Text

Initial Exam 2014-301 Final Administrative JPMs
	ML14154A383
Person / Time
Site:	Browns Ferry
Issue date:	06/02/2014
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
Shared Package
ML14155A059	List: ML14154A324; ML14154A337; ML14154A346; ML14154A365; ML14154A369; ML14154A373; ML14154A377; ML14154A383; ML14154A390; ML14154A393; ML14154A396; ML14154A399;
References
	50-259/OL-14, 50-260/OL-14, 50-296/OL-14
	Download: ML14154A383 (81)
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JPM SRO/RO Ala OPERATOR:

RO DATE:________

JPM NUMBER: SRO RD Ala TASK NUMBER: U-000-NO-47 TASK TITLE: Determine Electrical Safety requirements and the correct procedural requirements to Rack Out 480V SD BD 2A compartment 7A supply for Control Bay Chiller 3A K/A NUMBER: 2.1.26 K/A RATING: RO 3.4 SRO 3.6 TASK STANDARD: Determine the correct procedural section to rack out 480V SD BD 2A Compartment 7A breaker, the verification requirement and the Electrical Safety PPE and Protective Boundary requirement LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: 0-GOI-300-2, TI-300 Attachment 1 and TI-300, NPG-SPP- 10.3 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMINER 1

V\iJ

JPM SROIRO Ala INITIAL CONDITIONS:

You are an operator.

All three units are operating at 100% power.

The breaker for 480V SD BD 2A, Compartment 7A is OPEN.

The equipment supplied by this breaker has been removed from service in accordance with the applicable operating instruction.

It is now desired to rack out Compartment 7A to hang a clearance tag.

INITIATING CUE:

Your task is to determine:

1) The required procedure to rack out this breaker compartment

2) ALL personnel protective measures

3) The MiNIMUM required human performance verification method(s) needed to rack out the breaker and hang a clearance tag.

2

JPM SROIRO Ala Class Room INITIAL CONDITIONS:

You are an operator.

All three units are operating at 100% power.

The breaker for 480V SD BD 2A, Compartment 7A is OPEN.

The equipment supplied by this breaker has been removed from service in accordance with the applicable operating instruction.

It is now desired to rack out Compartment 7A to hang a clearance tag.

INITIATING CUE:

Your task is to determine:

1) The required procedure to rack out this breaker compartment

2) ALL personnel protective measures

3) The MINIMUM required human performance verification method(s) needed to rack out the breaker and hang a clearance tag.

3

JPM SRO/RO Ala START TIME____

Performance Step 1: Critical Not Critical Refers to 0-GOI-300-2, Electrical and Illustration 7 for 480V SD BD 2A Compartment 7A.

Illustration 7 (Page 10 of 34) 4KV/480/250 Breaker Application Matrix ELECTRICAL BOARD Compt {MP MP (AK NTJ NT 3A-25}

GOI 300-2 RACK-OUT Section (5.17) 5.13 (5.19)

GOI 300-2 RACK-IN Secion (5.18) 5.14 (8.20) 480v Shutdown Bd 2A 1C 7A X I Standard:

Determines 0-GOI-300-2 section 5.13 SAT_ UNSAT_ N/A _COMMENTS:___

4

JPM SRO/RO Ala Performance Step 2: Critical Not Critical Refers to section 5.13 which provides the PPE procedure for racking out the breaker 5.19 GE 480V Manually Operated Breakers Type AK-15(25) with Racking Screw racking mechanism, RACK-OUT Checklist NOTE Found on 480V Shutdo wn, Unit, Comm on, Lighting boards, and Service Bldg vent boards.

[1] NOTIFY affected Unit Operator(s) of breaker being racked-out.

[2] REVIEW Precautions and Limitations listed in Section 3.0.

[3] OBTAIN personal protective equipment (PPE) in accordance with Health and Safety Manual TI-300 Electrical Safe Work Practices.

Standard:

Determines Electrical Safety requirements are listed in TI-300 SAT_ UNSAT N/A COMMENTS:_____________

5

JPM SRO/RO Ala Performance Step 3: Critical Not Critical Refers to TI-300, Electrical Safe Work Practices C. Arc-Flash Annually, 80% of electrical injuries are caused by bums from radiant energy.

Since arc-flashes vary greatly in size and intensity, TVA has put an extensive program in place to quantify the arc-energy present at each bus in the facility.

1. Hazardous Arc-Flash Incident energy in excess of 1 .2cal/cm2 will result in 2nd or 3rd degree bums. For all 48Ovolt and 4,l6Ovolt equipment within the owner controlled area at Browns Ferry, PPE to protect from this hazard is required.

Different equipment configurations can produce different hazards. Select the PPE for all 480v and 4,160 volt work from the matrix in Attachment 1.

Standard:

Proceeds to TI-300 Attachment, Electrical Safe Work Practices: Arc Flash Personal Protective Equipment / Protective Boundary Matrices SAT_ UNSAT_ N/A COMMENTS:__________________________

6

JPM SRO/RO Ala Performance Step 4: Critical Not Critical Electrical PPE Matrix 0 q

Notes:

NOTE 1: Gloss 0O gloves are reguirec when contact edit &I-300v is required or edwr acddeetal contact ts Skety NOTE 2: Glass gloves e4d leather protectors are requtred when witirrr foot z a a of exposed 480 scIls.

6 NOTE 3: Class 1 gloves wIth leather protectors. OR gloves rated for SO catfcm, 0 0 are reqtred when withIn 1 foot of 480V or 4 feet Of exposed 4kv. tee callcrnr, NOTE & Class 1 gloves eMit leafier protectors. OR gloves rated for 75 0 S are reqiared wIse.-. wigir 1 foot of 480V or4 feet of exoosed 4kv. 4)

NOTE 5: Class gloves are used in 480v appbcaliorrs whet. calculated lncdient Energy lovets are above ED cal1cnr wid tee er.ergzed corn onent is within 1 foot.

NOTE 6: Hard flat riot reqiured Electrloai PPE. Ret. WA Safety Manual, 1022. E U.

GENERAL: Exposed, energized 480v arid 4kv hazards that have bsen tj temporarily nsulaaed will, approved materrafsl are not considered exposed by itt this procedure. PPE described in this fable may be reduced accordingly.

GENERAL:Witonwlngiscloseprox,mdytoenecgxodorpotentallyenergized orcues dose neck tanyards anti oosrcet,y SHALL be secured on the inside of U)

U.

die cuter lar Qf clothing prelerredi or reversed on tine ned. In such a wanner tee tee prevent tntact with those circuits. te. tee in. &

teete as w c cs ComDonentiBoardf Bus ,

480v Shutdown Board 24 I 18 64 23 4 Any task that expostis 480v or works within 1 foot of 480v. x x x x x x ICornoartnienis with no fixoosed 480v (250 vdc onivi. I Avoid Contact x x x x x I Standard:

Determines needs natural fibers, leather shoes, hard hat, safety glasses, earplugs and gloves long gauntlet.

Determines for the person performing the racking needs Gloves Voltage Rated (Class 1) Note 4, and a 100 2 flash suit.

cal/cm SAT_ UNSAT_ N/A _COMMENTS:____________________________

7

JPM SRO/RO Ala Performance Step 5: Critical X Not Critical

2. Work on 480v and 4,160v equipment requires a PPE Boundary be erected to assure other personnel do NOT encroach on the calculated arc-flash. PPE Boundaries are barricaded. See Appendix A for PPE Boundary information.

1. Boundaries:

Establish a PPE Boundary accordingly. See Attachment 1 for the size of the boundary U,

Electrical PPE Matrix 0 q

No NOTE 1: Class (3 gloves are required whet, contact e,th fO-300v is requhed or 4, when acuOerrtat contact is likery. 4, NOTE 2: CLees g)oves wtd te3ther protectors are equrrec when n4irr ¶ foot 0 0 o exposed 490 teds.

z z NOTE 3: Class 1 gloxes with teether protectors. OR gloces rated for 50 celicret, 0 Q are reiy.ured after, wdhin 1 foot of 480V or 4 feet of exposed 4kv. 54 4, 4, NOTE 4: Class 1 gloves etth leather protectors. OR gloves rated for 75 cafIcm. 4, E 4, 0t Os U U .1!

are required when wdldn I foot of 48EV or 4 feet of exposed 4kv. 4, C., 0 C-,

NOTE 5: Class l gloves are used in 480v agspfoat.ons aher calcjlated Incident 0

Energy te.els are Chore 50 cDlionr antI Pie erre.grced core porerst is wrISts fooL a 4, 4,

NOTE 6: ffrd hat not required EieIrfcat PPE. Ref. WA Safety Manual. i022. (5 4, C m 4, 4, GENERAL: Exposed, enerpiced 480v and 4kv hazards that have been U U.

@1 C 4, 4? 4, terirporanly losuiated with approv5d materialIst are trot consrdered exposed oy -x at at at thIs procedure. PPE desoibed in this table may be reduced accordingly. 0 4,

4, GENERAL: When working itt close proximity to energized or poterrbalty energized l 4, 4, 0 circurds rouse neck lrryards and dosxneky Sl-tAU. be secured ott the rnside of Ill C13 U.

the cuter layer of clottrrng (preferred) or reversed on the reck in need a rnarnrer to 4, 0 (9 4, 4, Os prevent cattIest with those cfrcuits z 4, 4? 4, lx. p >

w 0 0 0 4, 15 ComponentiBoardiBus 11 0 0 0 480v Shutdown Board 2A AnV task that exposss 480v or works within 1 foot of 480v, I 18 64 23 x x x x x x 4 Icomoartmertts with no etrtosed 480v (250 vdc onlvt. I Avoid Contact x x x x x I Standard:

Determines that the PPE boundary must be 23 feet SAT UNSAT N/A COMMENTS:

8

JPM SRO/RO Ala Performance Step 6: Critical X Not Critical Verification Program NPG-SPP-lO.3 3.3.5 Circuit Breakers Circuit breaker verification shall include a local inspection of the breaker, control power switches or fuses, and other equipment as outlined below:

A. To verify a breaker is removed from service, the independent or concurrent verifier shall ensure control power is isolated (if required) by inspecting appropriate switches, fuses or fuse blocks, and ensure the breaker is racked out to the disconnected position, as applicable.

Appendix A (Page 1 of 2)

Systems and Components Requiring Independent or Concurrent Verification SYS BFN 31 Control Bay and Off-Gas Building HVAC (CREV)

Standard:

CV is required SAT_ UNSAT N/A COMMENTS:________

END OF TASK STOP TIME 9

AdminROAlb OPERATOR:____________________________

RO___ DATE:

JPM NUMBER: Admin RO Alb TASK NUMBER: U-000-SU-06 TASK TITLE: 2-SR-2 Drywell Floor and Equipment Drain Log Calculation K/ANUMBER: 2.1.7 K/A RATING: RO 4.4 SRO4.7 TASK STANDARD: Calculate the correct Drywell Floor and Equipment Sump leakage using 2-SR-2.

LOCATION OF PERFORMANCE: Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: 2-SR-2 VALDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMINER 1

INITIAL CONDITIONS:

Unit 2 is operating at 100% power after a Refuel Outage last month. The unit has been on line for 10 days. It is Saturday morning and the time is 0800.

IMTL4TJNG CUE:

The Unit Supervisor directs you as a Reactor Operator to pump the sumps and complete 2-SR-2 for the Drywell Floor and Equipment Drain Sumps and report results.

Admin RO Aib Unit 2 Simulator INITIAL CONDITIONS:

Unit 2 is operating at 100% power after a Refuel Outage last month. The unit has been on line for 10 days. It is Saturday morning and the time is 0800.

iNITIATING CUE:

The Unit Supervisor directs you as a Reactor Operator to pump the sumps and complete 2-SR-2 for the Drywell Floor and Equipment Drain Sumps and report results.

3

AdminROAlb START TIME____

Performance Step 1: Critical Not Critical X 6.4 Manually Pumping Down Drywell Floor Drain Sump NOTE This section is performed at Panel 2-9-4 in Unit 2 Control Room.

[1] REVIEW Precautions and Limitations. REFER TO Section 3.0.

Standard:

Reviews P&Ls Section 3.0 SAT_ UNSAT_ N/A COMMENTS:_______________________________

Performance Step 2: Critical Not Critical X

[2] VERIFY OPEN the following valves:

DW FLOOR DRAiN OUTBD 1SOL VALVE, 2-HS-77-2B

DW FLOOR DRAiN INBD ISOL VALVE, 2-HS-77-2A Standard:

Verifies OPEN 2-HS-77-2B and 2A SAT_ UNSAT N/A COMMENTS:____

4

AdminROAlb Performance Step 3: Critical X Not Critical

[3] PLACE in START RETURN TO AUTO one of the following pumps:

DW FLOOR DRAiN SUMP PUMP 2A, 2-HS-77-1A-A OR

DW FLOOR DRAiN SUMP PUMP 2B, 2-HS-77-1B-A Standard:

Starts Drywell Floor Drain Sump 2A or 2B SAT UNSAT_ N/A COMMENTS:________________________________

Performance Step 4: Critical Not Critical X

[4] VERIFY pump started in Step 6.4[3] auto stops on sump low level.

Standard:

Verifies pump in step 6.4[3] auto stops on sump low level.

SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 5: Critical X* Not Critical Completes 2-SR-2 for Drywell Unidentified Leakage for 0800 Saturday morning.

Standard:

Completes 0800 readings for Saturday.

Logs the integrator reading (should be 114627+/-5) in Column A.1 of Table 1.2 SAT_ UNSAT N/A _COMMENTS:________________________________

5

AdminROAlb Performance Step 6: Critical Not Critical Calculates a current unidentified leakrate of 0.30 gpm Standard:

Calculates a current unidentified leakrate of 0.30 +/- .01 gpm and logs the value into column G. 1 of Table 1.2 SAT UNSAT N/A COMMENTS:________________________________

Performance Step 7: Critical Not Critical Calculates a change in leakrate of 0.01 gpm Standard:

Calculates a change in leakrate of 0.01+/-.0l gpm and logs into column 1.1 of Table 1.2.

SAT_ UNSAT N/A COMMENTS:_______________________________

6

AdminROAlb Performance Step 8: Critical Not Critical 2-01-64 6.6 Manually Pumping Down Drywell Equipment Drain Sump NOTE This section is performed at Panel 2-9-4 in Unit 2 Control Room.

[1] REVIEW Precautions and Limitations. REFER TO Section 3.0.

Standard:

Reviews P&Ls Section 3.0 SAT_ UNSAT N/A Performance Step 9: Critical Not Critical X

[2] VERIFY equipment sump temperature less than high end of operating band on DRYWELL EQPT DRAIN SUMP TEMP, 2-TIS-77-14.

Standard:

Verifies equipment sump temperature less than high end of operating band on 2-TIS-77-14.

SAT_ UNSAT_ N/A COMMENTS:____________________________

7

Admin RO Aib Performance Step 10: Critical Not Critical X

[3] IF equipment drain sump temperature indicates high out of operating band, THEN VERIFY or PLACE equipment drain sump in recire. REFER TO Section 6.5, Placing Drywell Equipment Drain Sump in Recirc. (Otherwise N/A)

Standard:

Step is N/A.

SAT_ UNSAT_ N/A _COMMENTS:_______________________________

Performance Step 11: Critical Not Critical

[4] VERIFY OPEN both of the following valves:

DW EQPT DRAIN OUTBD ISOL VALVE, 2-HS-77-15B

DW EQPT DRAiN INBD ISOL VALVE, 2-HS-77-15A Standard:

Verifies OPEN 2-HS-77-15B and iSA SAT_ UNSAT N/A COMMENTS:___

8

AdminROAlb Performance Step 12: Critical Not Critical

[5) IF sump is in RECIRC THEN PLACE, DW EQPT DR SUMP DISCH/RECIRC SEL, 2-HS-77-14C in DISCH.

(Otherwise N/A)

Standard:

Sump is not in recirc, step is N/A.

SAT_ UNSAT N/A _COMMENTS:_____________________________

Performance Step 13: Critical Not Critical

[6] VERIFY DW EQPT DR SUMP DISCHJRECIRC SEL, 2-HS-77-14C RETURN TO AUTO.

Standard:

Verifies 2-HS-77-14C in AUTO SAT_ UNSAT N/A _COMMENTS:___

9

AdminROAlb Performance Step 14: Critical Not Critical

[7] PLACE in START RETURN TO AUTO ç of the following pumps:

DW EQPT DRAIN SUMP PUMP 2A, 2-HS-77-14A-A OR

DW EQPT DRAIN SUMP PUMP 2B, 2-HS-77-14B-A Standard:

Starts Drywell Equipment Drain Sump 2A or 2B SAT_ UNSAT N/A _COMMENTS:____________________________

Performance Step 15: Critical Not Critical

[8] VERIFY pump started in Step 6.6[7] stops on sump low level.

Standard:

Verifies pump started in Step 6.6[7j stops on sump low level.

SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 16: Critical Not Critical Completes 2-SR-2 for Drywell Identified Leakage and Total Leakage for 0800 Saturday morning Standard:

Completes 0800 readings for Saturday.

Logs the integrator reading (should be 27560+/-5) in column A.2 of Table 1.3 SAT UNSAT_ N/A COMMENTS:_______________________________

10

AdminROAlb Performance Step 17: Critical Not Critical Calculates a current identified leakrate of 0.46 gpm Standard:

Calculates a current identified leakrate of 0.46*.01 gpm and logs into column G.2 of Table 1.3.

SAT_ UNSAT N/A _COMMENTS:_______________________________

Performance Step 18: Critical Not Critical Calculates a total leakrate of 0.76 gpm Standard:

Calculates a total leak rate of 0.76+/-.02 gpm and logs into column 1.2 of Table 1.3.

SAT_ UNSAT_ N/A _COMMENTS:________________________________

END OF TASK STOP TIME 11

(

DAY SHIFT WEEK: to Table 1.2 DRYWELL UNIDENTIFIED LEAKAGE APPLICABILITY: Modes 1 2 & 3 Readings are required at all times.

Surveillance Requirements: 3.4.4.1 LOCATION: Panel 2-9-4, 2-FQ-77-6 Col. C.1 Col. D.1 Cot. E.1 Cot. F.1 Col. G.1 Col. H.1 Cot. 1.1 Review Init Col. A.1 Col. B.1 Current Change in

. Current Previous Days Gallons Elapsed Time Leakrate Leakrate Preferred reading Point 3 2-FQ-77-6 Pumped Previous Days Cot. Dl Cot. C.1 Previous Days Cot. G.1

- Cot. H.1 2-FQ-77-6 Reading from Cot. A.1 Time from Col. E.1 ÷ Col. F.1 Leakrate from 1600 - Col. B.1 Current Time Col. D.1 (mm) (gpm) Col. G.1 (gpm) (gpm) LIMITS Unit Supvr Reading (gals) Col. A.1 (gals)

(Note 2) (Note 2) (Note 2) (Note 2) (Note 2, 5) (Note 2) (Note 2, 3, 5) (AC) UO (Note 4)

(Notes 1 2) (Note 2) 417 0800 0800 1440 .29 .29 .00 MS 114202 113785 418 1200 1200 1440 .29 .29 .00 DZ Friday 114344 113926 114060 424 1600 1600 1440 .29 .29 .00 BC 114484 Cot. G.1 5.0 gpm and Saturday Cot. 1.1 s 2 gpm (Note 3)

Student Handout Student Handout Student Handout Sunday Student Handout Student Handout Student Handout Monday (1) Manually pump down sump per 2-01-64 prior to reading. To record gallons, disregard the decimal position on integrator. Record only five digits including right-hand dials hash marks as gallons of flow. Example: Record 0065432.1 as 54321.

in (2) May be N/Ad if Surveillance Requirement is being met with the performance of 2-SR-3.4.4. 1 or 2-SR-3.4.4. 1-a and a note stating such shall be made all other entries except for Col. A. I and D. 1 the remarks section of this SR. When initial integrator reading is taken and no previous reading exists, should be N/Ad.

(3) Acceptance Criteria for Col. 1.1 is only applicable when in Mode 1 for> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(4) Unit Supervisor shall Independently Verify Inleakage Calculations and verify Inleakage Acceptance Criteria.

Admin RO Aib (5) NOTIFY Chemistry to initiate 2-TI-275E when Drywell Unidentified leakage reaches the following trigger values: Drywell Unidentified leakage has reached 0.50 gpm OR Drywell Unidentified leakage has risen by 0.25 gpm in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

13

C)

DAY SHIFT WEEK: to*

Table 1.3 DRYWELL IDENTIFIED and TOTAL LEAKAGE APPLICABILITY: Modes 1, 2 & 3 Readings are required at all times.

Surveillance Requirements: 3.4.4.1 LOCATION: Panel 2-9-4, 2-FQ-77-16 Cal. 0.2 Col. E.2 Cal. F.2 Cal. G.2 Cal. H.2 Cal. 1.2 Review Init Col. A.2 Col. B.2 Col. C.2 Current Current Previous Days Gallons Elapsed Time Leakrate Current Total Leakrate Preferred reading 2-FQ-77-16 Pumped Previous Days Cal. D.2 Col. C.2 Unidentified Cal. G.2 Point 4 times are 0800, Reading from Cal. A.2 Time from - Cal. E.2 ÷ Cal. F.2 Leakrate from + Col. H.2 2-FQ-77-16 120 and 600 (mm) (gpm) Cal. G.1 (gpm) (gpm) LIMITS Unit Supvr Reading (gals) Cal. A.2 (gals) Cal. B.2 Current Time Col. 0.2 (Nate 2) (Nate 2) (Note 2) (Nate 2) (Notes 2 & 3) (Note 2) (AC) UO (Note 4)

(Notes 1, 2) (Nate 2) (Note 2) 0800 0800 1440 .40 .29 .69 MS 26890 26310 580 1200 1200 1440 .43 .29 .72 DZ Friday 27136 26518 618 632 1600 1600 1440 .44 .29 .73 BC 27342 26710 Cal. 1.2 Saturday 30.0 gpm Student Handout Student Handout Student Handout Sunday Student Handout Student Handout Student Handout Monday only five digits (1) Manually pump down sump per 2-01-64 prior to reading. To record gallons, disregard the decimal position on integrator. Record including right-hand dials hash marks as gallons of flow. Example: Record 0065432.1 as 54321.

stating such shall be made in (2) May be N/Ad if Surveillance Requirement is being met with the performance of 2-SR-3 .4.4.1 or 2-SR-3 .4.4.1-a and a note except for Col. A.2 and D.2 the remarks section of this SR. When initial integrator reading is taken and no previous reading exists, all other entries should be N/Ad.

(3) G. I reading is from Drywell Unidentified Leakage Col. G. I on previous page.

(4) Unit Supervisor shall independently Verify Inleakage Calculations and verify Inleakage Acceptance Criteria.

C)

DAY SHIFT WEEK: to Table 1.2 DRYWELL UNIDENTIFIED LEAKAGE APPLICABILITY: Modes 1 2 & 3 Readings are required at all times.

Surveillance Requirements: 3.4.4.1 LOCATION: Panel 2-9-4, 2-FQ-77-6 Cot. C.1 Cot. D.1 Cot. E.1 Cot. F.1 Col. G.1 Col. H.1 Col. 1.1 Review mit Col. A.1 Cot. B.1 Current Change in

. Current Previous Days Gallons Elapsed Time Leakrate Leakrate Preferred reading Point 3 2-FQ-77-6 Pumped Previous Days Cot. D.1 Cot. C.1 Previous Days Col. G.1

- Cot. H.1 Time from - Cot. E.1 ÷ Col. F.1 Leakrate from 2-FQ-77-6 Reading from Cot. A.1 n - Col. B.1 Current Time Cot. D.1 (mm) (gpm) Col. G.1 (gpm) (gpm) LIMITS Unit Supvr Reading (gals) Col. A.1 (gals)

(Note 2) (Note 2) (Note 2) (Note 2) (Note 2) (Note 2, 3) (AC) UO (Note 4)

(Notes 1, 2) (Note 2) (Note 2) 417 0800 0800 1440 .29 .29 .00 MS 114202 113785 418 1200 1200 1440 .29 .29 .00 DZ Friday 114344 113926 424 1600 1600 1440 .29 .29 .00 Cot. G.1 BC 114484 114060 5.0 gpm 114627+/-5 114202 425+/-5 0800 0800 1440 .30+/-01 .29 +01+/-01 and ANSWER KEY ANSWER KEY ANSWER KEY Saturday Cot. 1.1

< 2 gpm (Note 3)

ANSWER KEY ANSWER KEY ANSWER KEY Sunday (1) Manually pump down sump per 2-01-64 prior to reading. To record gallons, disregard the decimal position on integrator. Record only five digits including right-hand dials hash marks as gallons of flow. Example: Record 0065432.1 as 54321.

be made in (2) May be N!Ad if Surveillance Requirement is being met with the performance of 2-SR-3 .4.4.1 or 2-SR-3 .4.4.1-a and a note stating such shall all other entries except for Col. A. 1 and D. I the remarks section of this SR. When initial integrator reading is taken and no previous reading exists, should be N/Ad.

(3) Acceptance Criteria for Col. LI is only applicable when in Mode I for> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(4) Unit Supervisor shall Independently Verify Inleakage Calculations and verify Inleakage Acceptance Criteria.

leakage has (5) NOTIFY Chemistry to initiate 2-TI-275E when Drywell Unidentified leakage reaches the following trigger values: Drywell Unidentified reached 0.50 gpm OR Drywell Unidentified leakage has risen by 0.25 gpm in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

n DAY SHIFT WEEK: to Table 1.3 DRYWELL IDENTIFIED and TOTAL LEAKAGE APPLICABILITY: Modes 1, 2 & 3 Readings are required at all times.

Surveillance Requirements: 3.4.4.1 LOCATION: Panel 2-9-4, 2-FQ-77-16 Col. C.2 Col. D.2 Col. E.2 Col. F.2 Cal. G.2 Col. H.2 CoP. 1.2 Review mit CoP. A.2 COP. B.2 Current

Current Previous Days Gallons Elapsed Time Leakrate Current Total Leakrate Preferred reading 2-FQ-77-16 Pumped Previous Days Cal. 0.2 Cal. C.2 Unidentified Col. G.2 Point 4 times are 0800, Reading from Col. A.2 Time from - Ccl. E.2 ÷ Col. F.2 Leakrate from + Ccl. H.2 2-FQ-77-16 1200 and 1600 Ccl. A.2 (gals) - Col. 8.2 Current Time Ccl. D.2 (mm) (gpm) Ccl. G.1 (gpm) (gpm) LIMITS Unit Supvr Reading (gals)

(Note 2) (Note 2) (Nate 2) (Nate 2) (Nate 2) (Notes 2 & 3) (Note 2) (AC) UO (Note 4)

(Notes 1, 2) (Note 2) 580 0800 0800 1440 .40 .29 .69 MS 26890 26310 618 1200 1200 1440 .43 .29 .72 DZ Friday 27136 26518 632 1600 1600 1440 .44 .29 .73 BC 27342 26710 26890 660+/-5 0800 0800 1440 .46+/-01 .30+/-01 .76+/-.02 27560+/-5 Col. 1.2 KEY ç30.0 gpm ANSWER KEY ANSWER KEY ANSWER Saturday ANSWER KEY ANSWER KEY ANSWER KEY Sunday (1) Manually pwnp down sump per 2-01-64 prior to reading. To record gallons, disregard the decimal position on integrator. Record only five digits including right-hand dials hash marks as gallons of flow. Example: Record 0065432.1 as 54321.

made in (2) May be N/Ad if Surveillance Requirement is being met with the performance of 2-SR-3 .4.4.1 or 2-SR-3 .4.4.1-a and a note stating such shall be for Col. A.2 and D.2 the remarks section of this SR. When initial integrator reading is taken and no previous reading exists, all other entries except should be N/Ad.

(3) G. I reading is from Drywell Unidentified Leakage Col. G. I on previous page.

(4) Unit Supervisor shall independently Verify Inleakage Calculations and verify Inleakage Acceptance Criteria

Admin RO A2 OPERATOR:

RO___ DATE:________

JPM NUMBER: Admin RO A2 TASK NUMBER: U-066-NO-02 TITLE: Evaluate Recombiner Performance K/A NUMBER: 2.2.44 K/A RATING: RO 4.2 TASK STANDARD: Evaluate Off-Gas Recombiner Performance. Determine that it does not meet Acceptance Criteria.

LOCATION OF PERFORMANCE: Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: 2-01-66 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED:

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMiNER 1

IMTL4L CONDITIONS:

You are a Unit Operator.

INITIATING CUE:

The Unit Supervisor has directed you to perfonn 2-01-66, Section 6.1, Recombiner Performance Evaluation and report results to the SRO.

2

Adrnin RO A2 IN-SIMULATOR: 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. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit Operator.

INITIATING CUE:

The Unit Supervisor has directed you to perform 2-01-66, Section 6.1, Recombiner Performance Evaluation and report results to the SRO.

3

Admin RO A2 START TIME Performance Step 1: Critical X Not Critical 6.1 Recombiner Performance Evaluation NOTES

1) The production of hydrogen and oxygen in the reactor is dependent upon reactor power level and upon the amount of hydrogen injected by the Hydrogen Water Chemistry System if in service. Since the recombination of hydrogen and oxygen is exothermic, the operating temperature of the recombiner is also dependent upon power level and the status of the HWC System.

2) Following startup, while still at low power, recombiner performance and hydrogen concentration should be closely monitored.

[1] Perform a Recombiner Performance Evaluation as follows:

[1.1] DETERMINE in-service recombiner inlet temperature, as indicated on applicable temperature indicator, Panel 2-9-53.

RECOMBINER 2A, iNLET TEMP 2-TI-66-75A

RECOMBINER 2B, iNLET TEMP 2-TI-66-75B Standard:

Determines Recombiner 2A is in service and records an inlet temperature from 2-TI-66-75A, Panel 2-9-53 of 410 °F to 420 °F SAT_ UNSAT N/A COMMENTS:_______________________________

4

Admin RO A2 Performance Step 2: Critical Not Critical

[1.2] DETERMINE in-service recombiner operating (center) temperature as indicated on RECOMB1NER 2A/2B TEMPERATURE recorder, 2-TRS-66-77, Panel 2-9-53.

Standard:

Determines the in-service recombiner operating (center) temperature as indicated on Recombiner 2A temperature recorder, 3-TRS-66-77, Panel 2-9-53, channel 6 point 2-TE-66-77AB is from 631 °F to 632 °F SAT_ UNSAT_ N/A COMMENTS:_____________________________

Performance Step 3: Critical Not Critical

[1.3] CALCULATE the temperature difference (AT) between the values obtained in Steps 6.1 [1] and 6.1 [2].

Standard:

Calculates Recombiner 2A inlet/center At and determines At is from 211 °F to 222 °F SAT_ UNSAT_ N/A COMMENTS:__________________________

Performance Step 4: Critical X Not Critical

[1.4] DETERMINE the reactor thermal power (MWt) from process computer.

Standard:

Determines reactor thermal power is 3252 MWt SAT_ UNSAT_ N/A COMMENTS:_______

5

Admin RO A2 Performance Step 5: Critical X Not Critical

[1.5] USING Illustration 1, PLOT the corresponding point of reactor power in MWt and Standard:

Using illustration 1, Plots corresponding point of reactor power (3252 MWth) and AT (211 °F to 222 °F), also may determines At corresponding to 3252 MWT is 227 °F to 228 °F. Calculation: AT 0.070 °F per MWth 0.070 X 3252 = 227.64 °F SAT_ UNSAT_ N/A COMMENTS:_______________________________

Performance Step 6: Critical Not Critical

[1.6] VERIFY point on illustration I is above or equal to the appropriate line (HWC in service or HWC out of service)

Standard:

Determines from Illustration I that calculated At vs MWt plots BELOW the HWC out of Service line. Candidate may also use calculated AT from curve factor to determine that actual AT (211 °F to 222 °F) is BELOW the HWC out of service temperature for 3252 MWt of 227 °F to 228 °F.

SAT UNSAT N/A COMMENTS:_____________________________

6

Admin RO A2 Performance Step 7: Critical Not Critical

[2] [F the in-service recombiner performance is below the minimum allowable, THEN:

[2.11 CHECK Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with Section 5.0.

Standard:

Reports to Unit Supervisor that in service recombiner performance is below the minimum allowable.

SAT UNSAT N/A _COMMENTS:______________________________

END OF TASK STOP TIME 7

Admin RO A2 Illustration 1 (Page 1 of 1)

Recombine Performance Evaluation AT to Reactor Power 0 500 1000 1500 2000 2500 3000 3500 MWt HWC Out of Servic& - - HWC In Servicej Evaluation is satisfactory when intersection point of AT to Reactor Power is above the appropriate line.

For 3458mwt HWC in service AT 190°F HWC out of service AT 242°F CURVE FACTORS Normal Water Chemistry (NWC) AT = 0.070°F per MWt Hydrogen Water Chemistry (HWC) AT = 0.055°F per MWt 8

Admin RO A2 OPERATOR:

RO___ DATE:________

JPM NUMBER: Admin RO A2 TASK NUMBER: U-066-NO-02 TITLE: Evaluate Recombiner Performance KJA NUMBER: 2.2.44 KJA RATING: RO 4.2 Determine that it does not TASK STANDARD: Evaluate Off-Gas Recombiner Performance.

meet Acceptance Criteria.

LOCATION OF PERFORMANCE: Unit 3 Simulator REFERENCES/PROCEDURES NEEDED: 3-01-66 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED:

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:

EXAMINER 1

iNITIAL CONDITIONS:

You are a Unit Operator.

INITIATING CUE:

n 6.1, Recombiner Performance The Unit Supervisor has directed you to perform 3-01-66, Sectio Evaluation and report results to the SRO.

2

Admin RO A2 ed. I will IN-SIMULATOR: I will explain the initial conditions and state the task to be perform When you compl ete provide initiating cues and reports on other actions when directed by you.

d. When the task successfully, the objective for this job performance measure will be satisfie s Correc t. (OR Thats your task is given, you will repeat the task and I will acknowledge That my task Incorrect, if applicable). When you have completed your assigned task, you will say, is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are a Unit Operator.

INITIATING CUE:

ance The Unit Supervisor has directed you to perform 3-01-66, Section 6.1, Recombiner Perform Evaluation and report results to the SRO.

3

Admin RO A2 START TIME____

Performance Step 1: Critical Not Critical 6.1 Recombiner Performance Evaluation NOTES

1) The production of hydrogen and oxygen in the reactor is dependent upon reactor power level and upon the amount of hydrogen injected by the Hydrogen Water is Chemistry System if in service. Since the recombination of hydrogen and oxygen exothermic, the operating temperature of the recombiner is also dependent upon power level and the status of the HWC System.

en

2) Following startup, while still at low power, recombiner performance and hydrog concentration should be closely monito red.

[1] Perform a Recombiner Performance Evaluation as follows:

[1.1) DETERMINE in-service recombiner inlet temperature as indicated on applicable temperature indicator, Panel 3-9-53.

RECOMBINER 3A, iNLET TEMP 3-TI-66-75A

RECOMBINER 3B, iNLET TEMP 3-TI-66-75B Standard:

Determines Recombiner 3A is in service and records an inlet temperature from 3-TI-66-75A, Panel 3-9-53 of 390 °F to 400 °F SAT UNSAT N/A COMMENTS:_______________________________

4

Admin RO A2 Critical Not Critical Performance Step 2:

as

[1.2] DETERMINE in-service recombiner operating (center) temperature er, indicated on GLY/RECMB/OG MOIST SEP TEMPERATURE record 3-TRS-66-106, Panel 3-9-53.

Standard:

as indicated on Determines the in-service recombiner operating (center) temperature

, channel 6 point Recombiner 3A temperature recorder, 3-TRS-66-106, Panel 3-9-53 3-TE-66-77AB is from 613 °F to 614 °F SAT UNSAT_ N/A COMMENTS:_____________________________

Critical X Not Critical Performance Step 3:

ed in

[1.3] CALCULATE the temperature difference (AT) between the values obtain Steps 6.1[1] and 6.1[2].

Standard:

211 °F to 223 °F Calculates Recombiner 3A inlet/center At and determines At is from SAT_ UNSAT_ N/A COMMENTS:_____________________________

Critical X Not Critical Performance Step 4:

[1.4] DETERMINE the reactor thermal power (MWt) from process computer.

Standard:

Determines reactor thermal power is 3258 MWt SAT UNSAT_ N/A COMMENTS:_______

5

Admin RO A2 Performance Step 5: Critical Not Critical

[1.5] USiNG Illustration 1, PLOT the corresponding point of reactor power in MWt and AT.

Standard:

Using illustration 1, Plots corresponding point of reactor power (3258 MWth) and AT (211 °F to 223 °F), also may determines At corresponding to 3258 MWT is 228 °F.

Calculation: AT = 0.070 °F per MWth 0.070 X 3258 = 228 °F SAT_ UNSAT_ N/A _COMMENTS:_____________________________

Performance Step 6: Critical Not Critical

[1.6] VERIFY point on illustration 1 is above or equal to the appropriate line (HWC in service or HWC out of service)

Standard:

Determines from Illustration 1 that calculated At vs MWt plots BELOW the HWC out of Service line. Candidate may also use calculated AT from curve factor to determine that actual AT (211 °F to 223 °F) is BELOW the HWC out of service temperature for 3258 MWt of 228 °F.

SAT_ UNSAT N/A _COMMENTS:_______________________________

6

Admin RO A2 Critical Not Critical X Performance Step 7:

um allowable, THEN:

[2] IF the in-service recombiner performance is below the minim on in

[2.1] CHECK Off-Gas Preheater, Recombiner and SJAEs are in operati accordance with Section 5.0.

Standard:

is below the minimum Reports to Unit Supervisor that in service recombiner performance allowable.

SAT_ UNSAT N/A COMMENTS:_____________________________

END OF TASK STOP TIME 7

Admin RO A2 illustration I (Page 1 ofl)

Power Recombine Performance Evaluation AT to Reactor 1000 1500 2000 2500 3000 3500 0 500 MWt HWC Out of Servics - - HWC n Service of \T to Reactor Power is above the Evaluation is satisfactory when intersection point appropriate line.

For 3458mwt HWC in service T 190°F HWC out of service T 242F CURVE FACTORS Normal Water Chemistry (NWC) = 0.070°F per MWt Hydrogen Water Chemistry (HWC) L\T = 0.055°F per MWt 8

JPM RO A4 OPERATOR:

RO___ SRO___ DATE:________

JPM NUMBER: A4 TASK NUMBER: U-000-EM-87 TASK TITLE: EPIP-5 Appendix B and C Notifications K/A NUMBER: 2.4.43 K/A RATING: RO 3.2 SRO 3.8 TASK STANDARD: Completion of ERO Activation and State Notification in accordance with Appendix B and Appendix C of EPIP-5.

LOCATION OF PERFORMANCE: Unit 2 Simulator REFERENCES/PROCEDURES NEEDED: EPIP 5 VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: 15 minutes for State Notifications and County Notifications PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:_______

EXAMINER 1

INITIAL CONDITIONS:

You are an Operator.

Shift Manager has declared a General Emergency due to a Security Event that is ongoing.

Browns Ferry is currently operating in O-AOI-100-8, Security Event Response.

INITIATING CUES:

The SHIFT MANAGER/SED directs you to:

1. Complete Appendix C (State of Alabama Notification) utilizing a completed Appendix A (General Emergency Initial Notification Form).

2. Implement EPIP-5, Appendix B, Activation of the Emergency Response Organization (ERO) utilizing DRILL STAGING AREA notification.

3. Appendix A provided NOTE: When attempting to contact anyone by phone dial 30504 and inform the person who answers who you are calling.

TIME Critical

JPM RO A4 Simulator INITIAL CONDITIONS:

You are an Operator.

Shift Manager has declared a General Emergency due to a Security Event that is ongoing.

Browns Ferry is currently operating in O-AOI-l00-8, Security Event Response.

INITIATING CUES:

The SHIFT MANAGER/SED directs you to:

4. Complete Appendix C (State of Alabama Notification) utilizing a completed Appendix A (General Emergency Initial Notification Form).

5. Implement EPIP-5, Appendix B, Activation of the Emergency Response Organization (ERO) utilizing DRILL STAGING AREA notification.

6. Appendix A provided NOTE: When attempting to contact anyone by phone dial 30504 and inform the person who answers who you are calling.

TIME Critical NOTE: Appendix C starts at JPM Step 1 Appendix B starts at JPM Step 5 Appendix I starts at JPM step 9 3

JPMROA4 START TIME____

I CUE: Have operator DIAL 30504 Performance Step 1: Critical Not Critical APPENDIX C Page 1 of 1 State of Alabama Notification 1.0 State Notification NOTE Notification of the Risk Counties / State of Alabama is required to be completed within 15 minutes from the time of emergency declaration.

[1] REPORT the information recorded on completed Appendix A to the BFN Risk Counties A. Limestone County 9-1-256-232-2631 Person Contacted (after hours) 9-1-256-232-0111 B. Morgan County 9-1-256-351-4620 Person Contacted (after hours) 9-1-256-353-2515 Option 0 C. Lawrence County 9-1-256-974-764 1 Person Contacted (after hours) 9-1-256-974-7911 D. Lauderdale County 9-1-256-760-6363 Person Contacted (after hours) 9-1-256-760-9117 Standard:

Operator notifies each of the above counties within 15 minutes SAT IJNSAT N/A COMMENTS:______

STOP TIME____

I CUE: Repeat Back information provided in the report I 4

JPM RO A4 START TIME____

Performance Step 2: Critical Not Critical APPENDIX C

[2] REPORT the information recorded on completed Appendix A to the State of Alabama A. FAX a copy of completed Appendix A to the State of Alabama at 9-1-205-280-2495.

B. REPORT to the State of Alabama the information on Appendix A utilizing:

24 Hours Primary: 9-1-205-280-23 10 Backup: 9-1-800-843-0699 Backup: 9-1-334-324-0076 Name of Person Notified (Name)

Date and Time of Notification (Date) (Time)

Standard:

Operator notifies the State within 15 minutes and Faxes a copy of Appendix A to the State.

SAT UNSAT N/A COMMENTS:____________________________

STOP TIME____

CUE: Repeat Back information provided in the report. When Appendix A is placed in FAX, inform Operator FAX is complete 5

JPM RO A4 Performance Step 3: Critical Not Critical X APPENDIX C

[3] REQUEST that the State representatives repeat back the information you have provided from Appendix A.

Standard:

Operator requests repeat back from state representatives SAT UNSAT N/A COMMENTS:__________________________

Performance Step 4: Critical Not Critical X APPENDIX C

[4] Return the completed Appendix C and Appendix A to the SED.

Standard:

Operator returns completed Appendix C and Appendix A to the SED SAT UNSAT N/A COMMENTS:

6

JPM RO A4 Performance Step 5: Critical X Not Critical APPENDIX B Page 1 of3 Activation of the Emergency Response Organization (ERO) 1.0 Activation of the Emergency Response Organization CAUTION Ongoing or anticipated security events may present a danger to site personnel. Do not conduct the notification of site personnel PA message during an ongoing or anticipated security event. All pertinent site personnel PA messages will be conducted per 0-AOl- 100-8 Security Event Response for security events.

[1] CONDUCT a Plant PA announcement similar to the following:

(Dial 687 to obtain the Plant PA)

Standard:

Operator does NOT read General Emergency message or make a Plant PA announcement.

SAT UNSAT N/A COMMENTS:______________________

CUE: If Operator request 0-AOI-l0O-8 or informs you that PA messages will be conducted JAW O-AOI-100-8, INFORM Operator another individual is conducting the required PA announcements.

7

JPM RO A4 Performance Step 6: Critical X Not Critical APPENDIX B

[2] TVA Enterprise Emergency Notification System (TEENS) DIRECT the ODS at 5-751-1700 or 5-751-2495 to ACTIVATE TEENS utilizing the notification as instructed by the SED C EMERGENCY C EMERGENCY STAGiNG AREA (If events are on-going or anticipated that may present a danger to normal emergency center staffing such as security related issues.)

CDRILL C DRILL STAGING AREA (If events are on-going or anticipated that may present a danger to normal emergency center staffing such as security related issues AND a drill is in progress).

Standard:

Operator checks DRILL STAGING AREA box as directed by the Shift Manager in the CUE. Operator attempts to contact the ODS.

SAT UNSAT N/A COMMENTS:_

8

JPM RO A4 Performance Step 7: Critical Not Critical APPENDIX B

[3] IF unable to establish contact with the ODS THEN continue to perform Step 1.0 [2] for 5 minutes Standard:

Operator proceeds to step 4 SAT UNSAT N/A COMMENTS:

[ CUE: 5 minutes has elapsed Performance Step 8: Critical Not Critical APPENDIX B

[4] IF unable to establish contact with the ODS after 5 minutes THEN IMPLEMENT Appendix I, Activation of the Emergency Paging System concurrently with this Appendix beginning at Step 2.0.

Standard:

Operator implements Appendix I SAT UNSAT N/A COMMENTS:

NOTE: This is the start of Appendix I. The rest of Appendix B follows Appendix I at JPM step 15.

9

JPM RO A4 Performance Step 9: Critical X Not Critical AppdndLx I NOTE

The Emergency Paging System (EPS) consists of a dedicated touch screen CRT. Activation of any screen feature requires the user place their fingertip within the boundary of the select button and leave it there for at least 1 second.

The CRT Screen will normally display a large rectangle that indicates that the paging system is available but currently inactive.

If the EPS fails to operate, contact the SMISED immediately. Request that the ODS be contacted to initiate the notification system (TEENS is preferred EPS is Alternate) from their location.

1.0 Activate the Emergency Paging System (EPS)

[1] PRESS the EPS CRT screen once to activate the paging options Standard:

Operator activates the Emergency Paging System using the touch screen.

SAT UNSAT N/A COMMENTS:

10

JPMROA4 Performance Step 10: Critical X Not Critical Appendix I

[2] PRESS the appropriate option as instructed by the SED

DRILL

EMERGENCY

STAGiNG AREA Standard:

Operator presses STAGiNG AREA as directed by the Shift Manager in the cue.

SAT UNSAT N/A COMMENTS:

Performance Step 11: Critical X Not Critical Appendix I

[3] PRESS the START button to initiate the option OR PRESS the ABORT button to deny the option request Standard:

Operator Presses the START button.

SAT UNSAT N/A COMMENTS:

11

JPMROA4 Performance Step 12: Critical Not Critical X Appendix I

[4] IF the EPS fails to operate locally THEN CONTACT the ODS at 5-751-1700 or 5-75 1-2495 AND DIRECT the ODS to activate the notification system (TEENS is preferred:

EPS is alternate) for BFN.

Standard:

NA SAT UNSAT N/A COMMENTS:___________________________

Performance Step 13: Critical Not Critical Appendix I

[5] IF the EPS FAILS to operate either locally or by the ODS, exit this step and re-enter this Appendix at Step 2.0 Otherwise continue in this procedure.

Standard:

NA SAT UNSAT N/A COMMENTS:

12

JPM RO A4 Performance Step 14: Critical Not Critical Appendix I

[6] MONITOR the Paging System Terminal Display NOTE Monitor ERO positions through OSC Document Control. Positions below OSC Document Control are courtesy pages and are not subject to call-out requirements.

1.6.1 IF A NO response is observed, OR The position being paged has not responded promptly or within approximately 20 minutes, THEN UTILIZE the Weekly Duty List and attempt to contact the position representative with available information. (No Fitness for Duty question is required.)

Standard:

Operator determines that all personnel have responded to the TEENS System SAT UNSAT N/A COMMENTS:

CUE: Provide EPS Printout showing TWENTY Minutes has elapsed and all personnel have responded as required.

13

JPM RO A4 Performance Step 15: Critical Not Critical Appendix B 2.0 Dose Assessment Evaluation

[1] CONTACT the Site Emergency Director and determined if a Dose Assessment Evaluation is warranted.

[2] IF emergency circumstances warrant dose assessment, CONTACT Radiation Protection at 7865 and REQUEST the implementation of EPIP-13 for dose assessment.

Otherwise continue in this Appendix Standard:

Operator continues SAT UNSAT N/A COMMENTS:

CUE: When SED contacted inform Operator that a Dose Assessment is NOT warranted 14

JPM RO A4 Performance Step 16: Critical Not Critical Appendix B 3.0 Notify On Shift Unit Supervisors of the emergency.

Standard:

Operator calls Unit 1 and 3 and notifies the Unit Supervisor of Emergency SAT UNSAT N/A COMMENTS:

CUE: Acknowledge Notification Performance Step 17: Critical Not Critical Appendix B 4.0 Conduct Notification of Site Personnel

[1] OBTAIN a copy of EPIP-5, Appendix A used for the State Notification and available affected Unit Control Room logs

[2] FAX copies to the TSC at 3742

[3] FAX copies to the CECC at 5-751-1682 Standard:

Operator Faxes copies of Appendix A to TSC and CECC SAT UNSAT N/A COMMENTS:_______________________

CUE: When Appendix A is placed in FAX, inform Operator FAX is complete 15

JPMROA4 Performance Step 18: Critical X Not Critical Appendix B

[4] IF The emergency has been declared based upon a security related event THEN A. DELAY making notification steps 4.0 [5] through 4.0 [8].

B. NOTIFY the Shift Manager of the delay C. Periodically MONITOR the event until such time that the Shift Manager determines the present danger has subsided OR The Shift Manager suspends notification steps 4.0 [5] through 4.0 [8].

Otherwise continue in this procedure Standard:

Operator does NOT perform steps 5, 6, 7 and 8 and notifies Shift Manager of Delay SAT UNSAT N/A COMMENTS:

CUE Acknowledge Notification CUE This Completes the JPM END OF TASK STOP TIME 16

JPMSROA1b OPERATOR:

SRO DATE:________

JPM NUMBER: SRO Alb TASK NUMBER: Conduct of Operations TASK TITLE: NFR ESOMs Shift Staffing K/A NUMBER: 2.1.5 K/A RATING: SRO 3.9 TASK STANDARD: Enter data for operators into the Nuclear Fatigue Rule data base. When the data base is opened determines Work Hour limitations were exceeded for one operator and determine actions required due to violations of fatigue rule NPG-SPP 3.21. For the other two operators enters data and determines one operator will not violate the NFR and the other operator can NOT work the additional hours or he will violate NFR.

LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: NPG-SPP 3.21, Technical Specifications VALDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE:_________________ DATh:

EXAMINER 1

c

\%

JPM SRO Aib INITIAL CONDITIONS:

th*

29 You are a Senior Reactor Operator and it is 1100 on Tuesday April Operator #2 and #4 are needed to work a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months dayshift on Saturday, May 3.

INITIATING CUES:

Enter these work hours into the Nuclear Fatigue Rule Database.

r, Evaluate ALL operators status to identify any violation or potential violation to the exam procto including the required actions, if any.

2

JPMSROA1b Class Room INITIAL CONDITIONS:

th 29 You are a Senior Reactor Operator and it is 1100 on Tuesday April Operator #2 and #4 are needed to work a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months dayshift on Saturday, May 3.

INITIATING CUES:

Enter these work hours into the Nuclear Fatigue Rule Database.

Evaluate ALL operators status to identify any violation or potential violation to the exam proctor, including the required actions, if any.

EXAMINER NOTE Passwords for each applicant are needed to conduct this 3PM 3

JPM SRO Aib START TIME____

Performance Step 1: Critical Not Critical Logs into the NFR Data Base Standard:

Logs into the NFR Data Base SAT UNSAT_ N/A COMMENTS:_______________________________

CUE: After the applicant successfully locates the NFR Data Base, provide them with a password and ask them to select BFN TEST in the database.

Performance Step 2: Critical X Not Critical When logged in determines that Operator 3 is in violation of NFR.

Standard:

Determines Operator 3 is NOT in compliance with Fatigue Rule.

SAT_ UNSAT_ N/A COMMENTS:_______________________________

CUE: When applicant determines that operator 3 is NOT in compliance with a work hour guideline have applicant identify what guidelines they have violated.

4

JPM SRO Aib Performance Step 3: Critical X Not Critical Applicant goes to violation page and will describe the violation of Operator 3 Standard:

The cause of the violation for Operator 3 is greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period.

SAT_ UNSAT_ N/A _COMMENTS:_________________________

CUE: When applicant determines that Operator 3 is not in compliance with the fatigue rule that is currently working a shift, have the applicant determine the required actions to take and how long to restore shift manning to minimum and how long they have to restore.

5

JPMSROA1b Performance Step 4: Critical X Not Critical 3.1.2 Individual

9. Notifring the appropriate Department Nuclear Fatigue Rule (NFR) Administrator, appropriate Department Head, and Site NFR Subject Matter Expert in the event that a violation has occurred or appears to have occurred.

Standard:

Identifies that Operations Department Nuclear Fatigue Rule (NFR) Administrator, Operations Manager and Site NFR Subject Matter Expert must be notified.

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 5: Critical Not Critical 3.2.3 Work Hour Scheduling [R.3]

F. Deviations from 10 CFR 26 overtime limits may occur as the result of administrative errors or unforeseen circumstances. A problem evaluation report (PER) shall be generated, in accordance with NPG-SPP-03 .1, Corrective Action Program for each individual when this occurs.

Standard:

Identifies that a problem evaluation report is required.

SAT_ UNSAT_ N/A COMMENTS:____________________________

6

JPM SRO Aib Perfomiance Step 6: Critical X Not Critical 5.2.2 Unit Staff The unit staff organization shall include the following:

b. Shift crew composition may be less than the minimum requirement of 10 CFR 2

50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.f for a period of time not to exceed memb ers hours in order to accommodate unexpected absence of on-duty shift crew provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

Standard:

n.

Identifies that Operator 3 must be replaced and the SRO has 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to fill the positio SAT UNSAT N/A COMMENTS:______________________________

f CUE: Have Applicant enter the given work hours for operators 2 and 4 into NFR I

Performance Step 7: Critical Not Critical Enters the given work hours into the NFR data base and refreshes the data base Standard:

Enters a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months dayshift for Saturday May 3 for Unit Operator 2 and 4.

SAT_ UNSAT N/A _COMMENTS:____________________

7

JPM SRO Aib Performance Step 8: Critical X Not Critical 3

r d Once refreshed determines that operator 2 can NOT work on Saturday May and that operator Td 3

4 can work on Saturday May Standard:

Determines that operator 2 will violate NFR if they work on Saturday May 3 and that operator 4 will be in compliance with NFR for the additional Saturday dayshifi. Operators 2 violation is that he must average 2.5 days off within a 7 day period SAT_ UNSAT_ N/A COMMENTS:____________________________

CUE: Have applicant describe the violation the violation for operator 2 EXA111NER NOTE All changes that the applicant made must be deleted before the 3PM is administered to the next applicant.

END OF TASK STOP TIME 8

JPMSROA3 OPERATOR:

SRO DATE:

JPM NUMBER: Admin SRO A3 TASK NUMBER: Radiation Control TASK TITLE: Determine Stay Time under Emergency Conditions and authorize KJA NUMBER: 2.3.4 K/A RATING: SRO 3.7 TASK STANDARD: Determine stay time for an AUO to perform an emergency evolution due to radiation levels and authorize.

LOCATION OF PERFORMANCE: Class Room REFERENCES/PROCEDURES NEEDED: EPIP 15 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE: DATE:

EXAMINER 1

INITIAL CONDITIONS:

Unit 2 is in a General Emergency and YOU are currently the Site Emergency Director.

An emergency exposure in excess of 10 CFR 20.120 1 limits is required to prevent equipment damage.

Mike Smith (EEN XXX5X9XXX) has volunteered to replace blown fuses to prevent the equipment damage.

Radiation Protection Supervision states that the dose rate at the fuse cabinet is 15 REM/hr and travel path dose rates are 10 REM/hr to and from the cabinet. It is estimated that it will take 12 minutes of total travel time to and from the cabinet.

Mike Smith has received 500 mrem TEDE, year to date, and he has been briefed of the radiological hazards associated with this evolution.

INITIATING CUE:

As the Site Emergency Director YOU, are directed to:

I) determine the maximum allowed emergency dose that SHOULD be authorized for Mike Smith to perform this mission,

2) determine how long Mike Smith can stay at the fuse cabinet to replace the fuses without exceeding the authorized Emergency Dose, and

3) complete the paperwork required to authorize the emergency exposure.

JPM SRO A3 Class Room INITIAL CONDITIONS:

Unit 2 is in a General Emergency and YOU are currently the Site Emergency Director.

An emergency exposure in excess of 10 CFR 20.120 1 limits is required to prevent equipment damage.

Mike Smith (EIN XXX5X9XXX) has volunteered to replace blown fuses to prevent the equipment damage.

Radiation Protection Supervision states that the dose rate at the fuse cabinet is 15 REM/hr and travel path dose rates are 10 REM/hr to and from the cabinet. It is estimated that it will take 12 minutes of total travel time to and from the cabinet.

Mike Smith has received 500 mrem TEDE, year to date, and he has been briefed of the radiological hazards associated with this evolution.

INITIATING CUE:

As the Site Emergency Director YOU, are directed to:

I) determine the maximum allowed emergency dose that SHOULD be authorized for Mike Smith to perform this mission,

2) determine how long Mike Smith can stay at the fuse cabinet to replace the fuses without exceeding the authorized Emergency Dose, and

3) complete the paperwork required to authorize the emergency exposure.

3

JPMSROA3 START TIME Performance Step 1: Critical X Not Critical Determine the maximum allowable radiation dose to protect valuable property Standard:

Determines that the maximum allowable dose limit for protecting valuable property is 10 REM SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical X Not Critical Determine the maximum allowed radiation dose that the AUO may receive, based on previous exposure Standard:

Determines that the AUO receive no more than 9.5 REM, based on previous exposure of 500 mrem TEDE, year to date, to protect valuable property SAT IINSAT N/A COMMENTS:

NRC Information: Reference is EPIP 15 SectIon 3.4 Dose Limits for Workers During Emergencies 3.4.1 Doses to all workers during emergencies should, to the extent practicable be limited to 10 CFR 20.1201 limits. There are, however, some emergency situations for which higher emergency exposures may be justified. Whenever these situations are justified and ALARA considerations have been evaluated the following limits can be administered.

3.4.2 Radiation Protection (RP) considers the to-date annual accrued dose to individuals when establishing the maximum dose limits for workers during emergencies, The to-date annual accrued dose would be subtracted f the applicable engicy dose limit to determine the authorized allowable dose for e emergency.

4

JPMSROA3 Performance Step 3: Critical X Not Critical Determines the amount of time the AUO has to replace the blown fuses without exceeding 9.5 REM Standard:

Determines that the AUO has 30 minutes to replace the blown fuses, without exceeding Emergency Exposure Limit of 9.5 REM (Including travel time and previous exposure), If calculated in hours 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months SAT UNSAT N/A COMMENTS:

Performance Step 4: Critical X Not Critical Completes Acknowledgment and Authorization to Exceed Occupational Dose Limits form Appendix B of EPIP 15 Standard:

EPIP 15, Appendix B completed with the following critical elements:

Name and EIN of employee

9.5 Rem in the dose limit (rem) column on Appendix B

Applicants signature and date SAT UNSAT N/A COMMENTS:

NOTE Cntical Data on form is Name and UN of employee, the authorized 9 5 REM, Approval signature and date.

END OF TASK STOP TIME 5

JPMSROA3 APPENDIX B Page 1 of 1 ACKNOWLEDGMENT AND AUTHORIZATION TO EXCEED OCCUPATIONAL DOSE LIMITS READ THE FOLLOWING STATEM ENT BEFORE SIGNING THIS FORM:

I aknowIedge by signature on this form that i an volunteering for exposures in excess of 10 CFR 20.1201 limitsaid that I have been made awaethrough training or a briefing of the risks involved. Briefing materiai was presented from Appendix A of this procedure.

The persons listed below have acknowledged and volunteered to receive dose limits in excess of 100FR2O.1201 limits. Authorization is required by the Site Emergency Director to aiminister any emergency exposure limit. Authorization is acknowledged by Site Emergency Director signature on the bottom of this form.

Name Employee Ideenfleation Signatwe Doie Limit (Please print Last, First. M]) Number (E1N) (Rem) j________________________________ xxx5x9xxx 9.5 Rem Brief Description of Task:

Authorized by: I ADohicants SiRnature I / I I Site Emergency Director Time/Date LAST PAGE 6

JPM SRO A4 OPERATOR:

SRO___ DATE:_____

JPM NUMBER: SRO A4 TASK NUMBER: S-000-EM-21 (SRO ONLY)

TITLE: Emergency Action Level Classification K/A NUMBER: 2.4.4 1 K/A RATING: SRO 4.6 TASK STANDARD: The event is classified as a 3.2-S and the Initial Notification appendix is completed with correct information and within required times and notification is completed within required time.

LOCATION OF PERFORMANCE: Simulator or Class Room REFERENCES/PROCEDURES NEEDED: EPIP 1, EPIP 4 VALIDATION TIME: 30 minutes MAX. TiME ALLOWED: 15 minutes to classify and 15 minutes to notify PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMINER 1

kjjt

Class Room INITIAL CONDITIONS:

You are the SHIFT MANAGER. Unit 2 was initially manually scrammed from 100% power because of unisolable HPCI steam leak into Secondary Containment. The following conditions currently exist:

All attempts to isolate HPCI have failed

Reactor Coolant activity: 200 .tCi/gm Dose Equivalent 1-13 1

HPCI Room Radiation Level (90-24A): offscale high

HPCI Room Temperature (73-55A): 250 °F

Airborne Effluent Release Rate (0-SI-4.8.B.1.a.1): 5.4 x i0 Ci/sec

Release Fraction is greater than 1.0

Windisfrom 100°at5mph.

INITIATiNG CUES:

Identify the HIGHEST REOUIRED emergency classification, and complete the associated initial notification form. Raise your hand immediately once you have classified the event, and the examiner will then provide you with the EPIP youve chosen so you can begin completing the initial notification form.

JPM is Time Critical

JPM SRO A4 START TIME:

Performance Step 1: Critical Not Critical Refers to EPIP 1 to classify emergency event.

Standard:

SHIFT MANAGER refers to EPIP 1 and declares a SITE AREA EMERGENCY 3.2-S.

Based on an unisolable primary system leak is discharging into Secondary Containment and RM-90-24A (TABLE 3.2) is offscale high due to radiation.

SAT_ UNSAT N/A COMMENTS:______________________________

TIME Classified Performance Step 2: Critical Not Critical Implements EPIP-4 SITE AREA EMERGENCY.

Standard:

SHIFT MANAGER recognizes/implements a SITE AREA EMERGENCY in accordance with EPIP-4.

SAT_ UNSAT N/A COMMENTS:______________________________

3

JPM SRO A4 START TIME Performance Step 3: Critical Not Critical 3.0 EMERGENCY CLASSIFICATION ACTIONS WHEN the TSC SED has assumed the responsibilities from the SM SED THEN CONTINUE in this procedure at Appendix G. Otherwise continue in this procedure.

NOTE

Procedure steps can be performed concurrently.

All procedure steps within the body of this procedure can be delegated.

All procedure steps must be completed

All procedure appendices must be returned to the SED.

Step 3.2 (15 Minutes) and Step 3.4 (as soon as possible not to exceed 60 minutes from classification declaration) are time critical.

A STA or SRO should peer check Appendix A completion CAUTION Ongoing or anticipated security events or severe weather may present a danger to normal staffing and other Emergency Plan implementation processes. Observed all procedural steps careflully during security related events.

3.1 Activation of the Emergency Response Organization (ERO)

[1] DIRECT a RO or SRO to implement EPIP-4, Appendix B, Activation of the Emergency Response Organization (ERO) utilizing a notification listed below:

C] EMERGENCY C] EMERGENCY STAGING AREA (If events are on-going or anticipated that may present a danger to normal emergency center staffing such as security related issues.)

C] DRILL C] DRILL STAGING AREA (If events are on-going or anticipated that may present a danger to normal emergency center staffmg such as security related issues AND a drill is in progress.)

Standard:

Checks Drill Box and Directs an RO or SRO to implement EPIP-4, Appendix B SAT_ UNSAT N/A COMMENTS:________________________

4

JPM SRO A4 Performance Step 4: Critical Not Critical 3.2 State of Alabama Notification NOTE Notification of the Risk Counties / State of Alabama is required to be completed within 15 minutes from the time of emergency classification declaration.

[1] DIRECT a qualified SRO Communicator to COMPLETE Appendix A (Initial Notification Form) OR complete Appendix A.

Standard:

Completes Appendix A, critical portion is EAL Designator of 3.2-S, under Airborne Release column Releases above Federally approved limits is checked, under Liquid Release column Minor releases within federally approved limits is checked and Time and Date Event declared.

SAT_ UNSAT_ N/A COMMENTS:____________________________

5

JPM SRO A4 Performance Step 5: Critical X Not Critical 3.2 State of Alabama Notification

[2] DIRECT a RO / SRO to COMPLETE Appendix C (State of Alabama Notification) utilizing a completed Appendix A OR COMPLETE Appendix C.

Standard:

Notifies the State of Alabama within 15 minutes of classification.

SAT_ UNSAT N/A COMMENTS:____________

Time of State NOTIFICATION:

END OF TASK STOP TIME 6

JPM SRO A4 INITIAL CONDITIONS:

You are the SHIFT MANAGER. Unit 2 was initially manually scrammed from 100% power because of unisolable HPCI steam leak into Secondary Containment. The following conditions currently exist:

All attempts to isolate HPCI have failed

Reactor Coolant activity: 200 .tCi/gm Dose Equivalent 1-13 1

HPCI Room Radiation Level (90-24A): offscale high

HPCI Room Temperature (73-55A): 250 °F

Airborne Effluent Release Rate (0-SI-4.8.B.1.a.1): 5.4 x i0 tCi/sec

Release Fraction is greater than 1.0

Wind is from 1000 at 5 mph.

INITIATING CUES:

Identify the HIGHEST REOUIRED emergency classification, and complete the associated initial notification form. Raise your hand immediately once you have classified the event, and the examiner will then provide you with the EPIP youve chosen so you can begin completing the initial notification form.

JPM is Time Critical 7

EPIP.4 I BFN I SITE AREA EMERGENCY Rev 0034 I Page8of23 APPENDIX A Page 1 of I SITE AREA EMERGENCY INITIAL NOTIFICATION FORM

1. jI This is a Drill This is an Actual Event Repeat This is an Actual Event

2. The SED at Browns Ferry has declared a Site Area Emergency.

3. EAL Designator: 3. 3 (USE ONLY ONE EAL DESIGNATOR)

4. Radiological Conditions: (Check one under both Airborne and Liquid column.)

Airborne Releases Offsite Liquid Releases Offsite EJ Minor releases within federally approved limits 1 Minor releases within federally approved limit&

Releases above federally approved limits LJ Releases above federally approved limits 1

Q Release information not known Q Release information not known Tech Specs/ODCM) 1

( (Tech Specs/ODCM)

5. Event Declared: Time: Ccaas,.Yr Date:

Central Time

6. Protective Action Recommendation: None Completed By: ..S ca Peer Checked By:

ML14154A383

Text

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