ML14234A010
| ML14234A010 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/21/2014 |
| From: | Division of Reactor Safety II |
| To: | Virginia Electric & Power Co (VEPCO) |
| References | |
| 50-338/14-301, 50-339/14-301 | |
| Download: ML14234A010 (73) | |
Text
{{#Wiki_filter:Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Reactor power is 100% Reactor Coolant System boron concentration is 1250 ppm. In-service boric acid storage tank concentration is 14,660 ppm. Core age is 7038 MWD/MTU Movement of control rods is not desired. Tavg is higher than Tref. INITIATING CUE You are requested to calculate the amount of boric acid required to lower Tavg by 2°F. Record the answer below. Gallons of boric acid ADMINJPM 1aALL Page: 1 of7 NAPS 2014 NRC EXAM
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM RXXX TASK Calculate the amount of boric acid required to reduce Tavg by 2°F. TASK STANDARDS The correct amount of boron acid was calculated. KIA
REFERENCE:
G2.1.37 (4.3/4.6) ALTERNATE PATH: N/A TASK COMPLETION TIMES Validation Time = 15 minutes Start Time = Actual Time = minutes Stop Time = PERFORMANCE EVALUATION Rating [1 SATISFACTORY [ ] UNSATISFACTORY Candidate (Print) Evaluator (Print) Evaluators Signature / Date EVALUATORS COMMENTS ADMIN JPM la ALL Page: 2 of 7 NAPS 2014 NRC EXAM
Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation) OPERATOR PROGRAM RXXX READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. 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. Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 Reactor power is 100% Reactor Coolant System boron concentration is 1250 ppm. In-service boric acid storage tank concentration is 14,660 ppm. Core age is 7038 MWD/MTU Movement of control rods is not desired. Tavg is higher than Tref. ADMIN JPM 1 a ALL Page: 3 of 7 NAPS 2014 NRC EXAM
INITIATING CUE You are requested to calculate the amount of boric acid required to lower Tavg by 2°F. Record the answer below. Gallons of boric acid EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s)) Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s)) TOOLS AND EQUIPMENT Calculator Station Curve Book (or copies of 1-SC-2.1, 1-SC-2.2, 1-SC-2.4, and 1-SC-3.4) Station Data Book (or a copy of the ITC curve) ADMINJPM 1aALL Page:4of7 NAPS 2014 NRC EXAM
PERFORMANCE STEPS START TIME I Determine isothermal temperature coefficient (ITC). I Procedure Step Critical Step SAT[] UNSAT[] Standards From the ITC curve in the Reactor Data Book, determines ITC at 100% power and 1250 ppm boron is -19.0 pcm/°F Notes/Comments 12 I Determine desired reactivity insertion. I Procedure Step Critical Step SAT[] UNSAT[] I Standards Multiplies the amount RCS temperature is high by ITC. (2°F) x (-19.0 pcml°F) = -38 pcm. 1 Notes/Comments ADMIN JPM la ALL Page: 5of7 NAPS 2014 NRC EXAM
I3 I Determine boron coefficient. I Procedure Step Critical Step SAT[] UNSAT[] 1 Standards From 1-SC-3.4, determines boron coefficient at 7038 MWD/MTU is - 6.75 pcm/ppm. Notes/Comments 14 I Determine desired change in boron concentration. I Procedure Step -j Critical Step SAT[] UNSAT[] I 1 Standards Divides the desired reactivity insertion by the boron coefficient. (-38 cm) ÷ (-6.75 cm/m) = 5.6 m Notes/Comments ADMIN JPM la ALL Page: 6of7 NAPS 2014 NRC EXAM
5 Determine gallons of boric acid required to raise RCS boron Procedure Step concentration 5.6 ppm. Critical Step SAT[] UNSAT[] Standards Using 1-SC-2.2, determines the gallons of boric acid required to be added. Gal. acid = (9262 ft3) x (44.779 lbm/ft3) x In p4,660 ppm 1250 ppm
8.22 Ibm/gal 14,660 pprr 1255.6 ppm 50,455 x In 1310 13404k
= 21 gallons of acid Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME ADMIN JPM la ALL Page: 7 of 7 NAPS 2014 NRC EXAM
VIRGllTIAPOWER l-SC-2.1 NORTHANNA POWERSTATION REVISION 2 PAGE1OF3 BLENDED FLOW The general equations for Blended Flow boron concentration calculations are as follows: .. For a given acid flow, Boric Acid Storage Tanks (BAST) boron concentration, and Primary Grade water (PG) flow, the boron concentration in the blended flow will be as follows: (Gallons of Acid)x BAST Boron Conc) Boron Conc of Blended Flow = (Gallons.of Acui).+/-.(Gallons. of PG)
- For a given acid flow, BAST boron concentration, and desired boron concentration in the Blended Flow, the PG flow will be as follows:
= Gallons of Acid x [(BAST Boron Conc) (Desired Blended Flow Boron Cone)]
Gallons of PG Desired Blended Flow Boron Conc
- For a given PG flow, BAST boron concentration, and desired boron concentration in the Blended Flow, the acid flow will be as follows:
(Gallons of PG)x (Desired Blended Flow Boron Conc) Gallons of Acid = (BAST Boron Conc) (Desired Blended Flow Boron Conc)
The following tables contain the gallons of PG needed per gallon of acid for a given BAST boron concentration and desired Blended Flow boron concentration. These values may be used to determine the total PG and acid required for a given makeup. For example, if a 2600 gallon, 2350 ppm makeup is desired and the BAST is at 14,000 ppm, the table shows that 4.96 gallons of PG will be required for each gallon of acid in the makeup. The multiplier for the PG and acid flows will be {2600 ÷ (I + 4.96)} 436.2. Therefore, (436.2 x 1) = 436 gallons of acid and (436.2 x 4.96) = 2164 gallons of PG will be needed for this 2600 gallon makeup. APPROVED BY: DATE:
VIRGINiA POWER i-SC-2.2 NORTh ANNA POWER STATION REVISION 2 PAGEIOF3 BORON ADDITION The general equation for the gallons of Boric Acid from the Boric Acid Storage Tanks (BAST) to add to the Reactor Coolant System (RCS) to increase the RCS boron concentration is as follows:
= (Volume of RCS)x (Density of RCS Water) BAST ppm Initial RCS ppm Gallons ofAcid Density of Charging Flow I BAST ppm Desired RCS ppm
-
Below are typical values to use in the equation: Density of Charging Flow: 8.22 lbmlgallon BAST ppm: 14,350 ppm (This is an average of the 12,950 ppm minimum value and 15,750 ppm maximum value listed in Tech Specs 3.1.2.7 and 3.1.2.8) Volume of RCS: 9759 ft 3 with the Pressurizer Solid 8757 ft 3 with the Pressurizer level at 28.4% 9262 ft 3 with the Pressurizer level at 64.5% Density of RCS Water: RCS RCS RCS Water Temp Pressure Density 100°F 14.7 psia 6 1.999 Ibm/ft 3 200°F 350 psia 60.176 lbmlft 3 300°F 400 psia 57.3 80 ibm/ft 3 400°F 900 psia 53.877 ibm/ft 3 500°F 2000 psia 49.643 lbmlft 3 547°F 2250 psia 47.056 lbmlft 3 5 80.8°F 2250 psia 44.779 lbm/ft 3 NOTE: RCS Water above 100°F is typically a subcooled liquid and NOT a saturated liquid. Density values should be determined for the given RCS temperature and pressure. APPROVEDBY:______________________ DATE:_________
VIRGINIA POWER l-SC-2.4 NORTH ANNA POWER STATION REVISION 3 PAGE 1 OF 9 BORON DILUTION The general equation for the gallons of Primary Grade Water (PG) to add to the Reactor Coolant System (RCS) to dilute the RCS boron concentration is as follows: (Volume of RCS )x (Density of RCS Water) Initial RCS Boron Concentration Gallons of PG in 1 Density of Charging Flow Desired RCS Boron Concentration Below are typical values to use in the equation: Density of Charging Flow: 8.22 ibm/gallon Volume of RCS: 9759 3ft with the Pressurizer Solid 3 with the Pressurizer level at 28.4%. 8757 ft 9262 ft 3 with the Pressurizer level at 64.5% Density of RCS Water: RCS RCS RCS Water Temp Pressure Density 100°F 14.7 psia 61.999 ibm/ft 3 200°F 350 psia 60.176 ibm/ft 3 300°F 400 psia 57.380 Ibm/ft 3 400°F 900 psia 53.877 Ibm/ft 3 500°F 2000 psia 49.643 ibm/ft 3 547°F 2250 psia 47.056 ibm/ft 3 580.8°F 2250 psia 44.779 lbm/ft 3 NOTE: RCS Water above 100°F is typically a subcooled liquid and NOT a saturated liquid. Density values should be determined for the given RCS temperature and pressure. APPROVED BY: 7á DATE: vi loi
1 -SC-3.4 DOMINION Revision 15 NORTH ANNA POWER STATION Page 1 OF 1 NORTH ANNA UNIT I CYCLE 24
-
BORON COEFFICIENT VS. BURNUP FOR ZERO PERCENT POWER
-82
-8.0
-7.8
>
V -7.6 0. 0 C.)
-7.4 U,
0 9 a) C.) -7.2 a) 0 C.) 0 0 -7.0
-6.8
-6.6
-6.4 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 22000 Cycle Burnup (500 MWD/MTUIdiv)
APPROVED BY: C4 DATE: /7I/I3
C C rrIii TTi- rnui Tn hhFIi TTT FFFii 777 FrFiii iTT FFFFfl iii i-rnIri- iiT}V F iii nrriii Ti-F mri-li ITT rrrfl1 -v-i--i- rrrm ITT rrrrur -i-vT rrriii liT rrr rrr TTT F rrl 1ll N LLL_iJJ ILL LI-I-dId ILL LLL_IJJ ILL LLI-__il. ILL LLI-_I-J. .11! LLL_I-IJ. III LLL_LJ. dId kLL I-I-I. LI_I-_Ill LLL LI-I-_Ill ILLLLl__Ill ILL.I-LL_IllJLL LLL_I_iJlIL LLL_I_I_IIIL LLLi_I_I.llI LLLI_I-Ill.l
-i_I_I__i_i-I 4--I-I- i_iI_I_I-I ILL I-Il__i_i_I 4-La- -LI-IIIl. 414- I-I-II_I-I- 44-I- I-I--iIII. -414 LI-i_i_i_i- 4.-Il LI--I- 111444
-i-III-I-I 4-I-i- II--II-I--I 4+-I- l-I--ll-4-4 4+-I- I-I-III-I 44+ F-I-III-I- -44+ I-I-I-III- -144 I-I-I-III- -144 i-I-I- 111444 C
!!! rr mt m rm i-ri- i-fl mn i-n- i-rn i-rn i-rn i-rn i-rn ri-n i-rn I I I I-li- rn C
mrrn TIF mri-i-I TT1
-
Frii-i-I
!!
-ryrrmrmnl I!!
i-IT Fmrn i-rn rrrrnl-IT i-FrFrI-fijI 7FF rriiii N rruu-iI-i-ri rrri--i-] ITT Frrii-l ITT rrr-ii-i -ITT rFrrni lIT Fri in rrrrn N LI-I_Ill LLL LI-I-_Ill ILL LLI-_IlJ ILL LLI-_I_iJ ILL LLL_IlJ. ilL LLL_I_I_l. III LLL_I-I-I. JddI I-I_I- Ill LI-I_Ill ILL I-LI-_Ill IlL LI-I_Ill ILL LLL_i_iJ 444 LLL_I-IJ. III LLL_I_Il.14L II 1 LLL_I-LL LI_I_Ill
-I-III-a-I 44-I- IIIi-i-I 4-I-i- II-ll-4-l 444- I-I-III-I 444 I-II-II-I- -444 I-I-I-III- -444 4-I-I-IIi- -444 111444
-IIll4 t+t- i-i-IHI-I 4+1- 1-IiiHI 4+4 I-I-iiHI 4+4 II-I-ii-H 44+ I-I-I-i-i-I- 44+ I-I-I-II-4i H4+ iii44 C
iiI- -i-ir -i -r----i-i r-r-i- -r nn-i- i--rr i--r--r FnT -IT rnT Trr rrr -i-rr Trr rrr nrr nrr nn7 TrT T1F C
- Ccr TTi- FrrTh-Il ITT FFFi_n1 171 Fri-i-i-I i-IT FFi-iii 17T rrrrii i-IT 7FF nt li-I ni C
LI-l:ljj ::: CCCD:i] ::: CCC:]]] 211 CCC:]:]: ]1I rrrmm: EEE:C] Eli ECCECiC1 ]]f iThTh iii N
.LLI_IJJ IlL LI-I-_UI ILL I-CL_ill ILL I-Li__Ill 414 LI-L_IjJ lii. LLL_i_I1 141 LLLLlI. 141 LI-LIla
-LI_I_Ill IlL I-LI-ill IlL I-LIill 141 LLI_I_Il 411 I_LI-4_l4 411 I_I-L_I_Il. 4-il LLI__tl_l. 111 IIi. 41-i
-IiIl44 4+4- I-iI14 4+4- I-I-II-HI --1-4 IIIiI-I 44+ I-I-I-II-i- 44+ I-I-I-III- 444 I-F-I- III- 444 111444 riii-i-i tti- hiiI-I-I -Itt i-i-II--I--I itt i-i_ni-l -Itt I-i-i-II-I--ITt hi-frIII--I-It i-hi-III- It III- -I-I-I C
C Ii-I i-rr Tfi
-iiF mrn rrr rr1- Fi-1 Err::]
1 rrr Ii- i-n-i- i-mr ri-t i-n-F i-i-i- rrr i-i-li i-i-I T o rTm -n-i- - 00 CCC]]] : : ITT FFrin fiT Frrmii i-iT rrrrii i-IT rrrrri i-Il Fri i-1 LI-I-Ill LL_ LI-I-Ill LLLIIJ ILL LLL_lll LLL.IIl ill LLL_LJ_i ilL L&_I-lI UI d3 LLL lJJ LLL_I11 ILL I-LI_Ill 1 L LLL_iII ILL LLI-ll1 ILL LLL_i_l1 111 LLL III ijLL LI_I 441 i_I_L 111
-I--IIil-i 444- 1-i1-444 4 4- I-I--Iill 444 II--IIIl ILL I-I--IIIl 4-Il I-I- 114 444 I-I-III 444 Ili-444 I-IIi44 +4-I- I-iII-I-I 4 I- I-I-IIHI 4+4- I-I-III-I 4-1 I-I-I-I1 -14+ I- I-II-I -444 I-I-I- HII -144 +1-I- I-ih 444 C
-rii-I-i-I -l--I-r mni-i--i 7 r i-mri-i-i TTT FmII--i i-I FFrII-1 iTT mmri--i i-IT rrrnii lrT TFF I11 i1T C
© i-FT -n-n i-ri- i-i- i-FT -ri-i- i-i- rFT T i-mT i-nn i-rn i-i-$ I i-n-i- I I irt i-F ID iii II III II III Ill II iii I Ill III III III III I III I I III II I-LI-_Ill LLL LLI-_IJI 4 L LLL_IIl ILL I-LL_Ill 44 I-LI-_I_Il 14 LI-L_I_Il 1411 I-LI-_Li_i lii LLL LI_i Ill I-Li__Ill ILL LLL_I11 I I- LLL_I14 Ill LI-I-_ill dl LLL_I_Il I I LLL_I-I_I 1 1 I-LI-_Li_i 111 LI-I- LI_I_Ill
© I-Ii--I4-l 44-I- I-lII 4+1- I-I-HI-I4 4+4 I-I-I-iI 44 I-II-h--i-l -4 I-I-I-HIi 44 I-I-I-I-h--i 4-14 i-I-I- I-II 4-14 eq biil nniI-l-I tti-Ti-i-i-III-I-I rni-u tti-7Th i-i-Ih-HI rrrrn itt TTr i-i-iii rrriii t
i-i-i-i-i-II-I FFFrI I-It i-IT i-i-i-IIill-It FFrrnl n-IT i-i-i-IIi FFFII i-IT t ti-i-7FF IIi-I-It rn ui-i o D. i-FT i-F ri-r YT I - i-FT i-FT iTT i-FT T V T flE I T 7mT I I i-FT T LLI_ll_ LI-I_ll_ LI-I-.dll LI-I-_Ill IJ i J__ LI_I LI-I-_Ill ILL LI-I-_Ill ILL LI-LIll ILL I-LL_I_il 41 I-I-L II IlL LLI-_iI 111 LI-I-_I-Li 411 LI-I- LI-i 414 0 t C Ct I-iII--I-I I-iIl-I4
-rni-u rrrm ILL 4+I-ti-i-fli-4-I-I_i-Il I-I-II-4 nini-i--i nrrlfi 444 4+4-TTT TIT LI-ii-Il I-I-iiHI rrrii-i rrru--n 444
#4+
Ttt 1 7 LI-IIIl I-I-HIi-I i-rnii--i rrrin
-Il 4+
tt T I-I-I Iil I-i- rin rrin IHI 444
-14+
t fiT I-I-I--Si-i I-I-I-HI-I rIrni--I r-rcruu 444
#4+
i-It m I-LI-Iii I-I-I-i-Frrn i-Frrii I-Ii 414 niI i-IT 4+ Li_I-4-I-I-Ti-i-7FF 1-LI HIi rni-I-I ii-i 44 144
.2 !
s1 C
!ll LLLII_ LI-I-_Li_ LI-I-I_il LLL_Ill J_ j__
I-LI-Ill L_L I-LL_ill ILL LI-I-_i_il 1 4 I-LI-I_Il I LI-LI_il 411 LI-I-_I-Il ill LI-I-_I-Li Ill LLL I-Li lid I-LI__Ill ILL I-I-I-_Ill IlL I-LI-_i_il 1 1 LI-LI_Il 4 LLL_I_il Ill LL_I_II III LLL LI_I 4-Il Li_I- LI_I_Ill . I-iiI44 ++I- I-I-i444 444- I-I-iIi4 4 4 I-I-III-I 4 I-I-I-Ii-I #44 I-I-I-HI-I #44 4-I-I-II-I 44 4-I-I- Iii 444 i-iiVt-i tti- I-Iii-I-I tt4- I-I-II-I-I 4 4- i-I-iII-I 44 i-I-I--i-h-# -Itt i-i-i-HII -144 4-I-I- -HI-I H-It ti-I- i-II-I-I-I
© rnui rrrm Ti- Frri-Ii Trl mrili 7 7 rrrIi i-i- mrrnn r 1
i- rrr111 -ITT rrrnii i-IT vrr rii i-IT TTF rrrun ITT rrrrni i V rrri 1 -IT mmrlIl IflIT rrrrii ri-v rmr i-ri iii ti-F rn C LLLIII LLL_ill ILL LI-I-Jl_ I-LI-_Ill ILL LLL_IIl I-LI-_Ill 1
1 LI-I__iJ___LL_I_iJ LI- 41 LI-I-_i_Il II I LI-I-_I-i_i 141 LI-I-_I-Li I_I-i Ill LI-I- 4_I_I LI-I 114 o I-I WI 4 C Ll_LllI ILL LI-I-Ill ILL LI-I-_Ill 4 L I- Ill 44 LI-I-_il_IA 144 I-LI-_I-Il III I-LI-_I_II Ill LI-I- -I-LI Ill Cd I-I-Hi-I-I +4-I- I-I-Hl-I4 4+4- I-I-HI-I-I 4 4- HI-I-I 4+ I-I-I-Ii 44+ I-I-I-I-II 4-4+ I-I-I-HIi 44 4-I-I- -HHI-144 FInii tti- i-i_i__I-i-i ttt ri-FI-I-I -i t riii t i-i-i-i -itt hi-i-Iii it i-rn_I_i_I i-IT ti-n -rii fit C mrni TTT rnrm TV nrrrii 1 rnnui-v IT FFFWi -ITT mrrrn fiT i-Frrii fi 7FF i-ri C CflTThfl mrrm rmrm r rn 0
--- rmrmn i -FFifl JI -rm j]jl i 0
I-I-I-Ill LL I-Ill LL LLI-_I_iJ L LI-I-_i_il IlL LLI-_Lil 11 I-LI-_I-il IlL LLL 4_I_I 11 LI-I- 4_Li 14_i LI-i__ill II I-Ill III LI-I-_Ill I I I-I-LI-il 411 I-I-k_i_il 11 Li_I-_I-il 411 LLL_LI_I 14 LI-I- Li_i 114 00 Lli444 44 i444 444- I-I-HI4 4 4 I-I-I-i44 444 I-Ii-iil 44 I-I-I-iil 444 4-I-I-IiI 44 4-I-I- -iii 444 i-I-Ii 4+ ii-I-I ++i- I-I-I-i t + I-I-I-IHI 44+ I-NI-h--I-I -Ii I-I-I-III 44t tI-I-H14 -rt 4-rI- -HIi 4-14 mr-I-n TV liii 7Th FFr i 1 T mnii-i -I-i--i- mrii-i iT i-Fr_ri-I ifi i-mmrn i-IT 7FF i-1i i rrrui TI FFl ITT FFF il 1 T FFFfl -ITT mnii--i ii i-mrri-I uT rmrrri -I-IT 7FF -rrii-I-r
© z Ct Ct mnni-LI-I-Ill LI-I_Ill LI IL C) fill I-Ill I-Ill ITT ILL ILL FE I-I-Ill iir I-Ill
I I
L I rmnmm LI-I-Ill LI-I-Ill 1 lU ILl fiEIThl LI-I-_Ill LI-I-_Ill II 41 F i_I_i LLL_I_Il LI-I-_i_Il III 141 mr uii LLL_Li_I LLL_LI_i fiT IlL III TEE LLL ILL 4_il
-LI-iIll Ill ID
)
I-HiHI# +4 H1-I--I 4+4- I-I-H-I-I-I #4+ I-I-HII-I 4414 I-I-Hl--4-4 #4 I-I-I-IIi -144 4-I-I-Hi-I 444 tI-I- -HI-I -144 i-Iii-i-i tt i-iii t hi-ni_ni tt hi-i-Ii-i -tjtt i-i-i-_I_i-i -I-t hi-i-I_II 1t i-i-i-iI_I 1It ti-i- -HIHi-It nrru-iu TV © n-I-i-I T i- FFri--i--l ITT rnnlui -ITT mrrrn FFFFF -I-IT i-FFi-ri -I-IT 7FF rri i-I-I CCI:]]] ii N C]]] EEC:]] nr Err::] r CCC:ri] : CCC:CI] ]lI ECCCCI ]]: ICC CC 2 I_I- i_l_L i_CL LI_I- Li i_CL C i_i_I +/-l_L © L i_Ll4 LI_IL I_I .I-L 1_LI i_I I_CL I i_L l_L_L l_I-L 1_CL I_J_L I_I- - C I-I-I-Ill IL I-Il ILL LI-I-Ill ILL LI-I-_Ill 411 LI-I-_Ill II I-LI-_I-Il 141 LLI-_LI_i 111 ILL 4_i_I_Ill I-I-iI-I--I 44
© I-- 4 444 I-I-iil-I 444 LLIiij 444 I-LI-II-I 444 LI-I-IIi 444 Li_I- -ill-i 444 4-I-I- 11444 I-Hi---HI4 ni-ii--n 4+
tti-
-i-n H 1 i--u
#44-7Th I-i-Hh-h-I mnrui
#44 TT I-I-HIHI 1-i 1
mnnI
-Itt lTT i-I-I-II-I i-rnii-i
-Itt
-ITT I-i-I-Hii mu-i-rn
-144 iut I-I-i- -HHi i-mnnri IIt fiT ti-I- -HIIfi4 li-n -rn fiT 7
nrrmii TTi- -F nnFl 7Th mmmii ITT mmrmi -ITT mmrii-l -ITT i-mrri-I -I-IT i-rrrri -I-IT Ti-F -rn u-u iii hI Ii II iii iii iii iii ill III III Iii iii ill ii ii iii i i iii Iii iii iii iii iii i_I_I I_I_I I I C i_CL LI_I I_I- I_LI i_L_L i_i_L i_L_L i_CL 4_CC 4_I_I Ll_L I_I-I L J I_L 1_LI 1_l_L 1_i_L 1_l_L 1_CL LIII I_IL - I-I-i_Ill IL -LI-I-Ill IlL LI-I-Ill 4IL I-LI-Ill IlL I-LI-_Ill 114 I-LI-_I-il .441 i_I-I-_I-Il 111 LI-I- -I-Il 111 I-iIi-4# + I- -I-I-II-i-I 4+4- I-I-II-44 444- iiI4 1 I-I- 44+ I-I-I-I-I-I 444 I-I-I-h-i -444 I-I-I-HI-I -L-4# 4-I-I- -HI-I 14 bi-II ti- -hi-Hi-i-i ttt hi-H-Ii-i ttt i- i-II-I Itt hi-I-I-I-I It i-i-hHIi 1t i-i-i-Hi-I -I-It ti-i- i-it mrrlfi TTi- mrr-rli ITT mrrnnl ITT mrni -ITT rrnrml -ITT i-mmri-I ill 7FFrn nlT 7FF -rni-h mr-li TTF mmui TTT FFF1 117 cnnu -ITT rrnrn fiT i-nnil u1 I rmrrIi nii 7FF i-ri -n-ri I-I-I- I I ILL LI-I-Ill ILL LLI-Ill ILL LLI-Ill ILL LI-C_Ill Ill LLL_I-il III LLL_LIl ill LLL I-I-i_Ill 4_CL 1_l_L I_CL i_CL i_CL i_CL i_CL CLW ICL 4_CL Il_L LCL 4_Li. I 4 II I I I-I-I CI-I I-I-I I_LI I-I-I l_LL - o N 0 00 i_C N 0 00 i_C N 0 00 C tt N 0 00 C tt N 0 N Tr - en en en en en N N N N N , I I I I uoisiii .zad a/wad çj (aftuad) 2-LI 0 U
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 1 entered Mode 3 for a refueling outage at 1230 on April 8. It is now 0030 on April 15. The last refueling outage was completed more than six months ago. PCS computer point T0615A indicates component cooling temperature has exceeded the maximum allowable CC temperature for core off-load. CC temperature is 88°F. Fuel movement has been suspended. 110 fuel assemblies remain in the core. An operator has been sent to the Aux Building basement to increase SW flow to the CC heat exchangers. INITIATING CUE You are requested to perform Attachment 13 of 1-OP-4.1 to determine the new maximum allowable CC temperature, and to determine if core off-load may recommence. Record the answers below. New Maximum Allowable CC Temperature May core off-load recommence? Once you have determined the new maximum allowable CC temperature, another operator will initiate a 1-LOG-14 to check CC temperature on PCS. ADMINJPM 1bALL Page: 1 of7 NAPS 2014 NRC EXAM
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine the new maximum allowable CC temperature for core off-load. Determine if core off-load may recommence. TASK STANDARDS Given a copy of 1-OP-4.1, Attachment 13, determine the new maximum allowable CC temperature and determine if core off-load may recommence. KIA
REFERENCE:
G2.1.42 (2.5/3.4) ALTERNATE PATH: N/A TASK COMPLETION TIMES Validation Time = 10 minutes Start Time = Actual Time minutes Stop Time = PERFORMANCE EVALUATION Rating { ] SATISFACTORY [1 UNSATISFACTORY Candidate (Print) Evaluator (Print) Evaluators Signature / Date EVALUATORS COMMENTS ADMIN JPM lb ALL Page: 2 of 7 NAPS 2014 NRC EXAM
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. 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. Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 Unit 1 entered Mode 3 for a refueling outage at 1230 on April 8. It is now 0030 on April 15. The last refueling outage was completed more than six months ago. PCS computer point T0615A indicates component cooling temperature has exceeded the maximum allowable CC temperature for core off-load. CC temperature is 88° F. Fuel movement has been suspended. 110 fuel assemblies remain in the core. An operator has been sent to the Aux Building basement to increase SW flow to the CC heat exchangers. ADMIN JPM lb ALL Page: 3 of 7 NAPS 2014 NRC EXAM
INITIATING CUE You are requested to perform Attachment 13 of 1-OP-4.1 to determine the new maximum allowable CC temperature, and to determine if core off-load may recommence. Record the answers below. New Maximum Allowable CC Temperature May core off-load recommence? Once you have determined the new maximum allowable CC temperature, another operator will initiate a 1-LOG-14 to check CC temperature on PCS. EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s)) Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s)) TOOLS AND EQUIPMENT Copy of 1-OP-4.1 orjustAttachments 11, 12, and 13 Calculator PERFORMANCE STEPS START TIME ADMINJPM 1bALL Page:4of7 NAPS 2014 NRC EXAM
1 Immediately initiate actions to reduce CC temperature to within Procedure Step 1 limit. ISAT[1 UNSAT[] Standards Initials step (Initial Condition states that an operator is adjusting SW flow to the CC heat exchangers). Notes/Corn ments: 2 I Complete calculation to determine decay time. I Procedure Step 2 I Critical Step SAT[] UNSAT[J Standards Enters 1 10 (# of assemblies in reactor). Divides 110 by 7.8 Adds 156 (Tcurrent) Subtracts 20 Determines decay time (Tcalc) is 150 hours. Notes/Comments ADMINJPM 1bALL Page: 5of7 NAPS 2014 NRC EXAM
3 Determine the new maximum CC temperature by plotting the Procedure Step 3 Decay Time calculated above on the applicable attachment. CriticaiStep SAT[] UNSAT[] Standards Determines Attachment 12 (Non-Back-to-Back) is applicable because it has been greater than 120 days since the previous outage. Using Attachment 12, marks 150 hours on the X-axis, then moves up to intersect the curve, then moves left to find the new maximum allowable CC temperature of 86.5°F on the Y-axis. Notes/Comments 4 If CC temperature is less than or equal to the new maximum CC Procedure Step 4 temperature, then core off-load may recommence. CriticaiStep SAT[] UNSAT[] Standards Compares actual CC temperature (88°F) to the new maximum allowable CC temperature (86.5°F). Determines core off-load may not recommence. Notes/Comments ADMINJPM 1bALL Page: 6of7 NAPS 2014 NRC EXAM
5 I Initiate a 1-LOG-14 to check CC temperature. I Procedure Step 5 ISAT[] UNSAT[] I I Standards I Initials step (Initiating Cue). Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME ADMIN JPM lb ALL Page: 7 of 7 NAPS 2014 NRC EXAM
DOMINION 1-OP-4.1 North Anna Power Station Revision 75 Page 173 of 183 (Page 1 of 1) Attachment 11 Back-To-Back Refueling CC Supply Temperature vs Decay Time 90 89 88 LL a 87 0 86 (3 0 a 85 E 84 C) C-) ci> 83
-o (3
82 0 81 E D E 80 x (3 79 78 77 76 75 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 Time Between Shutdown and Start of Offload (Hours) Graphks No: MT1 934 MAXIMUM CC SUPPLY TEMPERATURE VS. DECAY TIME BACK-TO-BACK OFFLOAD (1 PUMP, 2 COOLER) NOTE: Back-to-Back outage is defined as an outage that has occurred at less than or equal to 120 days since the previous outage unit became subcritical.
DOMINION 1-OP-4.1 North Anna Power Station Revision 75 Page 174 of 183 (Page 1 of 1) Attachment 12 Non Back-To-Back Refueling CC Supply Temperature vs Decay Time 95 94 93 LL 0 92 ci) L 91 ci)
- 0. 90 E
89 C) () ci) 88
-o cci 87 0
86 E E 85 x cci 84 83 82 81 80 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 Time Between Shutdown and Start of Offload (Hours) Graphics No: MT1 933 MAXIMUM CC SUPPLY TEMPERATURE VS. DECAY TIME NON-BACK-TO-BACK OFFLOAD (1 PUMP, 2 COOLER) NOTE: Non Back-to-Back outage is defined as an outage that has occurred at greater than 120 days since the previous outage unit became subcritical.
DOMINION 1-OP-4.1 North Anna Power Station Revision 75 Page 175 of 183 (Page 1 of 2) Attachment 13 Determine New Maximum CC Temperature vs Decay Time
- 1. Immediately initiate actions to reduce CC temperature to within limit.
- 2. Immediately complete the following calculation to determine the Decay Time to be used to find the new maximum CC temperature for the current time since entry into Mode 3:
F # of assemblies in reactor 7 Tcalc
= L 7.8 assemblies per hour + Tcurrent
] - 20 Tcalc = Time to be used on the appropriate attachment (Attachment 11 or Attachment 12) to determine the new maximum CC temperature Tcjrren Time since entry into Mode 3.
Tcurrent = (time since entry into Mode 3) (Line 1) Assemblies (number of assemblies in reactor vessel) (Line 2) Line 2 divided by 7.8 = (Line 3) Line 3 + Line 1 = (Line 4) Line 4 20
- = (Line 5)
Line 5 is the Decay Time to read on the appropriate attachment (Attachment 11 or Attachment 12)
- 3. Determine the new maximum CC temperature by plotting the Decay Time calculated above on the applicable attachment listed below:
- Attachment 11, Back-To-Back Refueling CC Supply Temperature vs Decay Time
- Attachment 12, Non Back-To-Back Refueling CC Supply Temperature vs Decay Time
DOMINION 1-OP-4.1 North Anna Power Station Revision 75 Page 176 of 183 (Page 2 of 2) Attachment 13 Determine New Maximum CC Temperature vs Decay Time
- 4. IF the CC supply temperature, as indicated by Unit 1 PCS Computer Point T0615A, is less than or equal to the new maximum CC temperature, THEN core offload may recommence.
- 5. Initiate a 1-LOG-14 to check CC temperature, as monitored by Unit 1 PCS Computer Point T0615A, is less than or equal to the new maximum CC temperature in accordance with TRM TSR 3.9.7.1. Step 4.57 provides actions to be taken in the event CC temperature increases above the new maximum CC temperature.
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS 1-PT-14.1, Charging Pump 1-CH-P-1A Periodic Test, is in progress. Local charging pump data has been entered on Attachment 1, 1-CH-P-1A Data Sheet. INITIATING CUE You are requested to complete the calculations in Attachment 1 of 1-PT-14.1 and to plot pump flowrate and differential pressure on the pump curve in Attachment 4. ADMIN JPM 2 ALL Page: 1 of 6 NAPS 2014 NRC EXAM
_______ ______ Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Complete calculations and plot pump flowrate vs. differential pressure. TASK STANDARDS Attachment 1 calculations completed accurately. Pump flowrate vs. differential pressure plotted accurately on Attachment 4 to determine operation is in the acceptable range. K!A
REFERENCE:
G2.2.1 (4.5/4.4) ALTERNATE PATH: N/A TASK COMPLETION TIMES Validation Time = 10 minutes Start Time = Actual Time = minutes Stop Time = PERFORMANCE EVALUATION Rating [ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print) Evaluator (Print) Evaluators Signature / Date EVALUATORS COMMENTS ADMIN JPM 2 ALL Page: 2 of 6 NAPS 2014 NRC EXAM
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. 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. Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 1-PT-14.1, Charging Pump 1-CH-P-1A Periodic Test, is in progress. Local charging pump data has been entered on Attachment 1, 1-CH-P-1A Data Sheet. INITIATING CUE You are requested to complete the calculations in Attachment 1 of 1-PT-14.1 and to plot pump flowrate and differential pressure on the pump curve in Attachment 4. ADMIN JPM 2 ALL Page: 3 of 6 NAPS 2014 NRC EXAM
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s)) Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s)) TOOLS AND EQUIPMENT 1-PT-14.1 Attachment 1 with values recorded for each parameter except the Actual GPM, Discharge Flow and Differential Pressure calculations. 1-PT-14.1 Attachment 4 PERFORMANCE STEPS START TIME ADMIN JPM 2 ALL Page: 4 of 6 NAPS 2014 NRC EXAM
I 1 Calculate Actual GPM (e). I Procedure Step j CriticaiStep SAT[] UNSAT[] Standards Performs the following calculation: Square root of [recirc flow DP (19.8) divided by 144.47] X 180 = 66.6 gpm Notes/Comments: I 2 I Calculate Discharge Flow. Procedure Step I Critical Step SAT[] UNSAT[] Standards Performs the following calculation: a+b+c+d+e-f-g-h = discharge flow 70 + 7.8 + 7.9 + 7.9 + 66.6 2.36 1.97 1.78 = 154.09 gpm Notes/Comments ADMIN JPM 2 ALL Page: 5 of 6 NAPS 2014 NRC EXAM
3 Calculate Differential Pressure. Procedure Step I CriticaiStep SAT[] UNSAT[J Standards Performs the following calculation: Differential Pressure = x y Differential Pressure = 2575 50 = 2525 psid Notes/Corn ments I 4 Plot purnp flowrate vs. differential pressure on Attachment 4. I Procedure Step Critical Step SAT[] UNSAT[] I Standards Plots 154 gpm (x-axis) and 2525 psid (y-axis). Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME ADMIN JPM 2 ALL Page: 6of6 NAPS 2014 NRC EXAM
DOMINION 1-PT-14.1 North Anna Power Station Revision 52 Page 61 of7O (Page 1 of 2) Attachment I Charging Pump I-CH-P-IA Pump Data Sheet Reference Measured Required Action Parameter Values* Value Acceptable Low High Static Inlet Pressure (l-CH-PI-103, l-CH-Pi-104, or 1-CH-PI-105) 44.95 psig E? psig 33.4 < 33.4 None Charging Flow (I-CR-Fl-I 122A) 72.0 gpm (a) 7o gpm None None None Seal Water Flow (l-CH-FI-1130A) 7.6gpm (b) gpm None None None Seal Water Flow (l-CH-FI-1127A) 7.6gpm (c) gpm None None None Seal Water Flow 77 (i-CR-Fl-i 124A) Recirc Flow Indication from zVP 7.6 gpm 20.86 (d) 9 gpm in. None None None None None None Cell in. H 0 7 / H 0 7 (X = Recirc flow AP)
/x x 180 = Actual GP J 144.47 68.4 gpm Combined CHG Recirc Flow (e) None None None gpm 1-CH-FE-i 161 Seal Return 1-CH-FR-1 154A 2.85 gpm (f) None None None RCP 1A (Red Pen) gpm Seal Return 1-CR-FR-i 154A 2.55 gpm (g) None None None RCP lB (Green Pen) ( 97 gpm Seal Return 1-CR-FR-i 154A 2.16 gpm (h) None None None RCP iC (Blue Pen) 7 gpm i55.64gpm gpm >120 120 None (a+/-b+/-c+/-ci+/-e-f-g-h)
Discharge Pressure (i-CH-P1-I 151) 2550 psig (x) .7spsig None None None Dynamic Inlet Pressure (i-CH-PI-103) 40.34 psig (y) psig 33.4 < 33.4 None
- Reference values and Acceptance criteria in accordance with 1ST CaIc Basis (Reference 2.3.15)
DOMINION 1-PT-14.1 North Anna Power Station Revision 52 Page 62 of 70 (Page 2 of 2) Attachment I Charging Pump 1-CH-P-IA Pump Data Sheet Reference Measured Required Action Parameter Values* Value Acceptable Low High Differential 2509 66 Pressure x -y Attachment 4 Attachment 4 Attachment 4 psid psid Lube Oil Pressure (1-CH-PI-IO1A) 11.6 psig /O. psig 9.5 -12.0 None None Motor Current 63.0 amps amps None None None
- Reference values and Acceptance criteria in accordance with 1ST Calc Basis (Reference 2.3.15)
DOMINION 1-PT-i 4.1 North Anna Power Station Revision 52 Page 65 of 70 (Page 1 of 1) Attachment 4 1-CH-P-IA Quarterly Test Pump Curves 3000-2900-Required Action Range AcceptabIangtabIe Range 2300 Required Action Range ME-0417 Test Limit Pump Curve 2200-150 200 250 300 1-CH-P-1A Flowrate (GPM) Graphics No: PC2373 1-CH-P--IA QUARTERLY TEST PUMP CURVES
Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 1 is in mode 1. 1-CH-217, PG Supply to Boric Acid Blender Isolation Valve, diaphragm must be replaced. INITIATING CUE You are requested to review the 1-CH-217 tagging record package for accuracy and completeness using the Tag Out Preparation and Review Check List. A component configuration is NOT required by the tagout. Circle the results of your review, If not approved, record the reason below. Approved Not Approved ADMIN JPM 2 SRO Page: 1 of 11 NAPS 2014 NRC EXAM
_______ _______ Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM RXXX TASK Review a tagging record for accuracy and completeness. TASK STANDARDS Tagging record review identifies inadequate boundary because 1-GN-109 is not included as a boundary isolation valve. KIA
REFERENCE:
G2.2.13 (4.1 /4.3) ALTERNATE PATH: N/A TASK COMPLETION TIMES Validation Time = 30 minutes Start Time = Actual Time = minutes Stop Time = PERFORMANCE EVALUATION Rating [ ]SATISFACTORY [ ]UNSATISFACTORY Candidate (Print) Evaluator (Print) Evaluators Signature / Date EVALUATORS COMMENTS ADMIN JPM 2 SRO Page: 2 of 11 NAPS 2014 NRC EXAM
Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation) OPERATOR PROGRAM RXXX READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. 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. Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 Unit 1 is in model. l-CH-217, PG Supply to Boric Acid Blender Isolation Valve, diaphragm must be replaced. INITIATING CUE You are requested to review the l-CH-217 tagging record package for accuracy and completeness using the Tag Out Preparation and Review Check List. A component configuration is NOT required by the tagout. Circle the results of your review. If not approved, record the reason below. Approved Not Approved ADMIN JPM 2 SRO Page: 3 of 11 NAPS 2014 NRC EXAM
EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s)) Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s)) TOOLS AND EQUIPMENT Tagging record package for 1-CH-217 which includes:
- Tagout Preparation and Review Checklist
- Tagout covers heet
- OP-AP-300, Attachment 7, Reactivity Management Screening
- Tagout Request
- Valve Lineup sheets
- 1171 5-FM-095B, sheet I
- 11715FK-O95B, sheet 1
- 1171 5-FM-086D, sheet I ADMIN JPM 2 SRO Page: 4 of 11 NAPS 2014 NRC EXAM
PERFORMANCE STEPS START TIME I1 I Work scope defined and understood . Procedure Step ISPT[] UNSAT[} Standards Checks JPM initial conditions to define work scope (replace diaphragm) Notes/Comments I2 I Boundaries established for tasks and hazards .. NO I Procedure Step Critical Step SAT[] UNSAT[j Standards Reviews tagging record and reference material. Determines 1-PG-i 18 was excluded as a boundary isolation valve (1171 5-FM-086D, sheet 1) Notes/Comments ADMIN JPM 2 SRO Page: 5 of ii NAPS 2014 NRC EXAM
I3 I Review for heat trace, IA, seal water, seal cooling fuses ... Procedure Step I I SAT[] UNSAT[] Standards Reviews tagging record and reference material to determine no heat trace, IA, seal water, seal cooling, fuses Notes/Comments [ I If a component configuration is required by the tagout ... Procedure Step SAT[] UNSAT[] Standards Notes initiating cue that component configuration is not required and previously NAd step on the check list. Notes/Comments ADMIN JPM 2 SRO Page: 6 of 11 NAPS 2014 NRC EXAM
_____ 5 Applicable procedures and controlled documents are used to create Procedure Step tagout. If using non-priority drawings SAT[] UNSAT[] Standards Determines applicable procedures and controlled documents were used. Determines non-priority drawings were not used. Notes/Corn m ents 6 Tagout is sequenced as directed by controlling procedure, or per Procedure Step 0 P-AA-2 00. Critical Step SAT[] UNSAT[] I Standards I Reviews tagout and determines sequence is correct. Notes/Comments ADMIN JPM 2 SRD Page: 7 of 11 NAPS 2014 NRC EXAM
I7 I Return To positions reflect OP-lA, controlling procedure ... Procedure Step CriticaiStep SAT[] UNSAT[] Standards Reviews tagout and valve lineup sheets and determines return to positions are correct. Notes/Comments 8 Consider effects on alarms, indications, instrumentation, and Procedure Step controls. SAT[] UNSAT[] Standards Reviews tagout and determines no effects on alarms, indications, instrumentation, or controls. Notes/Comments ADMIN JPM 2 SRO Page: 8 of 11 NAPS 2014 NRC EXAM
9 Compliance with TS & TRM (maintain redundant equipment Procedure Step operable). ISAT[1 UNSAT[] Standards I Determines tagout is in compliance with TS and TRM. Notes/Comments I 10 I Reference documents and special notes ... are on cover sheet. Procedure Step I I SAT[] UNSAT[] Standards Reviews tagout to confirm reference documents and special notes are on cover sheet. Notes/Comments ADMIN JPM 2 SRO Page: 9 of 11 NAPS 2014 NRC EXAM
I11 I Tagout Request reviewed as applicable. I Procedure Step I SAT[] UNSAT[] I Standards I Reviews tagout request. Notes/Comments 12 I Consider the effects on reactivity management. I Procedure Step SAT[] UNSAT[]J Standards Reviews Reactivity Screening attachment. Reviews notes 1 2 and 4 on the tagout coversheet. Notes/Comments ADMIN JPM 2 SRO Page: 10 of 11 NAPS 2014 NRC EXAM
13 Pre-maintenance and post-maintenance requirements are Procedure Step understood. SAT[] UNSAT[] Standards Reviews tagging record package for pre-maintenance and post-maintenance requirements. Notes/Corn ments I 14 I Comments or problems found. I Procedure Step Critical Step SAT[] UNSAT[] Standards Notes failure to include 1-PG-118 as a boundary isolation. Circles not-approved on the JPM cover sheet. Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME ADMIN JPM 2 SRO Page: 11 of 11 NAPS 2014 NRC EXAM
________ __________ North Anna Operations Tag-Out Preparation and Review Check List Dominion- Tagging is a Safety Process, Tagging is NOT a production process. TagoutNumber _ 4 q-, °O/ Prep Review SRO1 SRO2 Personnel, Equipment and Administrative Review Items [j [] j Work scope defined and understood using the following, as applicable: work order, P3E, Craft, Planner and Work Week Coordinator. [I [ [ [ Boundaries established for task and hazards, all energy sources removed or noted on the tagout. Initiate WM-M-3O1, Operational Risk Assessment, for all tagouts containing non standard isolation boundaries or no available vent/drain path. [/1 [ I [ I [ I Review for heat trace, IA, seal water, seal cooling, fuses, patch cords, motor/MOV heaters, hidden power supplies.
,M4 [I [ 1 [1 IF a component configuration is required by the tagout, its NOT controlled by an MOP, and it is a component/condition controlled by Operations THEN use a Plant Requirement tag to ensure the required status.
.V1 [ I [ I [ I Applicable procedures and controlled documents are used to create tagout. If using Non-Priority Drawings then verify either no pending changes or the changes are reviewed and noted. If not, refer to OP-AA-200.
,,f [] []
Tagout is sequenced as directed by controlling procedure, or per OP-AA-200. [I [I [1 Return To positions reflect OP-lA, Controlling Procedure, or Equipment Status positions. At a minimum, Return To position conflicts are to be noted on tagout. Consider effects on alarms, indications, instrumentation, and controls. [I [I Compliance with TS & TRM (Maintain Redundant Equipment Operable). I [I References documents and special notes, as required by OP-AA-200, are on cover sheet. [[I [1 [1 Tagout Request reviewed as applicable. V [1 [I [1 Consider the effects on Reactivity Management. If affected, then note on the tagout. OP AP-300 Attachment 7 can be referenced to aid in determination. [I I Pre-maintenance and Post-maintenance requirements are understood. Walkdown to evaluate the following: tagout covers the work scope, labeling, components in overhead, work area hazards, work requests on components to be manipulated, return to positions match as found position, potential for trapped water in boundary, alternate lockout device required, potential Status Control bump hazards and inform lead craft of Preparer: Ct-L) Walkdown: Review: SRO: SRO: initials Initials initials initials initials Comments or Problems Found:
*lf modifications are required, evaluate affects to all associated tagouts.
The check list is to be used as a post tagout development self-check tool and is not an official document of Revision 10 Last updated 11-26-13 record. The checklist may be discarded after completion of the review process.
Tait Coversheet Dominion 7gfut: ONLINE North Anna Power Station ragout: 1-14-cH -0001 04/24/2014 13:30:11 Component to be Worked: 1-CH - -217 PG Supply To Boric Acid Blender Isolation Valve AB 274 BLENDER AREA NOTES FOR TRAINING USE ONLY
***Effects Reactivity. Refer to OP-AP-300 Att. 7***
- 1) This tagout removes the ability to supply PG to Unit 1. Ensure no makeups or dilutions are required before hanging this tagout.
- 2) 1-CH-220 IS LOCKED/CLOSED to comply with T.S. 3.1.8 in the event of a Unit Trip. If Unit 1 trips while this tagout is hanging, 1-CH-241, 1-CH-FCV-1114B, and 1-CH-FCV-1113B will also need to be secured in the Closed position with in 15 minutes, unless a boration is in progress,IAW T.S. 3.1.8 basis. Ensure Unit 1 OATC and Aux Bldg watchstander are briefed on this requirement before hanging tagout.
- 3) Ensure craft is ready to work prior to tagging.
- 4) Return to position for 1-CH-217 is with Unit 1 in Modes 1 or 2. If Unit 1 enters modes 3, 4, 5, or 6, then change the return to position of 1-CH-217 to LOCKED CLOSED.
REASON Replace diaphragm for 1-CH-217 due to leak. INSTRUCTIONS I HAZARDS CAUTION CRAFT: EXPECT WATER (PG). ADDITIONAL INFORMATION REF: 11715-FM-005B(1), FM-086D(1), FK-095B(1), O-OP-9A, 1-OP-8.1A Tagout Attributes: Attribute Description Attribute Value Section holder SHIFT MANAGER POD Work Week N/A POD Schedule Emergent rag On Request No Work Order List: 4umber I Equipment I[ Description 59102158672 Replace diaphragm due to leakage 12 1-CH - -217 Tagout Verification: Status Description Name Verification Date Prepared Prepared ESOMS CR0 TEST USER 04/24/2014 11:29:42 Walkdown Walkdown 1 SRO Review 1 SRO Review OP-AA -200 1/2
Tajut Coversheet Dominion Tagout: ONLINE North Anna Power Station ragout: 1-14-CH -0001 04/24/2014 13:30:11 Status Description Name Verification Date 2 SRO Review 2 SRO Review pproved to Hang Jproved to Hang Tags Verified Hung Tags Verified Hung Restoration SRO review Restoration Changed pproved to Remove Approved to Remove Tags Verified Removed Tags Verified Removed OP-AA -200 2/2
___ ______ __________ ragout Tag List Dominion ragout: ONLINE North Anna Power Station ragout: 1-14-CH -0001 04/24/2014 13:30:12 Tag Type Equipment Ver Pla Placement Place. 1st Verif Place. 2nd Verif Ver Rest Rest. Config Rest. 1st Verif Rest. 2nd Verif Seq Configuration Req Seq *As Left (If Duff.)
- Equipment Description Date/Time Date/Time Date/Time Date/Time Serial No.
- Equipment Location *
- Notes Notes Mech. 1-CH - -220 iv LOCKED CLOSED T IV 5 CLOSED Danger
- PG Supply To Chem Mixing Tk And Manual Dilute Isol
- BLENDER AREA Mech. 1-CH - -218 IV 1 CLOSED IV 4 OPEN Danger
- PG Supply To Boric Acid Blender Isolation Valve
- AUX BLDG 274 BLENDER AREA Mech. 1-CH - -216 IV 2 OPEN IV 3 OPEN Danger
- PG To Boric Acid Blender 1-CH-PC-1114 Isol Valve
- BLENDER AREA Mech. 1-CH -ICV -3212 IV 3 OPEN IV 1 CLOSED Danger
- 1-CH-PC-1114 INLET LINE VENT VALVE
- AB 274 AT UNIT 1 BLENDEF Maintena 1-CH - -217 IV IV 2 OPEN item
- PG Supply To Boric Acid Blender Isolation Valve
- AB 274 BLENDER AREA OP-AA -200
DOMINION OP-AP-300 REVISION 17 PAGE 43 OF 43 ATTACHMENT 7 (Page 1 ofi) Reactivity Management Screening Does the activity:
- 1. Affect nuclear fuel? Yes No
- 2. Affect CRD mechanisms or position indication? Yes No
- 3. Change input instrumentation or software providing heat balance calculations, core thermal calculations, or core power distribution calculations? Yes No
- 4. Affect reactivity calculations such as shutdown margin or ECP? Yes No
- 5. Affect incore or excore nuclear instrumentation? Yes No
- 6. Place Rods in Manual? Yes No
- 7. Trip Reactor Protection components? (SSPS, RPS, ElF, AMSAC) Yes No
- 8. Affect boration/dilution system? No
- 9. Affect main steam or feedwater flow or indication? Yes No
- 10. Change T hot or T cold indications? Yes No
- 11. Affect TAVG control circuits? Yes No
- 12. Affect EH controls? Yes No
- 13. Affect blowdown flows or indications? Yes No
- 14. Affect Steam Dump operation? Yes No
- 15. Place RCS pressure or controls to Manual? Yes No
- 16. Affect feedwater pre-heating systems (SD, ES)? Yes No If any answer is Yes, then notify the Shift Manager and STA. A formal pre-job brief shall be conducted with the control room team and all individuals involved in the activity. Consideration should be given to establishing additional controls, oversight and monitoring to preclude a reactivity event.
INFORMATION USE
DOMINION OP-AA-200 REVISION 19 PAGE 60 OF 70 Tag-Out Request Demnon OP-AA-200 AttachmentS
- Page 1 of 1 Issued To (Name) Extension Department Tag-Out Requested On Unit: Li D 2 3 D Common Reason For Tag-Out Initiating Document Work Order Number .g 02 ( -3 ? 7 2 iCorrective Maintenance D Preventive Maintenance Dewgn Change Package Number D Trouble Shooting Other D Testing D Engineering Work Package D Other Equipment Affected
(-i Work To Be Done fIcc pv1Jfr1 4 J d 1 Assist in Defining Work Scope and establishing safe work boundaries, review the following and check all that apply: NO ROTATION Tags (Equipment de-energized and prevented from E Heat Trace (consider if removing insulation) turning; Non-intrusive maintenance.) Purge Path Required (Describe Below) D NO FLOW Tags (System isolated to allow equipment to be manipulated without affecting the plant. Non-intrusive maintenance.) System in-service for Freon removal FULL TAGOUT Tags (Equipment isolated from all energy sources E Steam removed from air handler and depressurized. Intrusive maintenance.) Hazardous Chemicals involved D ELECTRICAL ONLY (Equipment electrically isolated, the craft will Control Power fuses removal required use LOCKOUT, if required, for all other energy sources.) D Controlling Procedure, which defines energy sources (OP, Grounds required MOP, PT, ICP, MCM, etc. List in remarks.) Motor Heater fuses D Personnel entering a piping system or plant equipment (List in remarks.) (Operations will assist in determining applicable OPS procedures.) fl MOV motor/grease heater fuse D Auxiliary Components associated with equipment: MOV internal power supplies on LS/Rotor Contacts D Seal Water D PMT requires Danger Tags (MOV testing, Flow Scan) D Oil sub-system Li Cooling Water (i.e., BC, SW, CD, CC) Tag-Out Request Submitted By (Name) I Date Time Tag-Out Request Verified By (Name) Date Time Recommended Isolations or Remarks (If possible, include tag type and position.) orm No. 721716(Aug 20111
DOMINION-NORTH ANNA PWR ST
-
5/8/2013 15:55:11 Type: VLU, Unit: 1, Procedure: 1-OP-8.1A, Revision: 36 Part 52 of 88 2 / 4 Step: 521 LETDOWN - BLENDER AREA (RT TO LFT) ==> BLENDER AREA (RIGHT TO LEFT) Equipment: Description/Instruction: Location: Required Conflg: Actual Config: Verif: Initials 1-CH - -223 Chemical Mixing Tank PG Supply BLENDER AREA OPEN IV Header Isol Valve Instruction: Group: 0 Required: Notes: Prints: 1-CH - -221 Charging Pumps Manual Dilute AB 274 BLENDER AREA CLOSED IV isolation Valve Instruction: Group: 0 Required: Notes: Prints: 1-CH - -220 PG Supply To Chem Mixing Tk And BLENDER AREA CLOSED IV Manual Dilute Isol Instruction: Group: 0 Required: Notes: Prints: 1-CH - -218 PG Supply To Boric Acid Blender AUX BLDG 274 BLENDER OPEN IV Isolation Valve AREA Instruction: Group: 0 Required: Notes: Prints: l-CH - -236 Blender Discharge To Dilute VCT CUBE/REACH ROD IN OPEN IV Header (Reach Rod) BLENDER AREA Instruction: Group: 0 Required: Notes: Prints: 1-CH - -186 Reactor Coolant Filter To Vct Inlet AUX BLDG 274 U-i OPEN IV Hdr Isol Valve (Chain Operated BLENDER AREA I I Reach Rod) Group: 0 Required: Instruction: Notes: Prints: 1-CH - -191 Vct To Stripper Vent Cond AB 274 BLENDER AREA OPEN IV Isolation Valve (Reach Rod) (REACHROD) Instruction: Group: 0 Required: Notes: Prints: 1-CH - -230 Boric Acid Blender To Rwst And AB Unit 1 Blender Area CLOSED IV Fuel Pit Isol Vv Instruction: Group: 0 Required: Notes: Prints: Page 63 of 113 CONTINUOUS USE
DOMINION-NOR THANNA PWR ST
-
2/26/2014 15:26:45 Type: VLU, Unit: 0, Procedure: 0-OP-9A, Revision: 17 Part 30 of 62 1 / 1 Step: 5.10 PG HEADER SOUTH OF CATALYTIC RECOM > PG HEADER SOUTH OF CATALYTIC RECOMBINER CUBICLE Equipment: Description/Instruction: Location: Required Contig: Actual Config: Verif: Initials 1-PG - -104 Gas Waste Recombiner Flushwater Aux Bldg elev.256 CLOSED IV Sply Isol Vv (10 feet overhead outside Recombiner Cube) Group: 0 Required: Instruction: Notes: Prints: 1-PG - -106 PG Supply to Recombiner 259 East Outside CLOSED IV Constant Temperature Bath (10 Recombiner Cube feet overhead outside Recombiner Cube) Group: 0 Required: Instruction: Notes: Prints: 1-PG - -118 Boric Acid Blender Flushwater AB 259 ;12 NORTH OPEN IV Supply Isol Valve (10 feet i-HC-H2A-i01 OVHD overhead outside Recombiner Cube) Group: 0 Required: Instruction: Notes: Prints: 1-PG - -210 Boric Acid Blender Flush Water AB 259 IN OVHD ABOVE OPEN IV Supply Isol Valve (above 1-IA-C-i) u-i AIR COMP. Instruction: Group: 0 Required: Notes: Prints: 1-PG - -300 Primary Grade Water Hose Conn Aux Bldg 259 at 2-IA-C-i CLOSED IV Isol Valve Instruction: Group: 0 Required: Notes: Prints: 1-PG - -143 Primary Grade Water Branch IN AUX. BLDG. OPEN IV Header Iso! Valve (West of L_ 2-IA-C-i) Group: 0 Required: Instruction: Notes: Prints: i-PG - -323 Primary Grade Water Supply West wall of 2-IA-C-i OPEN IV Header iso! Valve (West wall of 2-IA-C-i) Group: 0 Required: Instruction: Notes: Prints: Page 49 of 97 CONTINUOUS USE
DOMINION-NORTH ANNA PWR ST 5/8/2013 15:55:11 Type: VLU, Unit: 1, Procedure: 1-OP-&1A, Revision: 36 Part52ofB8- 1/4 Step: 521 LETDOWN - BLENDER AREA (RT TO LFT) => BLENDER AREA (RIGHT TO LEFT) Equipment: Description/Instruction: Location: Required Config: Actual Config: Verif: Initials 1-CH - -225 Chemical Mixing Tank Vent Valve BLENDER AREA CLOSED IV Instruction: Notes: Group: 0 Required: Prints: 1-CH - -226 Chemical Mbdng Tank Funnel u-i BLENDER AREA CLOSED IV Instruction: Group: 0 Required: Notes: Prints: 1-CH - -227 Chemical Mixing Tank Drain Valve BLENDER AREA CLOSED IV Instruction: Notes: Group 0 Required: Prints: 1-CH - -216 PG To Boric Acid Blender BLENDER AREA OPEN IV
-
1-CH-PC-1114 Isol Valve Instruction: Group: 0 Required: Notes: Prints: 1-CH - -217 PG Supply To Boric Acid Blender AB 274 BLENDER AREA OPEN IV Isolation Valve 1 Instruction: Modes 1 and 2 Group: 0 Required: Notes: 4 Prints:
-
1-CH - -217 PG Supply To Boric Acid Blender AB 274 BLENDER AREA LOCKED CLOSED IV Isolation Valve Instruction: Modes 3, 4, 5, and 6 Group: 0 Required: Notes: 4 Prints: 1-CH - -228 Chemical Mixing Tank Outlet AB 274 BLENDER AREA CLOSED IV Isolation Valve T Instruction: Group: 0 Required: Notes: Prints: 1-CH - -224 Chemical Mixing Tank PG Supply BLENDER AREA CLOSED IV Header Isol Valve Instruction: Group: 0 Required: Notes: Prints: Page 62 of 113 CONTINUOUS USE
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS An HP technician has reported possible damage on 1-CH-TCV-100 (letdown header bypass to VCT temperature control valve) in the Unit 1 non-regen heat exchanger cube. INITIATING CUE You are directed to perform the following as the operator who will inspect 1-CH-TCV-1 00. Record your answers below.
- Select the appropriate RWP task number.
- Determine the required protective clothing for the job.
- Determine the required dosimetry for the job.
- Determine the dose alarm setpoint AND the dose rate alarm setpoint.
- Determine the maximum stay time IN MINUTES based on reaching the dose alarm setpoint, assuming you avoid the areas surveyed for contact and 30 cm readings.
ADMIN JPM 3 ALL Page: 1 of 6 NAPS 2014 NRC EXAM
_______ Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine correct RWP task number, protective clothing, dosimetry, dose alarm setpoint, dose rate alarm setpoint, and maxim urn stay-time. TASK STANDARDS Correct RWP task, protective clothing, dosimetry, dose alarm and dose rate setpoints are identified from the RWP/Task. Correct maximum stay time is calculated based on the alarm setpoint. KIA
REFERENCE:
G2.3.7 (3.5/3.6) ALTERNATE PATH: N/A TASK COMPLETION TIMES Validation Time = 15 minutes Start Time = Actual Time = minutes Stop Time = PERFORMANCE EVALUATION Rating ]SATISFACTORY ]UNSATISFACTORY Candidate (Print) Evaluator (Print) Evaluators Signature I Date EVALUATORS COMMENTS ADMIN JPM 3 ALL Page: 2 of 6 NAPS 2014 NRC EXAM
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. 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. Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 An HP technician has reported possible damage on 1-CH-TCV-100 (letdown header bypass to VCT temperature control valve) in the Unit 1 non-regen heat exchanger cube. INITIATING CUE You are directed to perform the following as the operator who will inspect 1-CH-TCV-100. Record your answers below.
- Select the appropriate RWP task number.
- Determine the required protective clothing for the job.
- Determine the required dosimetry for the job.
- Determine the dose alarm setpoint AND the dose rate alarm setpoint.
- Determine the maximum stay time IN MINUTES based on reaching the dose alarm setpoint, assuming you avoid the areas surveyed for contact and 30 cm readings.
ADMIN JPM 3 ALL Page: 3 of 6 NAPS 2014 NRC EXAM
EVALUATION METHOD Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues) Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues) TOOLS AND EQUIPMENT RWP, Survey Map, Calculator PERFORMANCE STEPS START TIME 1 From the RWP provided, determine which task number is Procedure Step applicable for the job. Critical Step SAT[] UNSAT[] Standards Operator determines taski is the correct task. Notes/Comments: ADMIN JPM 3 ALL Page: 4 of 6 NAPS 2014 NRC EXAM
2 From the RWP provided, determine the protective clothing Procedure Step: requirements. Critical Step SAT[] UNSAT[] Standards Operator determines that the area is not contaminated; therefore, no protective clothing is required. Protective Clothing Requirements: None Notes/Comments: 3 From the RWP provided, determine the dosimetry required. Procedure Step: Critical Step SAT[] UNSAT[J Standards I Operator identifies that ED/SRD & TLD are required. Notes/Comments: ADMIN JPM 3 ALL Page: 5 of 6 NAPS 2014 NRC EXAM
4 From the RWP provided, determine the dose alarm setpoint and Procedure Step: dose rate alarm setpoint. Critical Step SAT [] UNSAT [] Standards Operator determines the dose alarm is 5 mRem and the dose rate alarm is 90 mRem/hr. Notes/Comments: 5 Determine the maximum stay time in minutes based on reaching Procedure Step: the RWP dose alarm setpoint. Critical Step SAT[] UNSAT[] Standards Operator uses RWP to determine dose alarm is set at 5 mRem. Operator uses survey map to determine highest general area dose rate is 35 mrem/hr. Operator performs the following calculation to determine stay stime in minutes: 5 mR divided by 35 mR/hr x 60 mm/hr 8.57 minutes Notes/Comments: END OF EVALUATION STOP TIME ADMIN JPM 3 ALL Page: 6 of 6 NAPS 2014 NRC EXAM
(erilied Current By Dali r- C ti/I Auxilllary Building, 244w Elevation Unit I Non Regen Cube Drain lines 5*J7 15*17 2050*/119 1-CH-TCV.400 /// PIPfl9 2000*/150 HRA VHRA = Very High Radiation Area HPA = Hot Particle Area CAM Continuous Air Monitor LHRA = Locked High Radiation Area CA = Contaminated Area SOP Step Off Pad HRA = High Radiation Area ARA Airborne Radioactivity Area LDWA = Low Dose Waiting Area RA Radiation Area RMA = Radioactive Material Area NEA = Neutron Exposure Area RCA Rado!oglcal Control Area -*** Radiological Boundary # N Neutron Dose Rate LL Contact and 30 cm Gamma Dose Rate Readings # f3 Corrected Beta Dose Rate
RADIATION WORK PERMIT
SUMMARY
14-1207 RP-AA-274 ATT. 2 PLANT CODE YEAR RWP NUMBER REV. RWP START TYPE CATEGORY RWP EXPIRATION 0 14 14-1207 0 01-JAN-2014 00:00 S RM 31-DEC-2014 23:59 RWP DESCRIPTION Routine Duties, walkdown, and valve line-ups by Operations personnel. TASK
SUMMARY
DOSE ALARM DOSE RATE ALARM TIME INTERVAL 1 Routine Duties, walkdown, and valve line-ups by Operations personnel. Access to Reactor 5 90 Containments allowed for containment closure team only 2 Perform change out of 1-DC-FL-2 (Radwaste Dewatering Filter). 10 90 3 BARS Operation, Sampling & 1-RP-FL-2 Change Out 5 90 ALARA INFORMATION ALARA Review No. Hours-Estimated Person-mrem 14-001 2099997 1580 SPECIAL INSTRUCTIONS: Requirements for High Radiation Area or Locked High Radiation Area Entry:
-Notify RP PRIOR to entry (Discuss work to be performed) -Signed in on an RWP that ALLOWS entry into the High Radiation Area or Locked High Radiation Area -Understand the ED Alarm set-points and your response to a dose or dose rate alarm -Understand the radological conditions (dose rates) in your work area -Monitor Electronic Dosimetry frequently (Approximately every 15 minutes) -Notify RP upon exit Prepared By Mark Stokes DATE: 05-OCT-2013 00:0( Approved By DATE:
Revised By DATE: Approved By DATE: Terminated By DATE: Approved By DATE: ORIGINAL Page 1
Task Number I OF3 RP-AA-274 ATT. 2 VALID FROM 01-JAN-2014 00:00 TO 31-DEC-2014 23:59 RWP 14-1207-1 0 REV. NO DOSE RATE ALARM: 90 mrem!Hr BUDGETED DOSE: 1533 mrem DOSE LIMIT ALARM: mrem ALARA EVALUATION NO: 14-001 JOB LOCATIONS: ALL RCAs EXCEPT UNIT 1 AND UNIT 2 REACTOR CONTAINMENTS JOB DESCRIPTION- Routine Duties, walkdown, and valve line-ups by Operations personnel. Access to Reactor Containments allowed for containment closure team only. THE MAXIMUM POSTED AREA THAT CAN BE ENTERED: Locked High Radiation Area RADIOLOGICAL CONDITIONS:*Indicates estimated value for RWP Preparation. See survey forms for details GENERAL AREA RADIATION LEVELS (mrem/hr): See Current RCA Surveys. CONTACT/HOT SPOT RADIATION LEVELS (mrem/hr): See Current RCA Surveys. CONTAMINATION LEVELS (dpmIlOOcm2): See Current RCA Surveys. AIRBORNE RADIOACTIVITY (DAC): 0.3* REQUIRED JOB COVERAGE: ROUTINE DOSIMETRY REQUIREMENTS: ED/SRD TLD DOSIMETRY COMMENTS: l.O)Caution: If PAM(ED) is utilized, ensure PAM(ED) is secured so that individual can feel the vibration if PAM(ED) alarms. 2.O)Notify HP prior to entry into a Neutron Exposure Area for additional dosimetry requirements. PROTECTIVE CLOTHING REQUIREMENTS: LAB COAT, SHOE COVERS & GLOVES MAY BE USED FOR ANY NON-PHYSICAL ACTIVITIES (I.E. OBSERVATIONS OR EQUIPMENT CHECKS> AND CONTAMINATION LEVELS ARE < 10,000 DPM/100CM2. 1.O)Required Protective Clothing: Surgeons Hood One Pair Coveralls Rubber Boots High Top Shoe Covers Cotton Inserts One Pair Rubber Gloves 2.0)Protective Clothing requirements as stated are for entry into Contaminated Areas only. 3.0)Double set of PCs are required for work in areas with contamination levels greater than 100,000 dpm/lOOcm2 4.0)Protective Clothing requirements for a Hot Particle Area (HPA) [in addition to those stated above] are: 4.l)Hood, gloves, coveralls, high top shoe covers and rubber boots. 4.2)Workers interfacing with individuals/equipment in a HPA - Gloves and face shield. ORIGINAL Page 2
Task Number I OF 3 RP-AA-274 ATT. 2 A RWP PRE-JOB BRIEFING IS REQUIRED: HRA BRIEF BY AN HP TECHNICIAN AND SIGN ATTENDANCE SHEET. WORKER INSTRUCTIONS: 1.0)ED Alarms: l.l)If ED dose rate alarm occurs, THEN leave area immediately and notify HP (unless authorized by HP Supervisor and have been briefed on proper responses> l.2)If ED dose alarm occurs, THEN leave area immediately and report to the Health Physics office. 2.0)Unless Continuous Health Physics Coverage is provided, workers shall read their SRD/ED approximately every 15 minutes. 3.0)When 80% of dose alarm setpoint is reached, leave work area in a safe condition and exit the RCA. 4.0)Do not enter High Radiation Areas without HP coverage or a ED with knowledge of work area dose rates. 5.0)Workers are responsible for notifying the HP Supervisor or Lead Technician prior to venting\draining systems, that may affect Radiological Conditions in an area, to ensure proper Health Physics Monitoring. 6.0)HPA exit instructions: 6.l)Use extreme care in removing PC5 and frisking. 6.2)Workers are to be monitored by HP upon exiting the HPA. 6.3)Workers are to be monitored by HP after interfacing with workers/equipment in a HPA. 7.0)Do not remove any items from a posted Hot Particle Area until authorized by HP-Ops. 8.0)Prior to returning Electronic Dosimetry (ED), all individuals shall process through the PDA for whole body monitoring. This is not required if returning ED solely for the purpose of changing RWPs. 9.0)Notify HP prior to entry in overhead areas greater than 8 feet. HEALTH PHYSICS INSTRUCTIONS: l.0)Stop work and leave area if whole body dose rates exceed 2000 mRem/hr. 2.0)When the ED dose rate alarm is set >1000 mRem/hr then: 2.1)Stay times and continuous HP coverage is required. 2.2)If worker ED alarms, then have worker immediately exit area and report to HP. 3.0)Hot Particle Area (HPA) monitoring requirements: 3.l)Workers exposed skin shall be monitored by HP-Ops every four hours while the workers are in the HPA. ORIGINAL Page 3
Task Number 2 OF 3 RP-AA-274 ATT. 2 VALID FROM 01-JAN-2014 00:00 TO 31-DEC-2014 23:59 14-1207-2 0 RWP REV. NO DOSE RATE ALARM: 90 mrem/Hr BUDGETED DOSE: 30 mrem DOSE LIMIT ALARM: 10 mrem ALARA EVALUATION NO: 14-001 JOB LOCATIONS: DECON BUILDING AND WASTE SOLIDS JOB DESCRIPTION: Perform change out of 1-DC-FL-2 (Radwaste Dewatering Filter). THE MAXIMUM POSTED AREA THAT CAN BE ENTERED: Locked High Radiation Area RADIOLOGICAL CONDITIONS:*Indicates estimated value for RWP Preparation. See survey forms for details GENERAL AREA RADIATION LEVELS (mrem/hr): 2 to 10, up to 500 at 1 foot from exposed tilters* CONTACT/HOT SPOT RADIATION LEVELS (mrem/hr): Up to 2500 on exposed filters* CONTAMINATION LEVELS (dpm/1 OOcm2):
<1000, up to 200,000 on exposed fi(ters*
AIRBORNE RADIOACTIVITY (DAC):
<0.30*
REQUIRED JOB COVERAGE: ROUTINE DOSIMETRY REQUIREMENTS: ED/SRD TLD DOSIMETRY COMMENTS: l.0)Caution: If PAM(ED) is utilized, ensure PAM(ED) is secured so that individual can feel the vibration if PAM(ED) alarms. PROTECTIVE CLOTHING REQUIREMENTS: LAB COAT, SHOE COVERS & GLOVES MAY BE USED FOR ANY NON-PHYSICAL ACTIVITIES (I.E. OBSERVATIONS OR EQUIPMENT CHECKS) AND CONTAMINATION LEVELS ARE < 10,000 DPM/100CM2. l.0)Required Protective Clothing: Surgeons Hood One Pair Coveralls Rubber Boots High Top Shoe Covers Cotton Inserts One Pair Rubber Gloves 2.0)Double PCs are required for work in areas with contamination levels greater than 100,000 dpm/lOOcm2 A RWP PRE-JOB BRIEFING IS REQUIRED: HRA BRIEF BY AN HP TECHNICIAN AND SIGN ATTENDANCE SHEET. ORIGINAL Page 4
Task Number 2 OF 3 RP-AA-274 ATT. 2 WORKER INSTRUCTIONS: l.0)ED Alarms: l.l)If ED dose rate alarm occurs, THEN leave area immediately and notify HP (unless authorized by HP Supervisor and have been briefed on proper responses) l.2)If ED dose alarm occurs, THEN leave area immediately and report to the Health Physics office. 2.0)Unless Continuous Health Physics Coverage is provided, workers shall read their SRD/ED approximately every 15 minutes. 3.0)When 80% of dose alarm setpoint is reached, leave work area in a safe condition and exit the RCA. 4.0)Do not enter High Radiation Areas without HP coverage or a ED with knowledge of work area dose rates. 5.0)Spent filters are to be stored according to the direction of the Supervisor RMC 6.0)Prior to returning Electronic Dosimetry (ED), all individuals shall process through the PDA for whole body monitoring. This is not required if returning ED solely for the purpose of changing RWP5. 7.0)Notify HP prior to entry in overhead areas greater than 8 feet. HEALTH PHYSICS INSTRUCTIONS: l.0)Stop work and leave area if whole body dose rates exceed 7500 mrem/hr.
2.0 )CAUTION
Filter dose rates are typically four times the filter housing dose rates. Set the ED Dose Rate Alarm accordingly. 3.0)When the ED dose rate alarm is set >1000 mRem/hr then: 3.1)Stay times and continuous HP coverage is required. 3.2)If worker ED alarms, then have worker immediately exit area and report to HP. 3 .0)Radiation survey requirements: 3.l)Prejob filter housing survey. 3.2)Of filters. 4 0) Contamination Survey requirements:
.
4.l)Post Job Survey 5.0)HPOps to emphasize precautions associated with opening contaminated systems. 6.0)If there is no DP across filters(See Operations), Strainer cleaning may be necessary. Additional contamination controls should be implemented. 7.0)Filter change-out criteria: 7.1)Filters are to be drained free of standing water. 7.2)Filters are to be bagged, with an amount of absorbent material (preferably mopheads) placed in the bag equal to the filter volume. 7.3)In NO case, should there be standing water in the bottom of the bag when placed for disposal, whether in the liner or the sea-land. 7.4)Filters can be placed on the DAW sea-land if contact dose rates are < 150 mrem/hr ; otherwise place in the High Radiation Trash DAW liner in Waste Solids. ORIGINAL Page 5
Task Number 3 OF 3 RP-AA-274 ATT. 2 VALID FROM 01-JAN-2014 00:00 TO 31-DEC-2014 23:59 14-1207-3 0 RWP REV. NO DOSE RATE ALARM: 90 mrem/Hr 17 BUDGETED DOSE: mrem DOSE LIMIT ALARM: mrem ALARA EVALUATION NO: 14-001 JOB LOCATIONS: Aux Building 259 BARS Skid JOB DESCRIPTION: BARS Operation, Sampling & 1-RP-FL-2 Change Out THE MAXIMUM POSTED AREA THAT CAN BE ENTERED Locked High Radiation Area RADIOLOGICAL CONDITIONS:*Indicates estimated value for RWP Preparation. See survey forms for details GENERAL AREA RADIATION LEVELS (mrem/hr): See Current RCA Surveys CONTACT/HOT SPOT RADIATION LEVELS (mremlhr): See Current RCA Surveys CONTAMINATION LEVELS (dpm/1 OOcm2): See Current RCA Surveys AIRBORNE RADIOACTIVITY (DAC): 0.3* REQUIRED JOB COVERAGE: ROUTINE DOSIMETRY REQUIREMENTS: ED/SRD TLD PROTECTIVE CLOTHING REQUIREMENTS: LAB COAT, SHOE COVERS & GLOVES MAY BE USED FOR ANY NON-PHYSICAL ACTIVITIES (I.E. OBSERVATIONS OR EQUIPMENT CHECKS) AND CONTAMINATION LEVELS ARE < 10,000 DPM/100CM2. l.0)Required Protective Clothing: Surgeons Hood One Pair Coveralls Rubber Boots High Top Shoe Covers Cotton Inserts One Pair Rubber Gloves 2.0)Protective Clothing requirements as stated are for entry into Contaminated Areas only. 3.0)Double set of PCs are required for work in areas with contamination levels greater than 100,000 dpm/lOOcm2 4.0)Protective Clothing requirements for a Hot Particle Area (HPA) [in addition to those stated above] are: 4.l)Hood, gloves, coveralls, high top shoe covers and rubber boots. 4.2)Workers interfacing with individuals/equipment in a HPA - Gloves and face shield. A RWP PRE-JOB BRIEFING IS REQUIRED: HRA BRIEF BY AN HP TECHNICIAN AND SIGN ATTENDANCE SHEET. ORIGINAL Page 6
Task Number 3 OF 3 RP-AA--274 ATT. 2 WORKER INSTRUCTIONS: 1.0)ED Alarms: l.l)If ED dose rate alarm occurs, THEN leave area immediately and notify HP (unless authorized by HP Supervisor and have been briefed on proper responses) l.2)If ED dose alarm occurs, THEN leave area immediately and report to the Health Physics office. 2.0)Unless Continuous Health Physics Coverage is provided, workers shall read their SRD/ED approximately every 15 minutes. 3.0)When 80% of dose alarm setpoint is reached, leave work area in a safe condition and exit the RCA. 4.0)Do not enter High Radiation Areas without HP coverage or a ED with knowledge of work area dose rates. 5.0)Workers are responsible for notifying the HP Supervisor or Lead Technician prior to venting\draining systems, that may affect Radiological Conditions in an area, to ensure proper Health Physics Monitoring. 6.0)HPA exit instructions: 6.l)Use extreme care in removing PC5 and frisking. 6.2)Workers are to be monitored by HP upon exiting the HPA. 6.3)Workers are to be monitored by HP after interfacing with workers/equipment in a HPA. 7.0)Do not remove any items from a posted Hot Particle Area until authorized by HP-Ops. 8.0)Prior to returning Electronic Dosimetry (ED), all individuals shall process through the PDA for whole body monitoring. This is not required if returning ED solely for the purpose of changing RWP5. 9.0)Notify HP prior to entry in overhead areas greater than 8 feet. HEALTH PHYSICS INSTRUCTIONS: l.0)Stop work and leave area if whole body dose rates exceed 1500 mrem/hr. 2.0)When the ED dose rate alarm is set >1000 mRem/hr then: 2.l)Stay times and continuous HP coverage is required. 2.2)If worker ED alarms, then have worker immediately exit area and report to HP. 3 .0)Radiation survey requirements: 3.l)Prejob filter housing survey. 3.2)Of filter.
- 4. 0) Contamination Survey requirements:
4.l)Post Job Survey 5.0)HP-Ops to emphasize precautions associated with opening contaminated systems. 6.0)Filter change-out criteria: 6.l)Filters are to be drained free of standing water. 6.2)Filters are to be bagged, with an amount of absorbent material (preferably mopheads) placed in the bag equal to the filter volume. 6.3)In NO case, should there be standing water in the bottom of the bag when placed for disposal, whether in the liner or the sea-land. 6.4)Filters can be placed on the DAW sea-land if contact dose rates are < 150 mrem/hr otherwise place in the High Radiation Trash DAW liner in Waste Solids. ORIGINAL Page 7
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Both units were at 100% power. High winds from a severe thunderstorm caused a loss of all off-site power. All emergency diesel generators started and loaded as designed. A tube rupture occurred on the unit 1 A steam generator. The unit 1 control room crew manually initiated safety injection. An operator has been directed to locally close the unit 1 A SG PORV which is open and will not shut from the control room. INITIATING CUE You are requested to classify the emergency event in accordance with EPIP-1 .01. Do NOT use SEM Judgment to classify the event. This is a time critical JPM (15 minutes). Record your results in the spaces provided. Emergency Classification EAL Identifier ADMIN JPM 4 SRO NAPS 2014 NRC EXAM Page 1 of 7
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Classify an emergency event. TASK STANDARDS Event is classified as a Site Area Emergency (FS1.1) in accordance with EPIP-1.01 and the applicable Emergency Level Action Matrix (Hot Conditions > 200°F). Classification is made within 15 minutes of starting the evaluation. K!A
REFERENCE:
G2.4.41 (4.6) ALTERNATE PATH: N/A TASK COMPLETION TIMES Validation Time = 12 minutes Start Time = Actual Time = minutes Stop Time = PERFORMANCE EVALUATION Rating [1 SATISFACTORY [ ] UNSATISFACTORY Candidate (Print) Evaluator (Print) Evaluators Signature / Date EVALUATORS COMMENTS ADMIN JPM 4 SRO NAPS 2014 NRC EXAM Page 2 of 7
Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. 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. Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 Both units were at 100% power. High winds from a severe thunderstorm caused a loss of all off-site power. All emergency diesel generators started and loaded as designed. A tube rupture occurred on the unit 1 A steam generator. The unit 1 control room crew manually initiated safety injection. An operator has been directed to locally close the unit 1 A SG PORV which is open and will not shut from the control room. INITIATING CUE You are requested to classify the emergency event in accordance with EPIP-1.01. Do NOT use SEM Judgment to classify the event. This is a time critical JPM (15 minutes). Record your results in the spaces provided. Emergency Classification EAL Identifier ADMIN JPM 4 SRO NAPS 2014 NRC EXAM Page 3 of 7
EVALUATION METHOD Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues) Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues) TOOLS AND EQUIPMENT EPIP-1 .01 EAL Matrix EAL Basis Document PERFORMANCE STEPS START TIME START TIME IS CRITICAL: Start time begins the 15 minute clock for event classification (clock stops when classification is made element 4 of JPM).
1 Operator determines the Event Category on the applicable Procedure Step Emergency Action Level Matrix. Critical Step SAT[] UNSAT[] Standards Event is identified as Fission Product Barriers, Category F, of the Hot Conditions > 200°F Matrix. Notes/Comments ADMIN JPM 4 SRO NAPS 2014 NRC EXAM Page 4 of 7
_____ 2 Operator reviews the Emergency Action Level Matrix associated Procedure Step with the Event Category. ISATI1 UNSATF1 I Standards I Category F reviewed to determine highest level of classification. Notes/Comments 3 Operator uses available resources to obtain indications of Procedure Step emergency conditions. SAT[1 UNSAT[T Standards Category F emergency condition descriptions are compared to the Initial Conditions.
. Table F-i is reviewed to determine that RCS Barrier D.3 and Containment Barrier D.3 apply (loss of two barriers).
- Category F is reviewed to determine that FS1 .1 applies (loss or potential_loss_of_any_two_barriers).
Notes/Comments SU1.i may be noted as a lower level classification. ADMIN JPM 4 SRO NAPS 2014 NRC EXAM Page 5 of 7
_____ 4 Operator classifies event based on emergency action level being Procedure Step exceeded. Critical Step SAT[] UNSAT[J Standards Event is classified as a Site Area Emergency lAW EAL Identifier FS1.1 within 15 minutes of the start of the evaluation. Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME ADMIN JPM 4 SRO NAPS 2014 NRC EXAM Page 6 of 7
SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required) ADMIN JPM 4 SRO NAPS 2014 NRC EXAM Page 7 of 7}}