: (Check one under both Airborne and Liquid column.)

Airborne Releases Offsite Liquid Releases Offsite El Minor releases within federally approved limits 1 El Minor releases within federally approved limits 1 El Releases above federally approved limits 1 El Releases above federally approved limits 1 El Release information not known El Release information not known Tech Specs) 1

( Tech Specs) 1

(

6. Event Declared: Time: Date:
7. The Meteorological Conditions are: (Use 46 meter data from the Met Tower)

Wind Direction is FROM: Wind Speed: m.p.h

8. Provide Protective Action Recommendation: (Check either 1 or 2 or 3.)

El Recommendation I R WIND FROM El Recommendation 2

  • EVACUATE LISTED SECTORS (2 mile Radius E *DEGREES E
  • EVACUATE LISTED SECTORS (2 mile and 10 miles downwind) Radius and 5 mile downwind)

DIRECTION SHELTER remainder of 10 mile EPZ

  • SHELTER remainder of 10 mile EPZ *

(item 7) CONSIDER issuance of POTASSIUM

  • CONSIDER issuance of POTASSIUM IODIDE in (Mark) accordance with the State Plan. IODIDE in accordance with the State Plan.

A-lB-IC-iD-i, C-2,-6,-7,-8,D-2,-3,-5,-6 - 12-49 A-lB-iC-iD-i, C-2,D-2 A-i,B-i,C-i,D-1, D-2,-3,-4,-5,-6 50-70 A-lB-iC-iD-I, 0-2 A-lB-IC-iD-i, A-3,-4, D-2,-3,-4,-5 - 71-112 A-i,B-i,C-i,D-1, A-3,D-2 A-i,B-i,C-i,D-1, A-2,-3,-4,-5,-6, 0-4 - 113-146 A-i,B-i,C-i,D-1, A-2,A-3, A-i, B-i, C-i, D-i, A-2, 4, -5, -6, B-2 147- 173 A-i, B-i, C-i, D-1, A-2, A-3, B-2 A-1,B-i,C-i,D-i, A-2,-5,-6, B-2,-3,-4 - 174-214 A-i,B-i,C-i,D-1, A-2,B-2, A-I, B-i, C-i, D-i, B-2, 4, 6, -7,-8 215- 258 A-i, B-i, C-I, D-i, B-2, B-5, A-lB-IC-ID-i, B-2,-3,-5,-6,-7,-8, C-2,-3,-4,-5,-6 259-331 A-1,B-i,C-i,D-1, B-2,B-5,C-2 A-lB-iC-iD-i, B-5, C-2,-3,-4,-5,-6,-7,-8 332-il A-1,B-i,C-i,D-i, B-5,C-2 El Recommendation 3 -

SHELTER all sectors.

CONSIDER issuance of Potassium Iodide in accordance with the State Plan.

9. Please repeat back the information you have received to ensure accuracy. El
10. When completed, FAX this information to the ODS or TEMA as required by Sections 3.1 or 3.2. El FORWARD COMPLETED PROCEDURE TO PAGE 15 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER

GENERAL SEQUOYAH EMERGENCY EPIP-5 Appendix D GENERAL EMERGENCY FOLLOW-UP INFORMATION

1. El THIS ISA DRILL El THIS ISA REAL EVENT
2. There has been a GENERAL EMERGENCY declared at Sequoyah affecting:

El Unit 1 El Unit 2 El Both Unit 1 and Unit 2

3. Reactor Status: Unit 1: El Shut Down El At Power El Refueling El N/A Unit 2: El Shut Down El At Power El Refueling El N/A
4. Additional EAL Designators
5. Significant Changes in Plant Conditions:
6. Significant Changes in Radiological Conditions:
7. Offsite Protective Action Recommendation: (CECC to provided detailed PAR Sector Recommendations)

El Recommendation 1 -

Evacuate 2 mile radius and 10 miles downwind and shelter remainder of the 10 mile EPZ El Recommendation 2 -

Evacuate 2 mile radius and 5 miles downwind and shelter remainder of the 10 mile EPZ El Recommendation 3 Shelter all sectors.

8. Onsite Protective Actions: Assembly and Accountability El No El Initiated El Completed Site Evacuation El No El Initiated El Completed
9. The Meteorological Conditions are: Wind Speed:

(Use 46 meter data on the Met Tower) Wind Direction is from:

10. Event Terminated: Date/Time
11. Please repeat the information you have received to ensure accuracy. \El
12. FAX to ODS at 5-751-8620 or CECC Director at 5-751-1682 after completing the notification. El Completed by: Date/Time FORWARD COMPLETED PROCEDURE TO PAGE 16 of 16 REVISION 39 EMERGENCY PREPAREDNESS MANAGER