ML102371281

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301 Draft Administrative Documents
ML102371281
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 08/25/2010
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
50-390/08-301
Download: ML102371281 (19)
v • d • e


Text

ES-401 PWR Examination Outilne Form ES-401-2 NRC Exam EacH ity: Watts Bar Date of Exam: May 2008 RO Tier RO K/A Category Points SRO-Only Points Group K K K K K K A A A AG Total A2 G* Total 1 2 3456 1 234

  • 215 34 318
1. 1 Emergency NIA NIA

& Abnormal 1 3 2 j 2

Plant Evolutions Tier Totals 4 7 4 5 4 27 3 2 3 4 2 1 3 4 2 2 2 28 1

ant 2 1 1 1 1 1 1 2 10 2

Systems Tier Totals 5 2 4 4 3 2 4 5 2 3 4 38

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 3 2 2 3 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7* The generic (C) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals

(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

DRAFF Watts Bar Nuclear Plant NRC Exam May 2008

ES-401 2 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Emergçv and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

E/APE # / Name / Safety Function Ki K2 K3 Al A2 G K/A Topic(s) lR 000007 (BW/E02&E1 0; CE/E02t Reactor 01 Reason for actions contained in EOP for reactor trip 4.0 1 Trip Stabilization Recovery / I 000009 Small Break LOCA / 3 03 Interrelation between S/Gs and small break LOCA 3.0 1 03 Basis for reduced power with one RCP out of service 3.0 1 000015/17 RCP Malfunctions / 4 000022 Loss of Reactor Coolant Makeup / 2.4.31 Alarms, indications, and response procedures 4.2 1 2

000025 Loss of RHR System / 4 02 RHR low press piping isolation 3.3 1 000026 Loss of Component Cooling Water 02 Monitor loads on CCW system from control room 3.2 1

/8 000027 Pressurizer Pressure Control 02 Normal values for RCS pressure 3.8 1 System Malfunction / 3 2.2.40 Apply Tech Specs 3.4 1 000038 Steam Gen. Tube Rupture / 3 000040 (BW/E05; CE/E05; W/E12) Steam 02 Adhere to procs and operate within limits of license 1 Line Rupture Excessive Heat Transfer / 4 01 Operate/monitor incore thermocouples 3.7 1 000055 Station Blackout / 6 01 Reasons for EOP actions 4.1 1 000057 Loss of Vital AC Elec. Inst. Bus / 6 000058 Loss of DC Power / 6 01 Op imps of battery chrgr and instrumentation 2.8 1 02 Determine/interpret cause of SWS leak 2.9 1 000062 Loss of Nuclear Service Water / 4 000065 Loss of Instrument Air / 8 04 Reason for crossover to backup air supplies 3.0 1 03 Manipulation of controls for desired results 3.8 1 W/E04 LOCA Outside Containment / 3 W/E1 1 Loss of Emergency Coolant 03 Monitor for desired results 1 Recirc./4 BW/E04; W/E05 Inadequate Heat Transfer 02 Adhere to procs and operate within limits of license 1

- Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric 2.1.20 Interpret and execute procedure steps 4.6 1 Grid Disturbances / 6 2 1 5 3[4 3 18 K/A Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant NRC Exam May 2008

ES-401 3 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Emergy and Abnormal Pnt Evolutions - Tier 1/Group 2 (RO)

E/APE # / Name / Safety Function Ki K2 K3 Al A2 G K/A Topic(s) 000001 Continuous Rod Withdrawal / 1 01 Rod bank step counters 2.9 1 000028 Pressurizer Level Malfunction / 2 01 PZR reference leak abnormalities 2.8 1 000032 Loss of Source Range NI / 7 01 Power supplies, md proper switch positions 2.7 1 000059 Accidental Liquid RadWaste Rel. / 9 01 Reasons for termination of a release 3.5 1 000067 Plant Fire On-site / 8 07 Operate/mon fire alarm reset panel 2.9 1 000069 (W/E14) Loss of CTMT Integrity / 5 01 Determine conditions and select procedures 3.3 1 000076 High Reactor Coolant Activity / 9 2.2.38 Conditions and limitations in facility license 3.6 1 W/EOl & E02 Rediagnosis & SI Termination / 3 02 Procedures associated with SI Termination 3.3 1 01 Component interlocks, failure modes, etc. 3.0 1 W/E13 Steam Generator Over-pressure/4 K/A Category Point Totals: 1 3 2 11 I Group Point Total: 9 Watts Bar Nuclear Plant NRC Exam May 2008

ES-401 4 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Fanstems- ]1er2/Gp 1O)

System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KIA Topic(s) 04 Effect on RPS of RCP malt 3.9 1 003 Reactor Coolant Pump 14 L/D tank bypass valve 2.8 1 004 Chemical and Volume Control 005 Residual Heat Removal 09 Dilution/boration consider 3.2 1 006 Emergency Core Cooling Eff. of core flood tanks malt 3.4 1 02 Maintain PRT tank pressure 27 1 007 Pressurizer Relief/Quench Tank 02 High/low surge tank level 3.2 1 008 Component Cooling Water 01 Monitor during PORV test 3.0 1 010 Pressurizer Pressure Control 08 Cause/eff with PZR level 3.2 1 012 Reactor Protection 2.4.31 Alarms, response procs 4.2 1 013 Engineered Safety Features 02 4.3 1 Actuation Reset ESFAS channels 022 Containment Cooling 01 Monitor auto operation 4.1 1 025 Ice Condenser 05 Abnormal glycol tank level 2.5 1 03 Containment sump level 3.5 1 026 Containment Spray 08 Steam removal eff on react 3.6 1 039 Main and Reheat Steam 03 Rad mon inds for SGTR 3.4 1 05 Control MFP speed 2.5 1 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 02 AFW malt effect on S/G 4.2 1 01 Power supp to system 062 AC Electrical Distribution loads 02 Cause/eff with AC system 2.7 1 063 DC Electrical Distribution 02 Power supp to fuel oil pps 2.8 1 064 Emergency Diesel Generator 05 Incomplete start relay 2.8 1 01 PRM malf eff on release 3.6 1 073 Process Radiation Monitoring 2.4.35 Local AO tasks and effects 3.8 1 03 CCW hx isolation valves 2.9 1 076 Service Water 02 Rx/turb bldg water temps 2.6 1 01 Sensor air 2.8 1 078 Instrument Air 05 Emergency entry 2.9 1 103 Containment 09 Cont. vacuum system 3.1 1 3[2 3 4 2 1 3 4 2 2 2 28 K/A Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant NRC Exam May 2008

ES-401 5 Form ES-401-2 NRC Exam ES-401 PWR Examination Outline Form ES-401-2 Plant Systems- Tier 2/GrouqgRO) =

System # / Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) 014 Rod Position Indication 02 Power loss to RPIS 3.1 1 028 Hydrogen Recombiner 02 34 1 andPurge Control Predict effect on cont pressure 033 Spent Fuel Pool Cooling 2.2.36 Effect of maint on LCO status 3.1 1 045 Main Turbine Generator 17 Effect on reactor of raising load 2.5 1 055 Condenser Air Removal 2.4.3 Identify post-accident instrument 3.7 1 056 Condensate 03 Cause/eff with MFW 2.6 1 068 Liquid Radwaste 10 Rad mon eff on on Liq Rad Sys 2.5 1 075 Circulating Water 02 Interface with radwaste discharge 2.9 1 079 Station Air 01 Cross-tie with lAS 2.7 1 086 Fire Protection 01 FPS malf eff on S/D capability eqp 2.7 1 2 10 K/A Category Point Totals: Group Point Total:

Watts Bar Nuclear Plant NRC Exam May 2008

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 NRC EXAM Facility: Watts Bar Date of Exam: May 2008 RO Category KJA # Topic RD SRO-OnIy IR # IR 2.1.5 Ability to use procedures related to staffing/overtime. 2.9 1 2.1.28 Purpose of major system components/controls 4.1 1 1

Conduct 2.1.36 Procedures/limitations for core alterations 3.0 1 of Operations Subtotal 3 2.2.12 Knowledge of surveillance procedures 3.7 1 2.2.44 Interpret control room indications 4.2 1 2.

Equipment Control Subtotal 2 2.3.7 Ability to comply with radiation work permits 3.5 1 2.3.14 Knowledge of radiation or contamination hazards 3.4 1 3.

Radiation Control Subtotal 2 2.4.13 Knowledge of crew roles during EOP usage 4.0 1 2.4.37 Knowledge of lines of authority during E-plan. 3.0 1 4

Emergency 2.4.42 Knowledge of emergency response facilities 2.6 1 Procedures /

Plan Subtotal 3 Tier 3 Point Total 10

DRAFT ES-401 PWR Examination Outline Form ES-401-2 NRC EXAM Facility: Watts Bar Date of Exam: May 2008 SRO Tier RO K/A Category Points SRO-Only Points Group K K K K K K A A A AG Total A2 G* Total 1 234561 234 *

1. 1 6 Emergency N!A NIA

& Abnormal 2 2 2 4 Plant Evolutions Tier Totals 3 2 5 1

2.

Plant 2 2 3 Systems Tier Totals 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7

2 1 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RD and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RD exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RD and SRO ratings for the RD and SRD-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRD-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RD and SRD-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals

(#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

DRAFT Watts Bar Nuclear Plant NRC Exam May 2008

ES-401 2 Form ES-401-2 NRC EXAM ES-401 PWR Examination Outline Form ES-401-2 Emegpcd Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

E/APE # / Name / Safety Function Ki K2 K3 Al A2 G KJA Topic(s) H #

000007 (BW/E02&E10; CE/E02) 5 39. 1 Reactor Trip - Stabilization - Interpret reactor trip first-out indication Recovery/i 000022 Loss of Reactor Coolant 2.1.7 Evaluate plant pen and make operational judgements 4.7 1 Makeup/2 000025 Loss of RHR System /4 I Interpret running RHR pump amperage 2.9 1 000027 Pressurizer Pressure 2.4.6 EOP mitigation strategies 4.7 1 Control System Malfunction /3 000058 Loss of DC Power / I Determine loss of DC power has occurred/backups I/S 4.1 1 W/E1 1 Loss of Emergency Coolant 2.2.22 Knowledge of LCOs and safety limits I Recirc. /4 K/A Category Point Totals:

f [ Group Point Total:

6 Watts Bar Nuclear Plant NRC Exam May 2008

ES-401 3 Form ES-401-2 NRC EXAM ES-401 PWR Examination Outline Form ES-401-2 Emeigv and Abnormal Plant Evolutions Tier 1/Group 2 (SRO)

E/APE #1 Name / Safety Function Ki K2 K3 Al A2 G K/A Topic(s) 000059 Accidental Liquid RadWaste Rel. /9 3 Misleading Rad Mon inds for accidental release 3.6 1 000068 (BW/A06) Control Room Evac. /8 2.4.8 Use of abnormal procs in conj with EOPs 4.5 1 W/E13 Steam Generator Over-pressure! 4 1 Interpret conditions and select appr procedures 3.4 1 CE/All; W/E08 RCS Overcooling - PTS /4 2.4.18 Specific bases for EOPs 4.0 1 K/A Category Point Totals: JE 2 Group Point Total: 4 Watts Bar Nuclear Plant NRC Exam May 2008

ES-401 4 Form ES-401-2 NRC EXAM ES-401 PWR Examination Outline Form ES-401-2

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System # / Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) lR 003 Reactor Coolant Pump 5

Effect of VCT press 2.8 1 012 Reactor Protection 2.2.44 Verify system status 4.4 1 9 Total loss of feedwater **TBD 1 061 Auxiliary/Emergency Feedwater 2.2.37 Determine operability 4.6 1 064 Emergency Diesel Generator 076 Service Water I Loss SWS 3.7 1 K/A Category Point Totals: --

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(TBD): Please note: Internal discussion with exam team members determined that the Importance Rating of K/A 061A2.09 is greater than 2.5. This discussion included the following points:

1. Safety significance of total loss of FW on Watts Bar Nuclear Plant operation and entry into Emergency Operating Procedures.
2. Recent industry operating experience related to total loss of feedwater.

Watts Bar Nuclear Plant NRC Exam May 2008

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ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 NRC EXAM Facility: Watts Bar Date of Exam: May 2008 SRO Category K/A # Topic RO SRO-Only IR # IR 2.1.23 Perform system and integrated procedures all modes 4.4 1 2.1.34 Knowledge of primary/secondary plant chemistry limits 3.5 1 1

Conduct of Operations Subtotal 2 2.2.40 Ability to apply Tech Specs for a system 4.7 1 2.

Equipment Control Subtotal 1 2.3.6 Ability to approve release permits 3.8 1 2.3.15 Knowledge of radiation monitoring equipment 3.1 1 3.

Radiation Control Subtotal 2 2.4.23 Basis for prioritizing emergency procedures implementation 4.4 1 2.4.29 Knowledge of the emergency plan 4.4 1 4

Emergency Procedures /

Plan Subtotal 2 Tier 3 Point Total 7

ES-401 Record of Rejected K/As Form ES-401-4 RO Examination Tier I Group Randomly Selected K/A Reason for Rejection 1/1 000022 Category K2 Category K2 has no K/As with importance rating > 2.5. Randomly selected Category G, with a randomly selected K/A of 2.4.31.

1/1 000058 Category K2 Category K2 has no K/As with importance rating > 2.5. Randomly selected Category Ki with a randomly selected K/A of Ki .01.

1/1 000062 Category Ki Category K1 contains no K/As. Randomly selected another category (K2). This category also contains no K/As. Continued random selection of categories and obtained Category A2, with a K/A of A2.02.

1/1 000065 Category K2 Category K2 has no K/As with importance rating > 2.5. Randomly selected Category K3 with a randomly selected K/A of K3.04.

1/2 000076AA1 .04 Failed fuel monitor not part of current design basis at Watts Bar. Since there were no other K/As in Category Al with importance rating > 2.5, selected another Category, obtaining Category Generic. Note: this Category re-selection was not entirely random, but was implemented in order to improve sampling balance in Category Generic, for Tier 1, Group 2. After selecting G Category, performed_a_random_sample,_and_obtained_G2.2.38.

2/1 005K5.04 Low importance rating (2.1). Randomly resampled and obtained 005K5.09.

2/1 039 Category K6 Category K6 has no K/As with importance rating 2.5. Randomly resampled and obtained Category KS.

2/1 078 Category K5 Category K5 has no K/As with importance rating > 2.5. Randomly resampled and obtained Category Ki.

2/1 103 Category K6 Category K6 has no K/As with importance rating > 2.5. Randomly resampled and obtained Category A2.

2/1 026Al .05 Chemical additive tank for Cont. Spray not part of Watts Bar design. Randomly resampled remaining K/As in Category Al and obtained_Al .03.

2/2 033 Category K6 Category K6 has no K/As with importance rating > 2.5. Randomly resampled and obtained Category A4.

2/2 033 Category A4 Category A4 has no K/As with importance rating 2.5. Randomly resampled and obtained Category G.

2/2 045K5.08 Low importance rating (1.8). Resampled and obtained K5.lO. Resampled repeatedly (due to numerous low importance ratings) until obtaining_K5.17.

2/2 055 Category K4. Category K4 has no K/As with importance rating > 2.5. Randomly resampled and obtained Category G.

2/2 056 Category K3 Category K3 has no K/As with importance rating > 2.5. Randomly resampled and obtained Category Al.

2/2 056 Category Al Category Al has no K/As with importance rating > 2.5. Randomly resampled and obtained Category Kl.

2/2 068 Category K2 Category K2 has no K/As with importance rating 2.5. Randomly resampled and obtained Category K6.

2/2 075Kl .05 Low importance rating (2.0). Resampled and obtained Kl .02.

2/2 079 Category K2 Category K2 has only one K/A and it has a low importance rating (2.3). Resampled and obtained Category Al.

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ES-301 Administrative Topics Outline Form ES-301-1 Facility: WATTS BAR Date of Examination: May 2008 Examination Level (circle one 0/ RO Operating Test Number 1 Administrative Topic Type Describe activity to be performed Code (see_Note)

Hand calculation of Boric Acid & Primary Water Conduct of Operations N integrator settings for a manual makeup to the VCT.

Conduct of Operations N Determine work hour restrictions.

Equipment Control N Hand calculation of RCS water inventory balance 1-SI-68-32.

Calculate radiation dose to perform job in an area with Radiation Control M two possible access routes and determine if dose exceeds administrative limits.

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

Type Codes & Criteria (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs;< 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (>1)

(P)revious 2 exams (< 1; randomly selected)

DRAFT NUREG-1021, Revision 9

\ rv_z ES-301 Administrative Topics Outline Form ES-301-1 Facility: WATTS BAR Date of Examination: May 2008 Examination Level (circle one): RO Operating Test Number r Administrative Topic (see_Note)

Type Describe activity to be performed SRO review of hand calculation of Boric Acid & Primary Conduct of Operations N Water integrator settings for a manual makeup to the VCT (must find error).

Conduct of Operations N Determine work hour restrictions.

Equipment Control N Hand calculation of RCS water inventory balance, 1-SI-68-32.

Calculate radiation dose to perform job in an area with Radiation Control M two possible access routes and determine if dose exceeds administrative limits.

Emergency Plan M Classify the event per the REP and determination of PAR, per EPIP 4.

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

Type Codes & Criteria (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

NUREG-1021, Revision 9

ES-301 uRAF Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: May 2008 Exam Level: RO Operating Test No.: I B. 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Eu nction

a. Synchronize Main Turbine to grid with failure of automatic 4S voltage regulator. MALS
b. Manual makeup to VCT with failure of Primary Water to 1 automatically stop. MAS
c. Transfer Containment Spray Suction to Containment Sump 5 Per ES-1.3. DS
d. Raise Cold Leg Accumulator Level. DENS 3
e. Transfer from two RHR train operation to single (A) RHR 4P train operation with failure of mini flow valve to automatically MALS open.
f. Respond to a Source Range instrument failure. DS 7
g. Restore charging and letdown with failure of letdown 2 temperature controller. NAS
h. Place Upper Containment Purge in service. NS 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
a. Local SIG level control from Motor Driven AFW Pump. DRE 4S 6
b. lA-A Diesel Generator idle start for warmup. D
c. Local emergency boration DREA 1

© All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SRO-l I SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrom bank <91<8 / <4 (E)mergency or abnormal in-plant > 1 / 1 / 1 (EN)gineered safety feature - / - / > 1 (control room system)

(L)ow-Power / Shutdown > 1 / > 1 / > 1 (N)ew or (M)odified from bank including 1(A) 2/ > 2 / 1 (P)revious 2 exams < 3/ < 3 / < 2 (randomly selected)

(R)CA 1/1 1>1 (S)imulator

ES-301 Dw Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: May 2008 Exam Level: SRO-l Operating Test No.: I B.1 Control Room Systems©(8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. (Not required for SRO-l.)

-_(_CJ

. Manual makeup to VCT with failure of Primary Water to 1 automatically stop. MAS

c. Transfer Containment Spray Suction to Containment Sump/ 7 5 Per ES-1.3.
d. Raise Cold Leg Accumulator Level. DENS 3
e. Transfer from two RHR train operation to single (A) RHR 4P train operation with failure of mini flow valve to automatically MALS open.

f DS 7

g. Restore charging and letdown with failure of letdown 2 temperature controller. NAS
h. Place Upper Containment Purge in service. NS 8 In-Plant Systems© (3 for RO); (3 for SRO-l); (3 or 2 for SRD-U)
a. Local SIG level control from Motor Driven AFW Pump. DRE 4S
b. lA-A Diesel Generator idle start for warmup. D
c. Local emergency boration 1

© All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrom bank <9/ <8 / <4 (E)mergency or abnormal in-plant 1 / 1 / 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown > 1 / > 1 / > 1 (N)ew or (M)odified from bank including 1 (A) > 2/ > 2 / > 1 (P)revious 2 exams < 3/ < 3 / < 2 (randomly selected)

(R)CA >11>1 1>1 (S)imulator

ES-301 D FCntroI Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: May 2008 Operating Test No: I

[ Exam Level: SRO-U B.1 Control Room Systems©(8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. (Not required for SRO-U.)
b. (Not required for SRO-U.)
c. (Not required for SRO-U.)
d. Raise Cold Leg Accumulator Level. DENS 3
e. Transfer from two RHR train operation to single (A) RHR 4P MALS train operation with failure of mini flow valve to automatically open.
f. (Not required for SRO-U.)
g. Restore charging and letdown with failure of letdown 2 NAS temperature controller.
h. (Not required for SRO-U.)

In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

a. (Not required for SRO-U.)

6

b. lA-A Diesel Generator idle start for warmup. D
c. Local emergency boration. DREA 1

© All RD and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)Iternate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irectfrom bank 9/ <8 / <4 (E)mergency or abnormal in-plant 1 / ? 1 / > 1 (EN)gineered safety feature - / - I > 1 (control room system)

(L)ow-Power I Shutdown > 1 I > 1 / > 1 (N)ew or (M)odified from bank including 1 (A) 2/ 2 / 1 (P)revious 2 exams < 3I < 3 / < 2 (randomly selected)

(R)CA >11>1 1>1 (S)imulator

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