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| issue date = 02/06/2009
| issue date = 02/06/2009
| title = DC-2009-02-Draft Outlines
| title = DC-2009-02-Draft Outlines
| author name = Larson B T
| author name = Larson B
| author affiliation = NRC/RGN-IV/DRS/OB
| author affiliation = NRC/RGN-IV/DRS/OB
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:ES-301, Page 22 of 27ES-301Administrative Topics OutlineForm ES-301-1Facility: _______________________________           Date of Examination: _____________Examination Level:   RO          SRO         Operating Test Number:   __________
{{#Wiki_filter:ES-301                             Administrative Topics Outline                                    Form ES-301-1 Diablo Canyon Facility: _______________________________                                                           02/09/09 Date of Examination: _____________
Administrative Topic (see Note)
Examination Level: RO          SRO                                     Operating Test Number: __________L061C Administrative Topic           Type                        Describe activity to be performed (see Note)               Code*
Type Code*Describe activity to be performed Conduct of Operations Conduct of Operations Equipment Control
Determination of SFP Heat Load Removal Parameters (LJACO-01R)
Conduct of Operations               D, R      G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation. (4.4)
Review Outage Safety Checklist (NRC ADM02SRO - L031)
Conduct of Operations               D, R      G2.1.40 - Knowledge of refueling administrative requirements. (3.9)
Verify AFD is within Tech Spec Limits (LJAEC - 11S)
Equipment Control                   D, R      G2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications. (4.6)
Review Liquid Radwaste Discharge checklist N, R      G2.3.6 - Ability to approve release permits. (3.8)
Radiation Control Offsite Dose Assessment and classification - FHB Accident (LJC-166)
D, R l  Emergency Procedures/Plan                      G2.4.41 - Knowledge of the emergency action level thresholds and classifications. (4.6)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 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)
ES-301, Page 22 of 27


Radiation Control
ES-301                            Control Room/In-Plant Systems Outline                              Form ES-301-2 Diablo Canyon Facility: _____________________________                                                            02/09/09 Date of Examination: ______________
Exam Level: RO              SRO-I  SRO-U                                                          L061C Operating Test No.: _______________
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title                                    Type Code*            Safety Function
: a. S1 - 004/Isolate VCT Rupture (LJC-005)                                              M,A,E,S              02
: b. S2 - 010/Respond to PT-456 failed high (LJC-143)                                      D,S              03
: c. S3 - 005/Isolate LOCA outside containment (LJC-118)                                D,A,E,S            04p
: d. S4 - 103/Manually isolate CVI components                                            N,A,E,S              05
: e. S5 - 008/Loss of CCW to one RCP (L031 NRC test)                                    D,A,E,S              08
: f. S6 - 041/RCS cooldown for SGTR (LJC-090)                                            D,A,E,S            04s
: g. S7 - 073/Verify RM-44A OPERABLE                                                      N,S                07 h.
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. P1 - 062/Transfer pressurizer heater group 12 to backup (LJP-029)                    D,L,E              06
: j. P2 - 004/Align CCP suction to RWST (LJP-207, modified for Unit 2)                  M,E,L,R              02
: k. P3 - 012/De-energize SSPS to block SI (LJP-09S)                                        D,L              07
@          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-I / SRO-U                l (A)lternate path                                                              4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank                                                            #9/#8/#4 (E)mergency or abnormal in-plant                                              $1/$1/$1 (EN)gineered safety feature                                                      - / - / $1 (control room system)  l (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 (S)imulator ES-301, Page 23 of 27


Emergency Procedures/Plan lNOTE:All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 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)
ES-301                                     Transient and Event Checklist                             Form ES-301-5 Facility:                                         Date of Exam:                       Operating Test No.:
ES-301, Page 23 of 27ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility:  _____________________________          Date of Examination:  ______________Exam Level:  RO        SRO-I        SRO-U      Operating Test No.:  _______________
A          E                                                    Scenarios P          V              1                     2                   3                 4           T      M P          E                                                                                      O      I L          N          CREW                 CREW                CREW              CREW          T      N I          T        POSITION             POSITION             POSITION           POSITION         A I
Control Room Systems
M C                    S     A       B    S      A      B     S     A     B    S    A     B    L     U A           T       R      T     O      R      T     O      R     T      O   R    T     O          M(*)
@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM TitleType Code*Safety Function a.b.
N          Y        O      C       P     O     C     P     O     C     P   O     C     P R     I U T          P E
c.
RO          RX                                     2                                                 1   1   1 0 NOR                                     3                                                 1   1   1 1 SRO-I I/C       3,4, 5                     1-3,6                     3,4,7,8                   11   4   4 2 SRO-U        MAJ       7                           4                           6                     3   2   2 1 TS       3,4                                                                             2   0   2 2 RO          RX               2                                                                       1   1   1 0 NOR               1                           3                                           2   1   1 1 SRO-I I/C             3,4,5                     1,2,5   1,3-5                                 10   4   4 2 SRO-U        MAJ               7                         4       6                                   3   2   2 1 TS                                                 3,4                                   2   0   2 2 RO          RX                                                           2                             1   1   1 0 NOR                       1                                                               1   1   1 1 SRO-I I/C                     3,4,5 1,2,3                       1,3,5                           9   4   4 2 SRO-U        MAJ                       7     4                           6                             3   2   2 1 TS                             1,3                                                         2   0   2 2 RO          RX                                                                                             1   1 0 NOR                                                                                             1   1 1 SRO-I I/C                                                                                             4   4 2 SRO-U        MAJ                                                                                             2   2 1 TS                                                                                             0   2 2 Instructions:
d.
: 1.       Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
e.
: 2.       Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
f.
: 3.       Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
g.
h.
In-Plant Systems
@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i.j.k.@All RO and SRO-I control room (and in-plant) syst ems must be different and serve different safetyfunctions; 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 lCriteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature l(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 /  8 /  4 1 /  1 /  1  -  /  -  /  1 (control room system) l 1 /  1 /  1 2 /  2 /  1 3 /  3 /  2 (randomly selected) 1 /  1 /  1 ES-301 Transient and Event Checklist Form ES-301-5 Facility:     Date of Exam:   Operating Test No.:
Scenarios 1 2 3 4 CREW POSITION CREW POSITION CREW POSITION CREW POSITION      M       I N      I     M     U     M(*) A P P L I C A N T E V E N T T Y P E S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P T O T A L R I U RX       2         1 1 1 0 NOR       3           1 1 1 1 I/C 3,4, 5   1-3,6   3,4,7,8     11 4 4 2 MAJ   7     4       6     3 2 2 1 RO  SRO-I  SRO-U  TS 3,4             2 0 2 2 RX   2           1 1 1 0 NOR   1       3       2 1 1 1 I/C 3,4,5   1,2,5 1,3-5       10 4 4 2 MAJ     7      4    6       3 2 2 1 RO        SRO-I  SRO-U  TS       3,4       2 0 2 2 RX           2     1 1 1 0 NOR     1           1 1 1 1 I/C   3,4,5 1,2,3   1,3,5     9 4 4 2 MAJ     7   4       6     3 2 2 1 RO  SRO-I  SRO-U  TS   1,3         2 0 2 2 RX             1 1 0 NOR             1 1 1 I/C             4 4 2 MAJ             2 2 1 RO  SRO-I  SRO-U  TS             0 2 2 Instructions:  
: 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"  and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.  
: 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.  
: 3.         Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
A p p e n d i x D , Rev. 9    Scenario Outline Form ES-D-1  Facilit y: Diablo Ca ny on  Scenario No.:
1  Op-T est No.: L061 C-1  E x a m i n e r s:  Opera t ors:                Initial Conditions: 10 0% Rea c tor p o w e r, BOL, Bor on at 11 82 p p m  CFCU 1-2 cleared.
Turnov er:  High S w e ll w a rning is exp ecte d in 6 hours. ODM ha s decided to ramp both u n its to 25% po w e r  at 3 MW/min. OP O-28 ac tions are co mplete. OP L-4 prep ara t io ns are don e, at ste p 6.3.3.m. Turn Pzr Bac k up hea t ers on and c o mmence ra mp. Ev ent No. Malf. No.
Ev ent Ty p e* Ev ent Desc ription and Ti me Line 1  N Turn P z r Ba ckup Heate r s ON. 2  R Ramp u n it to 25% power.
3 Xmt rcs15 I Loop 1 n a rro w ran ge T c ol d fails high a nd ca uses ro ds to step in. (TS 3.3.1.E & X and 3.3.2.M) 4 Pmp ven C CFCU 11 ove r cu rrent trip. (TS 3.6.6.C )
5 Cnv  mf w 6 C FCV-5 40 F W reg valve to S/G 14 fails op en 6 mal tur1 C No Automatic turbine trip, mus t trip manually.  (CT) 7 mal rcs3a M Small brea k L O CA (4") 3 m i nutes after tu rbine tri p. Will requi re RCP Trip criteria.(CT) 8 Mal eps C 4KV Bus G differential trip on Safety Injec t ion. 9 pmp cvc1 C Cha r gin g pu mp 11 doe sn't auto start. (CT) 
                *(N)ormal,    (R)eacti v i t y ,    (I)n strument,    (C)omponent
,    (M)aj o r                  L061C Scenario 1.doc Rev. 0 


A p p e n d i x D , Rev. 9   Scenario Outline Form ES-D-1   Facilit y: Diablo Ca ny on  Scenario No.:
Appendix D, Rev. 9                               Scenario Outline                             Form ES-D-1 Facility:       Diablo Canyon                Scenario No.:   1                      Op-Test No.:     L061C-1 Examiners:                                                       Operators:
2  Op-T est No.: L061 C-2  E x a m i n e r s:   Opera t ors:               Initial Conditions: 75
Initial Conditions: 100% Reactor power, BOL, Boron at 1182 ppm CFCU 1-2 cleared.
% R eactor po w e r, MOL, Boro n at 848 ppm ASW pp 12 cleared.
Turnover: High Swell warning is expected in 6 hours. ODM has decided to ramp both units to 25% power at 3 MW/min. OP O-28 actions are complete. OP L-4 preparations are done, at step 6.3.3.m. Turn Pzr Backup heaters on and commence ramp.
Turnov er:   Ev ent No. Malf. No.
Event      Malf. No.     Event                              Event Description and Time Line No.                      Type*
Ev ent Ty p e* Ev ent Desc ription and Ti me Line 1 Vlv pzr5 C PCV-45 6 Pzr PORV fails o pen, must i s o l ate usin g blo ck valve. (TS 3.4.11 )  (CT) 2 M a l mfw2a R - CO C - BO Ramp u n it to 50% power d ue to FWP 11 high vibratio
1                           N        Turn Pzr Backup Heaters ON.
: n. 3 Xm t m f w 3 7 I N - CO N -BOP LT-4 59 Pzr le vel chan nel fails to 10%
2                           R         Ramp unit to 25% power.
  (TS 3.3.1.M, 3.3.3.F, 3.3.4)
3           Xmt rcs15      I         Loop 1 narrow range Tcold fails high and causes rods to step in. (TS 3.3.1.E & X and 3.3.2.M) 4          Pmp ven        C        CFCU 11 overcurrent trip. (TS 3.6.6.C )
Res t ores letdown flow.
5          Cnv mfw6        C        FCV-540 FW reg valve to S/G 14 fails open 6          mal tur1        C        No Automatic turbine trip, must trip manually. (CT) 7          mal rcs3a      M        Small break LOCA (4) 3 minutes after turbine trip. Will require RCP Trip criteria.(CT) 8          Mal eps        C         4KV Bus G differential trip on Safety Injection.
4 Mal rcs4c M S/G 13 tube leak ramp s to 400 gpm  (CT
9          pmp cvc1        C        Charging pump 11 doesnt auto start. (CT)
) 5 Pmp as w 1 C ASW pp 11 trips on ove r cu rre nt on rea c t o r trip, re quires x-tie with U-2.   (CT
*(N)ormal,    (R)eactivity,   (I)nstrument,     (C)omponent, (M)ajor L061C Scenario 1.doc                                     Rev. 0
) 6 Cnv mss C PCV-21 fail s open after RCS cool do wn co mplete. T r ansitio n to ECA 3.1   
                *(N)ormal,    (R)eacti v i t y ,   (I)n strument,   (C)omponent
,   (M)aj o r                  L061C Scenario 2.doc Rev. 0


L061C Scenario 3.doc  Rev. 0 Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility:Diablo Canyon Scenario No.:
Appendix D, Rev. 9                           Scenario Outline                               Form ES-D-1 Facility:       Diablo Canyon             Scenario No.:     2                        Op-Test No.:       L061C-2 Examiners:                                                     Operators:
3 Op-Test No.:L061C-3 Examiners:
Initial Conditions: 75% Reactor power, MOL, Boron at 848 ppm ASW pp 12 cleared.
Operators:
Turnover:
Initial Conditions: 100% Power, MOL, 782 ppm CB Turnover:  PRA Status: Yellow. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. RHR pp 11 is cleared for seal repair. U-2 at 100% power.
Event     Malf. No.       Event                             Event Description and Time Line No.                      Type*
Event No. Malf. No. Event Type* Event Description and Time Line 1 mal cvc8    C RCP seal injection filter plugs up, reducing charging flow to seals.
1           Vlv pzr5        C         PCV-456 Pzr PORV fails open, must isolate using block valve. (TS 3.4.11 )
2     R TOC requests ramp to 900 MW at 25 MW/min 3 xmt rcs93 I NI-44 fails high, requires rods to manual. ( TS 3.3.1.D, E, S, T) 4 mal eps4c C 4KV bus F diff trip  (TS 3.0.3 due to loss of both RHR pumps )
(CT) 2           Mal            R - CO    Ramp unit to 50% power due to FWP 11 high vibration.
5 mal mfw2a mal mfw2b C Both MFW pumps trip spuriously.
mfw2a          C - BO 3           Xmt mfw37      I         LT-459 Pzr level channel fails to 10% (TS 3.3.1.M, 3.3.3.F, 3.3.4)
6 mal ppl5a mal ppl5b M Reactor trip breakers won't open from the control room. ATWS. (CT) 7 ovr xv5i245o    C 52-hd-13 fdr for bus 13d fails to open, so 1 MG set stays in service. Crew must insert rods and go to FR S.1.  (CT) 8 vlv afw7    C TDAFW pp 11 fcv-95 won't open automatically, crew must open at VB3.   (CT)
N - CO    Restores letdown flow.
                    *(N)ormal,    (R)eactivity,   (I)nstrument,   (C)omponent,    (M)ajor
N -BOP 4          Mal rcs4c      M         S/G 13 tube leak ramps to 400 gpm (CT) 5          Pmp asw1        C         ASW pp 11 trips on overcurrent on reactor trip, requires x-tie with U-2. (CT) 6          Cnv mss        C         PCV-21 fails open after RCS cooldown complete. Transition to ECA 3.1
*(N)ormal,    (R)eactivity,   (I)nstrument, (C)omponent,    (M)ajor L061C Scenario 2.doc                                          Rev. 0


11/12/2008 Printed: ES-401 Facility: Diablo Canyon Power Plant PWR Examination Outline Form ES-401-2 3 3 3 3 3 3 1 2 2 1 1 2 4 5 5 4 4 5 3 2 3 3 3 2 1 3 2 3 3 1 1 1 1 1 1 1 0 1 1 1 4 3 4 4 4 3 2 3 3 4 4 2 3 3 2 RO K/A  Category  Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*1.Emergency&Abnormal Plant Evolutions 1 1 2 2 Tier Totals Tier Totals 2.Plant Systems 1 2 3 4 3. Generic Knowledge And Abilities Categories 2.The point total for each group and tier in the proposed outline must match that specified in the table.
Appendix D, Rev. 9                                      Scenario Outline                                    Form ES-D-1 Facility:       Diablo Canyon               Scenario No.:      3                        Op-Test No.:      L061C-3 Examiners:                                                        Operators:
Initial Conditions: 100% Power, MOL, 782 ppm CB Turnover: PRA Status: Yellow. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. RHR pp 11 is cleared for seal repair. U-2 at 100% power.
Event      Malf. No.      Event                              Event Description and Time Line No.                      Type*
1          mal cvc8        C        RCP seal injection filter plugs up, reducing charging flow to seals.
2                            R        TOC requests ramp to 900 MW at 25 MW/min 3          xmt rcs93        I        NI-44 fails high, requires rods to manual. ( TS 3.3.1.D, E, S, T) 4          mal eps4c        C        4KV bus F diff trip (TS 3.0.3 due to loss of both RHR pumps )
5          mal mfw2a        C        Both MFW pumps trip spuriously.
mal mfw2b 6          mal ppl5a        M        Reactor trip breakers wont open from the control room. ATWS. (CT) mal ppl5b 7          ovr              C        52-hd-13 fdr for bus 13d fails to open, so 1 MG set stays in service. Crew must xv5i245o                  insert rods and go to FR S.1. (CT) 8          vlv afw7        C        TDAFW pp 11 fcv-95 won't open automatically, crew must open at VB3. (CT)
*(N)ormal,    (R)eactivity,  (I)nstrument,    (C)omponent,    (M)ajor L061C Scenario 3.doc                                          Rev. 0
 
ES-401                                            PWR Examination Outline                                             Form ES-401-2 Facility:      Diablo Canyon Power Plant                                                                        Printed: 11/12/2008 Date Of Exam:          02/06/2009 RO K/A Category Points                                                SRO-Only Points Tier      Group K1        K2  K3    K4    K5    K6 A1      A2  A3    A4 G* Total                  A2        G*    Total
: 1.          1      3     3   3                     3     3                 3     18              0          0        0 Emergency 2      1     2   2                     1     1                 2     9              0          0        0
      &                                          N/A                      N/A Abnormal Tier Plant Totals    4     5   5                     4     4                 5     27              0          0        0 Evolutions 1      3     2   3     3     3     2   1     3   2     3   3     28              0          0        0 2.
2      1     1   1     1     1     1   1     0   1     1     1     10        0      0        0        0 Plant Systems          Tier                                                                                      0          0        0 4     3   4     4     4     3   2     3   3     4     4     38 Totals 1          2           3           4                1     2   3     4
: 3. Generic Knowledge And 10                                  0 Abilities Categories 2          3          3            2                0      0  0      0 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.
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.
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.
: 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.
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.
: 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.
Note: Date Of Exam:
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
02/06/2009 28 18 9 27 10 38 10 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).
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.
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 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.
: 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.
SRO-Only  Points A2 G* 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 3 4 0 0 0 0 0 0 0 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.
: 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.
Limit SRO selections to K/As that are linked to 10 CFR 55.43.
11/12/2008             9:31:49 am                                                                                                   1
6.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
 
N/A N/A Total 0 0 1 11/12/2008 9:31:49 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
PWR RO Examination Outline                                      Printed:    11/12/2008 Facility:   Diablo Canyon Power Plant ES - 401                                Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1                             Form ES-401-2 E/APE # / Name / Safety Function                K1  K2  K3 A1 A2      G      KA Topic                                      Imp.       Points 000008 Pressurizer Vapor Space Accident /        X                            AK1.02 - Change in leak rate with                 3.1       1 3                                                                            change in pressure 000009 Small Break LOCA / 3                                         X        EA2.12 - Charging pump ammeter                     2.8       1 000011 Large Break LOCA / 3                                     X            EA1.03 - Securing of RCPs                         4.0       1 000022 Loss of Rx Coolant Makeup / 2            X                           AK1.03 - Relationship between                     3.0        1 charging flow and PZR level 000025 Loss of RHR System / 4                                      X        AA2.07 - Pump cavitation                           3.4       1 000027 Pressurizer Pressure Control System            X                     AK2.03 - Controllers and positioners               2.6       1 Malfunction / 3 000029 ATWS / 1                                        X                      EK2.06 - Breakers, relays, and                   2.9*       1 disconnects 000038 Steam Gen. Tube Rupture / 3              X                           EK1.01 - Use of steam tables                       3.1       1 000040 Steam Line Rupture - Excessive                  X                      AK2.02 - Sensors and detectors                   2.6*       1 Heat Transfer / 4 000054 Loss of Main Feedwater / 4                              X            AA1.01 - AFW controls, including the               4.5        1 use of alternate AFW sources 000055 Station Blackout / 6                                              X   2.1.31 - Ability to locate control room           4.6        1 switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
ES - 401 Facility: Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 AK1.02 - Change in leak rate with change in pressure 3.1 1 X 000008 Pressurizer Vapor Space Accident /
000056 Loss of Off-site Power / 6                                   X         AA2.19 - T-cold and T-hot indicators               4.0        1 (wide range) 000057 Loss of Vital AC Inst. Bus / 6                                   X    2.4.20 - Knowledge of operational                 3.8        1 implications of EOP warnings, cautions, and notes.
3 EA2.12 - Charging pump ammeter 2.8 1 X 000009 Small Break LOCA / 3 EA1.03 - Securing of RCPs 4.0 1 X 000011 Large Break LOCA / 3 AK1.03 - Relationship between charging flow and PZR level 3.0 1 X 000022 Loss of Rx Coolant Makeup / 2 AA2.07 - Pump cavitation 3.4 1 X 000025 Loss of RHR System / 4 AK2.03 - Controllers and positioners 2.6 1 X 000027 Pressurizer Pressure Control System Malfunction / 3 EK2.06 - Breakers, relays, and disconnects 2.9*1 X 000029 ATWS / 1 EK1.01 - Use of steam tables 3.1 1 X 000038 Steam Gen. Tube Rupture / 3 AK2.02 - Sensors and detectors 2.6*1 X 000040 Steam Line Rupture - Excessive Heat Transfer / 4 AA1.01 - AFW controls, including the use of alternate AFW sources 4.5 1 X 000054 Loss of Main Feedwater / 4 2.1.31 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
000058 Loss of DC Power / 6                                     X            AA1.02 - Static inverter dc input                 3.1*        1 breaker, frequency meter, ac output breaker, and ground fault detector 000062 Loss of Nuclear Svc Water / 4                      X                  AK3.02 - The automatic actions                     3.6        1 (alignments) within the nuclear service water resulting from the actuation of the ESFAS 000065 Loss of Instrument Air / 8                                        X   2.4.47 - Ability to diagnose and                   4.2        1 recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
4.6 1 X 000055 Station Blackout / 6 AA2.19 - T-cold and T-hot indicators (wide range) 4.0 1 X 000056 Loss of Off-site Power / 6 2.4.20 - Knowledge of operational implications of EOP warnings, cautions, and notes.
W/E04 LOCA Outside Containment / 3                        X                 EK3.4 - RO or SRO function within the             3.6        1 control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated 11/12/2008         9:38:08 am                                                                                                                 1
3.8 1 X 000057 Loss of Vital AC Inst. Bus / 6 AA1.02 - Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector 3.1*1 X 000058 Loss of DC Power / 6 AK3.02 - The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 3.6 1 X 000062 Loss of Nuclear Svc Water / 4 2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
 
4.2 1 X 000065 Loss of Instrument Air / 8 EK3.4 - RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated 3.6 1 X W/E04 LOCA Outside Containment / 3 1 11/12/2008 9:38:08 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
PWR RO Examination Outline                                    Printed:    11/12/2008 Facility:  Diablo Canyon Power Plant ES - 401                                Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1                           Form ES-401-2 E/APE # / Name / Safety Function                K1  K2  K3 A1 A2      G      KA Topic                                  Imp.      Points W/E05 Inadequate Heat Transfer - Loss of                  X                  EK3.2 - Normal, abnormal and                   3.7        1 Secondary Heat Sink / 4                                                      emergency operating procedures associated with Loss of Secondary Heat Sink K/A Category Totals:    3   3   3   3   3   3                                   Group Point Total:       18 11/12/2008         9:38:08 am                                                                                                               2
ES - 401 Facility: Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EK3.2 - Normal, abnormal and emergency operating procedures associated with Loss of Secondary Heat Sink 3.7 1 X W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 18 3 3 3 3 3 3 K/A Category Totals:
 
Group Point Total:
PWR RO Examination Outline                                      Printed:    11/12/2008 Facility:   Diablo Canyon Power Plant ES - 401                                 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2                             Form ES-401-2 E/APE # / Name / Safety Function                K1  K2  K3 A1 A2      G      KA Topic                                      Imp.       Points 000032 Loss of Source Range NI / 7                         X                  AK3.01 - Startup termination on                    3.2        1 source-range loss 000033 Loss of Intermediate Range NI / 7                           X        AA2.01 - Equivalency between                      3.0        1 source-range, intermediate-range, and power-range channel readings 000036 Fuel Handling Accident / 8               X                            AK1.02 - SDM                                      3.4       1 000059 Accidental Liquid RadWaste Rel. /                                 X    2.2.22 - Knowledge of limiting                    4.0        1 9                                                                            conditions for operations and safety limits.
2 11/12/2008 9:38:08 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
000060 Accidental Gaseous Radwaste Rel. /                                X    2.4.50 - Ability to verify system alarm           4.2        1 9                                                                            setpoints and operate controls identified in the alarm response manual.
ES - 401 Facility: Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AK3.01 - Startup termination on source-range loss 3.2 1 X 000032 Loss of Source Range NI / 7 AA2.01 - Equivalency between source-range, intermediate-range, and power-range channel readings 3.0 1 X 000033 Loss of Intermediate Range NI / 7 AK1.02 - SDM 3.4 1 X 000036 Fuel Handling Accident / 8 2.2.22 - Knowledge of limiting conditions for operations and safety limits.4.0 1 X 000059 Accidental Liquid RadWaste Rel. /
000074 Inad. Core Cooling / 4                             X                 EK3.04 - Tripping RCPs                             3.9       1 W/E08 RCS Overcooling - PTS / 4                       X                      EK2.2 - Facility's heat removal systems,           3.6        1 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility W/E13 Steam Generator Over-pressure / 4                         X            EA1.1 - Components, and functions of               3.1        1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features W/E14 Loss of CTMT Integrity / 5                      X                      EK2.2 - Facility's heat removal systems,           3.4        1 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility K/A Category Totals:    1   2   2   1   1   2                                     Group Point Total:         9 11/12/2008         9:38:15 am                                                                                                                 1
9 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
 
4.2 1 X 000060 Accidental Gaseous Radwaste Rel. /
PWR RO Examination Outline                                          Printed:    11/12/2008 Facility:   Diablo Canyon Power Plant ES - 401                                       Plant Systems - Tier 2 / Group 1                                           Form ES-401-2 Sys/Evol # / Name                    K1 K2 K3  K4    K5  K6  A1    A2  A3  A4 G KA Topic                            Imp. Points 003 Reactor Coolant Pump                X                                            K1.08 - Containment                   2.7*     1 isolation 004 Chemical and Volume Control                                              X       A3.03 - Ion exchange                   2.9     1 bypass 004 Chemical and Volume Control                         X                            K5.11 - Thermal stress,               3.6      1 brittle fracture, pressurized thermal shock 005 Residual Heat Removal                              X                             K5.02 - Need for adequate             3.4     1 subcooling 006 Emergency Core Cooling                                                          X 2.1.30 - Ability to locate and         4.4      1 operate components, including local controls.
9 EK3.04 - Tripping RCPs 3.9 1 X 000074 Inad. Core Cooling / 4 EK2.2 - Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility 3.6 1 X W/E08 RCS Overcooling - PTS / 4 EA1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.1 1 X W/E13 Steam Generator Over-pressure / 4 EK2.2 - Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility 3.4 1 X W/E14 Loss of CTMT Integrity / 5 9 1 2 2 1 1 2 K/A Category Totals:
006 Emergency Core Cooling                                   X                        K6.13 - Pumps                         2.8     1 007 Pressurizer Relief/Quench                    X                                   K4.01 - Quench tank                   2.6     1 Tank                                                                                  cooling 008 Component Cooling Water                                              X           A2.02 - High/low surge tank           3.2     1 level 008 Component Cooling Water               X                                          K2.02 - CCW pump,                     3.0*     1 including emergency backup 010 Pressurizer Pressure Control                                                  X   A4.01 - PZR spray valve               3.7     1 010 Pressurizer Pressure Control                             X                        K6.03 - PZR sprays and                 3.2     1 heaters 012 Reactor Protection                                                  X           A2.03 - Incorrect channel             3.4     1 bypassing 013 Engineered Safety Features                                                      X 2.4.31 - Knowledge of                 4.2      1 Actuation                                                                            annunciator alarms, indications, or response procedures.
Group Point Total:
013 Engineered Safety Features         X                                            K1.10 - CPS                           2.8*     1 Actuation 022 Containment Cooling                                                          X   A4.01 - CCS fans                       3.6     1 022 Containment Cooling                                                 X            A2.01 - Fan motor                     2.5     1 over-current 026 Containment Spray                      X                                         K2.01 - Containment spray             3.4*     1 pumps 039 Main and Reheat Steam                                                    X       A3.02 - Isolation of the               3.1     1 MRSS 059 Main Feedwater                                                                X   A4.03 - Feedwater control             2.9*      1 during power increase and decrease 059 Main Feedwater                           X                                      K3.04 - RCS                           3.6     1 061 Auxiliary/Emergency                X                                            K1.11 - AFW turbine                   2.7     1 Feedwater                                                                            exhaust/drains 062 AC Electrical Distribution                X                                       K3.03 - DC system                     3.7     1 063 DC Electrical Distribution                                   X                  A1.01 - Battery capacity as           2.5      1 it is affected by discharge rate 11/12/2008           9:38:24 am                                                                                                 1
1 11/12/2008 9:38:15 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
 
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
PWR RO Examination Outline                                          Printed:    11/12/2008 Facility:   Diablo Canyon Power Plant ES - 401                                       Plant Systems - Tier 2 / Group 1                                         Form ES-401-2 Sys/Evol # / Name                    K1 K2 K3 K4    K5  K6  A1    A2  A3  A4 G  KA Topic                          Imp. Points 064 Emergency Diesel Generator                X                                        K3.01 - Systems controlled         3.8*       1 by automatic loader 073 Process Radiation Monitoring                        X                             K5.01 - Radiation theory,           2.5      1 including sources, types, units, and effects 076 Service Water                                                                  X 2.4.4 - Ability to recognize         4.5      1 abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
Diablo Canyon Power Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K1.08 - Containment isolation 2.7*1 X 003 Reactor Coolant Pump A3.03 - Ion exchange bypass 2.9 1 X 004 Chemical and Volume Control K5.11 - Thermal stress, brittle fracture, pressurized thermal shock 3.6 1 X 004 Chemical and Volume Control K5.02 - Need for adequate subcooling 3.4 1 X 005 Residual Heat Removal 2.1.30 - Ability to locate and operate components, including local controls.
078 Instrument Air                                X                                   K4.03 - Securing of SAS             3.1*      1 upon loss of cooling water 103 Containment                                  X                                   K4.01 - Vacuum breaker             3.0*       1 protection K/A Category Totals:   3  2  3  3     3   2     1    3  2   3 3                      Group Point Total:       28 11/12/2008         9:38:24 am                                                                                                 2
4.4 1 X 006 Emergency Core Cooling K6.13 - Pumps 2.8 1 X 006 Emergency Core Cooling K4.01 - Quench tank cooling 2.6 1 X 007 Pressurizer Relief/Quench Tank A2.02 - High/low surge tank level 3.2 1 X 008 Component Cooling Water K2.02 - CCW pump, including emergency backup 3.0*1 X 008 Component Cooling Water A4.01 - PZR spray valve 3.7 1 X 010 Pressurizer Pressure Control K6.03 - PZR sprays and heaters 3.2 1 X 010 Pressurizer Pressure Control A2.03 - Incorrect channel bypassing 3.4 1 X 012 Reactor Protection 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.
 
4.2 1 X 013 Engineered Safety Features Actuation K1.10 - CPS 2.8*1 X 013 Engineered Safety Features Actuation A4.01 - CCS fans 3.6 1 X 022 Containment Cooling A2.01 - Fan motor over-current 2.5 1 X 022 Containment Cooling K2.01 - Containment spray pumps 3.4*1 X 026 Containment Spray A3.02 - Isolation of the MRSS 3.1 1 X 039 Main and Reheat Steam A4.03 - Feedwater control during power increase and decrease 2.9*1 X 059 Main Feedwater K3.04 - RCS 3.6 1 X 059 Main Feedwater K1.11 - AFW turbine exhaust/drains 2.7 1 X 061 Auxiliary/Emergency Feedwater K3.03 - DC system 3.7 1 X 062 AC Electrical Distribution A1.01 - Battery capacity as it is affected by discharge rate 2.5 1 X 063 DC Electrical Distribution 1 11/12/2008 9:38:24 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
PWR RO Examination Outline                                          Printed:    11/12/2008 Facility:   Diablo Canyon Power Plant ES - 401                                       Plant Systems - Tier 2 / Group 2                                         Form ES-401-2 Sys/Evol # / Name                    K1 K2 K3  K4    K5  K6  A1    A2  A3  A4 G  KA Topic                          Imp. Points 001 Control Rod Drive                      X                                          K2.01 - One-line diagram of         3.5      1 power supply to M/G sets 011 Pressurizer Level Control                                                    X   A4.02 - Movement of the             3.4      1 pressure control valve, using manual controller 014 Rod Position Indication                                                        X 2.1.32 - Ability to explain         3.8      1 and apply system limits and precautions.
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
028 Hydrogen Recombiner and                            X                              K5.03 - Sources of hydrogen         2.9       1 Purge Control                                                                         within containment 033 Spent Fuel Pool Cooling                  X                                        K3.02 - Area and ventilation       2.8       1 radiation monitoring systems 034 Fuel Handling Equipment                                  X                         K6.02 - Radiation                   2.6       1 monitoring systems 035 Steam Generator                                                          X         A3.01 - S/G water level             4.0       1 control 071 Waste Gas Disposal                                            X                   A1.06 - Ventilation system         2.5       1 075 Circulating Water                            X                                   K4.01 - Heat sink                   2.5       1 079 Station Air                        X                                             K1.01 - IAS                         3.0       1 K/A Category Totals:   1  1  1  1    1    1     1     0  1   1 1                     Group Point Total:     10 11/12/2008         9:38:31 am                                                                                                 1
Diablo Canyon Power Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K3.01 - Systems controlled by automatic loader 3.8*1 X 064 Emergency Diesel Generator K5.01 - Radiation theory, including sources, types, units, and effects 2.5 1 X 073 Process Radiation Monitoring 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
 
4.5 1 X 076 Service Water K4.03 - Securing of SAS upon loss of cooling water 3.1*1 X 078 Instrument Air K4.01 - Vacuum breaker protection 3.0*1 X 103 Containment 28 3 2 3 1 3 3 K/A Category Totals:
Generic Knowledge and Abilities Outline (Tier 3)
3 3 2 2 3 Group Point Total:
PWR RO Examination Outline                                      Printed: 11/12/2008 Facility:  Diablo Canyon Power Plant                                                                          Form ES-401-3 Generic Category                            KA        KA Topic                                                  Imp. Points Conduct of Operations                        2.1.26 Knowledge of industrial safety procedures (such               3.4      1 as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
2 11/12/2008 9:38:24 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
2.1.39 Knowledge of conservative decision making                     3.6       1 practices.
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Category Total:                 2 Equipment Control                              2.2.2 Ability to manipulate the console controls as                 4.6      1 required to operate the facility between shutdown and designated power levels.
Diablo Canyon Power Plant PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 K2.01 - One-line diagram of power supply to M/G sets 3.5 1 X 001 Control Rod Drive A4.02 - Movement of the pressure control valve, using manual controller 3.4 1 X 011 Pressurizer Level Control 2.1.32 - Ability to explain and apply system limits and precautions.
2.2.6 Knowledge of the process for making changes to                 3.0       1 procedures.
3.8 1 X 014 Rod Position Indication K5.03 - Sources of hydrogen within containment 2.9 1 X 028 Hydrogen Recombiner and Purge Control K3.02 - Area and ventilation radiation monitoring systems 2.8 1 X 033 Spent Fuel Pool Cooling K6.02 - Radiation monitoring systems 2.6 1 X 034 Fuel Handling Equipment A3.01 - S/G water level control 4.0 1 X 035 Steam Generator A1.06 - Ventilation system 2.5 1 X 071 Waste Gas Disposal K4.01 - Heat sink 2.5 1 X 075 Circulating Water K1.01 - IAS 3.0 1 X 079 Station Air 10 1 1 1 1 0 1 K/A Category Totals:
2.2.13 Knowledge of tagging and clearance procedures.                 4.1       1 Category Total:                 3 Radiation Control                              2.3.4 Knowledge of radiation exposure limits under                   3.2      1 normal or emergency conditions.
1 1 1 1 1 Group Point Total:
2.3.13 Knowledge of radiological safety procedures                   3.4      1 pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
1 11/12/2008 9:38:31 am Facility: Diablo Canyon Power Plant Generic Category KA KA Topic Imp.Points Generic Knowledge and Abilities Outline (Tier 3)
2.3.14 Knowledge of radiation or contamination hazards               3.4      1 that may arise during normal, abnormal, or emergency conditions or activities.
Form ES-401-3 11/12/2008 Printed: PWR  RO  Examination Outline 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
Category Total:                 3 Emergency Procedures/Plan                    2.4.26 Knowledge of facility protection requirements,                 3.1      1 including fire brigade and portable fire fighting equipment usage.
3.4 1 Conduct of Operations 2.1.39 Knowledge of conservative decision making practices.
2.4.32 Knowledge of operator response to loss of all                 3.6       1 annunciators.
3.6 1 2 Category Total:
Category Total:                 2 Generic Total:                 10 11/12/2008         9:38:38 am                                                                                               1
2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
 
4.6 1 Equipment Control 2.2.6 Knowledge of the process for making changes to procedures.
ES-401                                             PWR Examination Outline                                             Form ES-401-2 Facility:      Diablo Canyon Power Plant                                                                        Printed: 11/12/2008 Date Of Exam:          02/06/2009 RO K/A Category Points                                                SRO-Only Points Tier      Group K1        K2  K3    K4    K5    K6 A1      A2  A3    A4 G* Total                  A2        G*    Total
3.0 1 2.2.13 Knowledge of tagging and clearance procedures.
: 1.          1      0     0   0                     0     0                 0     0             3          3        6 Emergency 2      0     0   0                     0     0                 0     0             2          2        4
4.1 1 3 Category Total:
      &                                          N/A                      N/A Abnormal Tier Plant Totals    0     0   0                     0     0                 0     0             5          5        10 Evolutions 1      0     0   0     0     0     0   0     0   0     0   0       0             3          2        5 2.
2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
2      0      0    0    0    0    0    0      0    0      0    0      0        1      1        1       3 Plant Systems          Tier                                                                                       5          3        8 0      0    0    0    0    0    0      0    0      0    0      0 Totals 1          2           3            4                1     2   3     4
3.2 1 Radiation Control 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
: 3. Generic Knowledge And 0                                  7 Abilities Categories 0          0          0            0                2      1  2      2 Note:
3.4 1 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
: 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).
3.4 1 3 Category Total:
: 2. The point total for each group and tier in the proposed outline must match that specified in the table.
2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.
3.1 1 Emergency Procedures/Plan 2.4.32 Knowledge of operator response to loss of all annunciators.
3.6 1 2 Category Total:
10 Generic Total:
1 11/12/2008 9:38:38 am 11/12/2008 Printed: ES-401 Facility: Diablo Canyon Power Plant PWR Examination Outline Form ES-401-2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 RO K/A  Category  Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*1.Emergency&Abnormal Plant Evolutions 1 1 2 2 Tier Totals Tier Totals 2.Plant Systems 1 2 3 4 3. Generic Knowledge And Abilities Categories 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.
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.
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.
: 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.
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.
: 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.
Note: Date Of Exam:
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
02/06/2009 0 0 0 0 0 0 0 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).
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.
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 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.
: 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.
SRO-Only  Points A2 G* 3 3 2 2 5 5 3 2 1 1 3 2 1 2 2 1 2 3 4 10 4 6 5 3 8 7 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.
: 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.
Limit SRO selections to K/As that are linked to 10 CFR 55.43.
11/12/2008             9:45:28 am                                                                                                   1
6.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
 
N/A N/A Total 1 5 1 11/12/2008 9:45:28 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
PWR SRO Examination Outline                                      Printed:    11/12/2008 Facility:   Diablo Canyon Power Plant ES - 401                                Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1                               Form ES-401-2 E/APE # / Name / Safety Function                K1  K2  K3 A1 A2      G      KA Topic                                      Imp.      Points 000007 Reactor Trip - Stabilization -                              X        EA2.06 - Occurrence of a reactor trip               4.5       1 Recovery / 1 000026 Loss of Component Cooling Water /                                X    2.2.36 - Ability to analyze the effect of           4.2        1 8                                                                            maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
ES - 401 Facility: Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 EA2.06 - Occurrence of a reactor trip 4.5 1 X 000007 Reactor Trip - Stabilization -
000055 Station Blackout / 6                                              X   2.4.4 - Ability to recognize abnormal               4.7        1 indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
Recovery / 1 2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
000056 Loss of Off-site Power / 6                                       X    2.4.6 - Knowledge of EOP mitigation                 4.7       1 strategies.
4.2 1 X 000026 Loss of Component Cooling Water /
000077 Generator Voltage and Electric Grid                          X         AA2.10 - Generator overheating and the             3.8       1 Disturbances / 6                                                             required actions W/E11 Loss of Emergency Coolant Recirc. /                          X        EA2.2 - Adherence to appropriate                   4.2        1 4                                                                            procedures and operation within the limitations in the facility's license and amendments K/A Category Totals:    0   0   0   0   3   3                                         Group Point Total:       6 11/12/2008         9:44:58 am                                                                                                                 1
8 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
 
4.7 1 X 000055 Station Blackout / 6 2.4.6 - Knowledge of EOP mitigation strategies.
PWR SRO Examination Outline                                      Printed:    11/12/2008 Facility:   Diablo Canyon Power Plant ES - 401                                Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2                               Form ES-401-2 E/APE # / Name / Safety Function                K1  K2  K3 A1 A2      G      KA Topic                                      Imp.      Points 000024 Emergency Boration / 1                                            X    2.4.11 - Knowledge of abnormal                     4.2        1 condition procedures.
4.7 1 X 000056 Loss of Off-site Power / 6 AA2.10 - Generator overheating and the required actions 3.8 1 X 000077 Generator Voltage and Electric Grid Disturbances / 6 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 4.2 1 X W/E11 Loss of Emergency Coolant Recirc. /
000076 High Reactor Coolant Activity / 9                                X   2.2.38 - Knowledge of conditions and               4.5        1 limitations in the facility license.
4 6 0 0 0 0 3 3 K/A Category Totals:
W/E01 Rediagnosis / 3                                              X         EA2.2 - Adherence to appropriate                   3.9        1 procedures and operation within the limitations in the facility's license and amendments W/E07 Inad. Core Cooling / 4                                        X        EA2.2 - Adherence to appropriate                   3.9        1 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals:    0   0   0   0   2   2                                         Group Point Total:       4 11/12/2008         9:45:04 am                                                                                                                   1
Group Point Total:
 
1 11/12/2008 9:44:58 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
PWR SRO Examination Outline                                          Printed:    11/12/2008 Facility:   Diablo Canyon Power Plant ES - 401                                        Plant Systems - Tier 2 / Group 1                                           Form ES-401-2 Sys/Evol # / Name                    K1 K2 K3  K4    K5  K6  A1    A2  A3  A4 G  KA Topic                            Imp. Points 003 Reactor Coolant Pump                                                X            A2.01 - Problems with RCP             3.9      1 seals, especially rates of seal leak-off 007 Pressurizer Relief/Quench                                            X             A2.02 - Abnormal pressure             3.2     1 Tank                                                                                  in the PRT 012 Reactor Protection                                                              X 2.2.38 - Knowledge of                 4.5      1 conditions and limitations in the facility license.
ES - 401 Facility: Diablo Canyon Power Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 2.4.11 - Knowledge of abnormal condition procedures.
059 Main Feedwater                                                                  X 2.2.38 - Knowledge of                 4.5      1 conditions and limitations in the facility license.
4.2 1 X 000024 Emergency Boration / 1 2.2.38 - Knowledge of conditions and limitations in the facility license.
061 Auxiliary/Emergency                                                  X             A2.03 - Loss of dc power             3.4     1 Feedwater K/A Category Totals:   0  0  0  0    0   0     0     3  0   0 2                      Group Point Total:       5 11/12/2008           9:45:10 am                                                                                                 1
4.5 1 X 000076 High Reactor Coolant Activity / 9 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.9 1 X W/E01 Rediagnosis / 3 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.9 1 X W/E07 Inad. Core Cooling / 4 4 0 0 0 0 2 2 K/A Category Totals:
 
Group Point Total:
PWR SRO Examination Outline                                      Printed:    11/12/2008 Facility:   Diablo Canyon Power Plant ES - 401                                        Plant Systems - Tier 2 / Group 2                                       Form ES-401-2 Sys/Evol # / Name                    K1 K2 K3  K4    K5  K6  A1    A2  A3  A4 G  KA Topic                        Imp. Points 034 Fuel Handling Equipment                                      X                    A1.01 - Load limits               3.2     1 041 Steam Dump/Turbine Bypass                                            X             A2.02 - Steam valve stuck         3.9     1 Control                                                                                open 055 Condenser Air Removal                                                          X 2.4.11 - Knowledge of             4.2      1 abnormal condition procedures.
1 11/12/2008 9:45:04 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
K/A Category Totals:   0  0  0  0     0   0     1    1  0   0 1                    Group Point Total:     3 11/12/2008         9:45:16 am                                                                                               1
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
 
Diablo Canyon Power Plant PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.01 - Problems with RCP seals, especially rates of seal leak-off 3.9 1 X 003 Reactor Coolant Pump A2.02 - Abnormal pressure in the PRT 3.2 1 X 007 Pressurizer Relief/Quench Tank 2.2.38 - Knowledge of conditions and limitations in the facility license.
Generic Knowledge and Abilities Outline (Tier 3)
4.5 1 X 012 Reactor Protection 2.2.38 - Knowledge of conditions and limitations in the facility license.
PWR SRO Examination Outline                                      Printed: 11/12/2008 Facility:  Diablo Canyon Power Plant                                                                          Form ES-401-3 Generic Category                              KA        KA Topic                                                  Imp. Points Conduct of Operations                          2.1.13 Knowledge of facility requirements for                         3.2      1 controlling vital / controlled access.
4.5 1 X 059 Main Feedwater A2.03 - Loss of dc power 3.4 1 X 061 Auxiliary/Emergency Feedwater 5 0 0 0 0 3 2 K/A Category Totals:
2.1.14 Knowledge of criteria or conditions that require               3.1      1 plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.
0 0 0 0 0 Group Point Total:
Category Total:                 2 Equipment Control                              2.2.15 Ability to determine the expected plant                       4.3      1 configuration using design and configuration control documentation, such as drawings, line-ups, tagouts, etc.
1 11/12/2008 9:45:10 am 11/12/2008 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:
Category Total:                 1 Radiation Control                              2.3.11 Ability to control radiation releases.                         4.3       1 2.3.15 Knowledge of radiation monitoring systems, such               3.1      1 as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:
Category Total:                 2 Emergency Procedures/Plan                      2.4.21 Knowledge of the parameters and logic used to                 4.6      1 assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
Diablo Canyon Power Plant PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A1.01 - Load limits 3.2 1 X 034 Fuel Handling Equipment A2.02 - Steam valve stuck open 3.9 1 X 041 Steam Dump/Turbine Bypass Control 2.4.11 - Knowledge of abnormal condition procedures.
2.4.47 Ability to diagnose and recognize trends in an                 4.2      1 accurate and timely manner utilizing the appropriate control room reference material.
4.2 1 X 055 Condenser Air Removal 3 0 0 0 1 1 1 K/A Category Totals:
Category Total:                 2 Generic Total:                 7 11/12/2008         9:45:23 am                                                                                               1
0 0 0 0 0 Group Point Total:
 
1 11/12/2008 9:45:16 am Facility: Diablo Canyon Power Plant Generic Category KA KA Topic Imp.Points Generic Knowledge and Abilities Outline (Tier 3)
ES-401                       Record of Rejected K/As                                        Form ES-401-4   l Tier /     Randomly                                  Reason for Rejection Group     Selected K/A RO-T2/G1    061 K2.03    KA is knowledge of the power supply to AFW diesel driven pump.
Form ES-401-3 11/12/2008 Printed: PWR  SRO  Examination Outline 2.1.13 Knowledge of facility requirements for controlling vital / controlled access.
This is not applicable at DCPP Replaced with 061 K1.11 interrelationship between AFW/Turbine exh/drains, IR 2.7 RO-T2/G1    076 A1.02    KA is to predict and monitor changes in reactor and turbine building closed cooling water temperatures.
3.2 1 Conduct of Operations 2.1.14 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.
At DCPP, Service Water is ASW which is not supplied to either building. It only supplies cooling to CCW.
3.1 1 2 Category Total:
Replaced with 008 K2.02- Power to pumps, including emergency B/U IR 3.0*
2.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tagouts, etc.
SRO -    W/E12 G2.4.1  KA tests knowledge of EOP entry conditions and immediate actions. There are no T1/G1                  immediate actions in the Steam Line Rupture (E-2) EOP.
4.3 1 Equipment Control 1 Category Total:
Replaced with APE 056 2.4.6 - EOP mitigation strategies IR 4.7 SRO  APE 005 G2.4.20 knowledge of eop warning, notes, cautions, for stuck rod, T1/G2                  not testable at SRO level. replaced with APE 076 G2.2.38 RO T1G1  APE 017G2.2.38  This is a Tech Spec KA, for RCPs there are no Tech Specs (ie <1hr) that are RO knowledge . Replaced with EPE055.G2.1.31 RO T1G2  APE 003AK1.17  theory KA that is not site specific and category 1. Replaced with E14.EK2.2 ES-401, Page 27 of 33}}
2.3.11 Ability to control radiation releases.
4.3 1 Radiation Control 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
3.1 1 2 Category Total:
2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
4.6 1 Emergency Procedures/Plan 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
4.2 1 2 Category Total:
7 Generic Total:
1 11/12/2008 9:45:23 am ES-401, Page 27 of 33ES-401Record of Rejected K/AsForm ES-401-4 lTier /Group Randomly Selected K/A Reason for Rejection}}

Latest revision as of 08:55, 14 November 2019

DC-2009-02-Draft Outlines
ML090790307
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 02/06/2009
From: Brian Larson
Operations Branch IV
To:
References
Download: ML090790307 (26)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Diablo Canyon Facility: _______________________________ 02/09/09 Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: __________L061C Administrative Topic Type Describe activity to be performed (see Note) Code*

Determination of SFP Heat Load Removal Parameters (LJACO-01R)

Conduct of Operations D, R G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation. (4.4)

Review Outage Safety Checklist (NRC ADM02SRO - L031)

Conduct of Operations D, R G2.1.40 - Knowledge of refueling administrative requirements. (3.9)

Verify AFD is within Tech Spec Limits (LJAEC - 11S)

Equipment Control D, R G2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications. (4.6)

Review Liquid Radwaste Discharge checklist N, R G2.3.6 - Ability to approve release permits. (3.8)

Radiation Control Offsite Dose Assessment and classification - FHB Accident (LJC-166)

D, R l Emergency Procedures/Plan G2.4.41 - Knowledge of the emergency action level thresholds and classifications. (4.6)

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

ES-301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Diablo Canyon Facility: _____________________________ 02/09/09 Date of Examination: ______________

Exam Level: RO SRO-I SRO-U L061C Operating Test No.: _______________

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. S1 - 004/Isolate VCT Rupture (LJC-005) M,A,E,S 02
b. S2 - 010/Respond to PT-456 failed high (LJC-143) D,S 03
c. S3 - 005/Isolate LOCA outside containment (LJC-118) D,A,E,S 04p
d. S4 - 103/Manually isolate CVI components N,A,E,S 05
e. S5 - 008/Loss of CCW to one RCP (L031 NRC test) D,A,E,S 08
f. S6 - 041/RCS cooldown for SGTR (LJC-090) D,A,E,S 04s
g. S7 - 073/Verify RM-44A OPERABLE N,S 07 h.

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

i. P1 - 062/Transfer pressurizer heater group 12 to backup (LJP-029) D,L,E 06
j. P2 - 004/Align CCP suction to RWST (LJP-207, modified for Unit 2) M,E,L,R 02
k. P3 - 012/De-energize SSPS to block SI (LJP-09S) D,L 07

@ 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-I / SRO-U l (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank #9/#8/#4 (E)mergency or abnormal in-plant $1/$1/$1 (EN)gineered safety feature - / - / $1 (control room system) l (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 (S)imulator ES-301, Page 23 of 27

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Date of Exam: Operating Test No.:

A E Scenarios P V 1 2 3 4 T M P E O I L N CREW CREW CREW CREW T N I T POSITION POSITION POSITION POSITION A I

M C S A B S A B S A B S A B L U A T R T O R T O R T O R T O M(*)

N Y O C P O C P O C P O C P R I U T P E

RO RX 2 1 1 1 0 NOR 3 1 1 1 1 SRO-I I/C 3,4, 5 1-3,6 3,4,7,8 11 4 4 2 SRO-U MAJ 7 4 6 3 2 2 1 TS 3,4 2 0 2 2 RO RX 2 1 1 1 0 NOR 1 3 2 1 1 1 SRO-I I/C 3,4,5 1,2,5 1,3-5 10 4 4 2 SRO-U MAJ 7 4 6 3 2 2 1 TS 3,4 2 0 2 2 RO RX 2 1 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 3,4,5 1,2,3 1,3,5 9 4 4 2 SRO-U MAJ 7 4 6 3 2 2 1 TS 1,3 2 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 1 Op-Test No.: L061C-1 Examiners: Operators:

Initial Conditions: 100% Reactor power, BOL, Boron at 1182 ppm CFCU 1-2 cleared.

Turnover: High Swell warning is expected in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ODM has decided to ramp both units to 25% power at 3 MW/min. OP O-28 actions are complete. OP L-4 preparations are done, at step 6.3.3.m. Turn Pzr Backup heaters on and commence ramp.

Event Malf. No. Event Event Description and Time Line No. Type*

1 N Turn Pzr Backup Heaters ON.

2 R Ramp unit to 25% power.

3 Xmt rcs15 I Loop 1 narrow range Tcold fails high and causes rods to step in. (TS 3.3.1.E & X and 3.3.2.M) 4 Pmp ven C CFCU 11 overcurrent trip. (TS 3.6.6.C )

5 Cnv mfw6 C FCV-540 FW reg valve to S/G 14 fails open 6 mal tur1 C No Automatic turbine trip, must trip manually. (CT) 7 mal rcs3a M Small break LOCA (4) 3 minutes after turbine trip. Will require RCP Trip criteria.(CT) 8 Mal eps C 4KV Bus G differential trip on Safety Injection.

9 pmp cvc1 C Charging pump 11 doesnt auto start. (CT)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario 1.doc Rev. 0

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 2 Op-Test No.: L061C-2 Examiners: Operators:

Initial Conditions: 75% Reactor power, MOL, Boron at 848 ppm ASW pp 12 cleared.

Turnover:

Event Malf. No. Event Event Description and Time Line No. Type*

1 Vlv pzr5 C PCV-456 Pzr PORV fails open, must isolate using block valve. (TS 3.4.11 )

(CT) 2 Mal R - CO Ramp unit to 50% power due to FWP 11 high vibration.

mfw2a C - BO 3 Xmt mfw37 I LT-459 Pzr level channel fails to 10% (TS 3.3.1.M, 3.3.3.F, 3.3.4)

N - CO Restores letdown flow.

N -BOP 4 Mal rcs4c M S/G 13 tube leak ramps to 400 gpm (CT) 5 Pmp asw1 C ASW pp 11 trips on overcurrent on reactor trip, requires x-tie with U-2. (CT) 6 Cnv mss C PCV-21 fails open after RCS cooldown complete. Transition to ECA 3.1

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario 2.doc Rev. 0

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Diablo Canyon Scenario No.: 3 Op-Test No.: L061C-3 Examiners: Operators:

Initial Conditions: 100% Power, MOL, 782 ppm CB Turnover: PRA Status: Yellow. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. RHR pp 11 is cleared for seal repair. U-2 at 100% power.

Event Malf. No. Event Event Description and Time Line No. Type*

1 mal cvc8 C RCP seal injection filter plugs up, reducing charging flow to seals.

2 R TOC requests ramp to 900 MW at 25 MW/min 3 xmt rcs93 I NI-44 fails high, requires rods to manual. ( TS 3.3.1.D, E, S, T) 4 mal eps4c C 4KV bus F diff trip (TS 3.0.3 due to loss of both RHR pumps )

5 mal mfw2a C Both MFW pumps trip spuriously.

mal mfw2b 6 mal ppl5a M Reactor trip breakers wont open from the control room. ATWS. (CT) mal ppl5b 7 ovr C 52-hd-13 fdr for bus 13d fails to open, so 1 MG set stays in service. Crew must xv5i245o insert rods and go to FR S.1. (CT) 8 vlv afw7 C TDAFW pp 11 fcv-95 won't open automatically, crew must open at VB3. (CT)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L061C Scenario 3.doc Rev. 0

ES-401 PWR Examination Outline Form ES-401-2 Facility: Diablo Canyon Power Plant Printed: 11/12/2008 Date Of Exam: 02/06/2009 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 0 0 0 Emergency 2 1 2 2 1 1 2 9 0 0 0

& N/A N/A Abnormal Tier Plant Totals 4 5 5 4 4 5 27 0 0 0 Evolutions 1 3 2 3 3 3 2 1 3 2 3 3 28 0 0 0 2.

2 1 1 1 1 1 1 1 0 1 1 1 10 0 0 0 0 Plant Systems Tier 0 0 0 4 3 4 4 4 3 2 3 3 4 4 38 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 10 0 Abilities Categories 2 3 3 2 0 0 0 0 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 (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 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.

11/12/2008 9:31:49 am 1

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident / X AK1.02 - Change in leak rate with 3.1 1 3 change in pressure 000009 Small Break LOCA / 3 X EA2.12 - Charging pump ammeter 2.8 1 000011 Large Break LOCA / 3 X EA1.03 - Securing of RCPs 4.0 1 000022 Loss of Rx Coolant Makeup / 2 X AK1.03 - Relationship between 3.0 1 charging flow and PZR level 000025 Loss of RHR System / 4 X AA2.07 - Pump cavitation 3.4 1 000027 Pressurizer Pressure Control System X AK2.03 - Controllers and positioners 2.6 1 Malfunction / 3 000029 ATWS / 1 X EK2.06 - Breakers, relays, and 2.9* 1 disconnects 000038 Steam Gen. Tube Rupture / 3 X EK1.01 - Use of steam tables 3.1 1 000040 Steam Line Rupture - Excessive X AK2.02 - Sensors and detectors 2.6* 1 Heat Transfer / 4 000054 Loss of Main Feedwater / 4 X AA1.01 - AFW controls, including the 4.5 1 use of alternate AFW sources 000055 Station Blackout / 6 X 2.1.31 - Ability to locate control room 4.6 1 switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

000056 Loss of Off-site Power / 6 X AA2.19 - T-cold and T-hot indicators 4.0 1 (wide range) 000057 Loss of Vital AC Inst. Bus / 6 X 2.4.20 - Knowledge of operational 3.8 1 implications of EOP warnings, cautions, and notes.

000058 Loss of DC Power / 6 X AA1.02 - Static inverter dc input 3.1* 1 breaker, frequency meter, ac output breaker, and ground fault detector 000062 Loss of Nuclear Svc Water / 4 X AK3.02 - The automatic actions 3.6 1 (alignments) within the nuclear service water resulting from the actuation of the ESFAS 000065 Loss of Instrument Air / 8 X 2.4.47 - Ability to diagnose and 4.2 1 recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

W/E04 LOCA Outside Containment / 3 X EK3.4 - RO or SRO function within the 3.6 1 control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated 11/12/2008 9:38:08 am 1

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points W/E05 Inadequate Heat Transfer - Loss of X EK3.2 - Normal, abnormal and 3.7 1 Secondary Heat Sink / 4 emergency operating procedures associated with Loss of Secondary Heat Sink K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 11/12/2008 9:38:08 am 2

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000032 Loss of Source Range NI / 7 X AK3.01 - Startup termination on 3.2 1 source-range loss 000033 Loss of Intermediate Range NI / 7 X AA2.01 - Equivalency between 3.0 1 source-range, intermediate-range, and power-range channel readings 000036 Fuel Handling Accident / 8 X AK1.02 - SDM 3.4 1 000059 Accidental Liquid RadWaste Rel. / X 2.2.22 - Knowledge of limiting 4.0 1 9 conditions for operations and safety limits.

000060 Accidental Gaseous Radwaste Rel. / X 2.4.50 - Ability to verify system alarm 4.2 1 9 setpoints and operate controls identified in the alarm response manual.

000074 Inad. Core Cooling / 4 X EK3.04 - Tripping RCPs 3.9 1 W/E08 RCS Overcooling - PTS / 4 X EK2.2 - Facility's heat removal systems, 3.6 1 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility W/E13 Steam Generator Over-pressure / 4 X EA1.1 - Components, and functions of 3.1 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features W/E14 Loss of CTMT Integrity / 5 X EK2.2 - Facility's heat removal systems, 3.4 1 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility K/A Category Totals: 1 2 2 1 1 2 Group Point Total: 9 11/12/2008 9:38:15 am 1

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X K1.08 - Containment 2.7* 1 isolation 004 Chemical and Volume Control X A3.03 - Ion exchange 2.9 1 bypass 004 Chemical and Volume Control X K5.11 - Thermal stress, 3.6 1 brittle fracture, pressurized thermal shock 005 Residual Heat Removal X K5.02 - Need for adequate 3.4 1 subcooling 006 Emergency Core Cooling X 2.1.30 - Ability to locate and 4.4 1 operate components, including local controls.

006 Emergency Core Cooling X K6.13 - Pumps 2.8 1 007 Pressurizer Relief/Quench X K4.01 - Quench tank 2.6 1 Tank cooling 008 Component Cooling Water X A2.02 - High/low surge tank 3.2 1 level 008 Component Cooling Water X K2.02 - CCW pump, 3.0* 1 including emergency backup 010 Pressurizer Pressure Control X A4.01 - PZR spray valve 3.7 1 010 Pressurizer Pressure Control X K6.03 - PZR sprays and 3.2 1 heaters 012 Reactor Protection X A2.03 - Incorrect channel 3.4 1 bypassing 013 Engineered Safety Features X 2.4.31 - Knowledge of 4.2 1 Actuation annunciator alarms, indications, or response procedures.

013 Engineered Safety Features X K1.10 - CPS 2.8* 1 Actuation 022 Containment Cooling X A4.01 - CCS fans 3.6 1 022 Containment Cooling X A2.01 - Fan motor 2.5 1 over-current 026 Containment Spray X K2.01 - Containment spray 3.4* 1 pumps 039 Main and Reheat Steam X A3.02 - Isolation of the 3.1 1 MRSS 059 Main Feedwater X A4.03 - Feedwater control 2.9* 1 during power increase and decrease 059 Main Feedwater X K3.04 - RCS 3.6 1 061 Auxiliary/Emergency X K1.11 - AFW turbine 2.7 1 Feedwater exhaust/drains 062 AC Electrical Distribution X K3.03 - DC system 3.7 1 063 DC Electrical Distribution X A1.01 - Battery capacity as 2.5 1 it is affected by discharge rate 11/12/2008 9:38:24 am 1

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 064 Emergency Diesel Generator X K3.01 - Systems controlled 3.8* 1 by automatic loader 073 Process Radiation Monitoring X K5.01 - Radiation theory, 2.5 1 including sources, types, units, and effects 076 Service Water X 2.4.4 - Ability to recognize 4.5 1 abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

078 Instrument Air X K4.03 - Securing of SAS 3.1* 1 upon loss of cooling water 103 Containment X K4.01 - Vacuum breaker 3.0* 1 protection K/A Category Totals: 3 2 3 3 3 2 1 3 2 3 3 Group Point Total: 28 11/12/2008 9:38:24 am 2

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X K2.01 - One-line diagram of 3.5 1 power supply to M/G sets 011 Pressurizer Level Control X A4.02 - Movement of the 3.4 1 pressure control valve, using manual controller 014 Rod Position Indication X 2.1.32 - Ability to explain 3.8 1 and apply system limits and precautions.

028 Hydrogen Recombiner and X K5.03 - Sources of hydrogen 2.9 1 Purge Control within containment 033 Spent Fuel Pool Cooling X K3.02 - Area and ventilation 2.8 1 radiation monitoring systems 034 Fuel Handling Equipment X K6.02 - Radiation 2.6 1 monitoring systems 035 Steam Generator X A3.01 - S/G water level 4.0 1 control 071 Waste Gas Disposal X A1.06 - Ventilation system 2.5 1 075 Circulating Water X K4.01 - Heat sink 2.5 1 079 Station Air X K1.01 - IAS 3.0 1 K/A Category Totals: 1 1 1 1 1 1 1 0 1 1 1 Group Point Total: 10 11/12/2008 9:38:31 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.26 Knowledge of industrial safety procedures (such 3.4 1 as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.1.39 Knowledge of conservative decision making 3.6 1 practices.

Category Total: 2 Equipment Control 2.2.2 Ability to manipulate the console controls as 4.6 1 required to operate the facility between shutdown and designated power levels.

2.2.6 Knowledge of the process for making changes to 3.0 1 procedures.

2.2.13 Knowledge of tagging and clearance procedures. 4.1 1 Category Total: 3 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 1 normal or emergency conditions.

2.3.13 Knowledge of radiological safety procedures 3.4 1 pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.14 Knowledge of radiation or contamination hazards 3.4 1 that may arise during normal, abnormal, or emergency conditions or activities.

Category Total: 3 Emergency Procedures/Plan 2.4.26 Knowledge of facility protection requirements, 3.1 1 including fire brigade and portable fire fighting equipment usage.

2.4.32 Knowledge of operator response to loss of all 3.6 1 annunciators.

Category Total: 2 Generic Total: 10 11/12/2008 9:38:38 am 1

ES-401 PWR Examination Outline Form ES-401-2 Facility: Diablo Canyon Power Plant Printed: 11/12/2008 Date Of Exam: 02/06/2009 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 3 3 6 Emergency 2 0 0 0 0 0 0 0 2 2 4

& N/A N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

2 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 3 Plant Systems Tier 5 3 8 0 0 0 0 0 0 0 0 0 0 0 0 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 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 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 (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 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.

11/12/2008 9:45:28 am 1

PWR SRO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000007 Reactor Trip - Stabilization - X EA2.06 - Occurrence of a reactor trip 4.5 1 Recovery / 1 000026 Loss of Component Cooling Water / X 2.2.36 - Ability to analyze the effect of 4.2 1 8 maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

000055 Station Blackout / 6 X 2.4.4 - Ability to recognize abnormal 4.7 1 indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

000056 Loss of Off-site Power / 6 X 2.4.6 - Knowledge of EOP mitigation 4.7 1 strategies.

000077 Generator Voltage and Electric Grid X AA2.10 - Generator overheating and the 3.8 1 Disturbances / 6 required actions W/E11 Loss of Emergency Coolant Recirc. / X EA2.2 - Adherence to appropriate 4.2 1 4 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 11/12/2008 9:44:58 am 1

PWR SRO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000024 Emergency Boration / 1 X 2.4.11 - Knowledge of abnormal 4.2 1 condition procedures.

000076 High Reactor Coolant Activity / 9 X 2.2.38 - Knowledge of conditions and 4.5 1 limitations in the facility license.

W/E01 Rediagnosis / 3 X EA2.2 - Adherence to appropriate 3.9 1 procedures and operation within the limitations in the facility's license and amendments W/E07 Inad. Core Cooling / 4 X EA2.2 - Adherence to appropriate 3.9 1 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 11/12/2008 9:45:04 am 1

PWR SRO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X A2.01 - Problems with RCP 3.9 1 seals, especially rates of seal leak-off 007 Pressurizer Relief/Quench X A2.02 - Abnormal pressure 3.2 1 Tank in the PRT 012 Reactor Protection X 2.2.38 - Knowledge of 4.5 1 conditions and limitations in the facility license.

059 Main Feedwater X 2.2.38 - Knowledge of 4.5 1 conditions and limitations in the facility license.

061 Auxiliary/Emergency X A2.03 - Loss of dc power 3.4 1 Feedwater K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 11/12/2008 9:45:10 am 1

PWR SRO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 034 Fuel Handling Equipment X A1.01 - Load limits 3.2 1 041 Steam Dump/Turbine Bypass X A2.02 - Steam valve stuck 3.9 1 Control open 055 Condenser Air Removal X 2.4.11 - Knowledge of 4.2 1 abnormal condition procedures.

K/A Category Totals: 0 0 0 0 0 0 1 1 0 0 1 Group Point Total: 3 11/12/2008 9:45:16 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 11/12/2008 Facility: Diablo Canyon Power Plant Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.13 Knowledge of facility requirements for 3.2 1 controlling vital / controlled access.

2.1.14 Knowledge of criteria or conditions that require 3.1 1 plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

Category Total: 2 Equipment Control 2.2.15 Ability to determine the expected plant 4.3 1 configuration using design and configuration control documentation, such as drawings, line-ups, tagouts, etc.

Category Total: 1 Radiation Control 2.3.11 Ability to control radiation releases. 4.3 1 2.3.15 Knowledge of radiation monitoring systems, such 3.1 1 as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Category Total: 2 Emergency Procedures/Plan 2.4.21 Knowledge of the parameters and logic used to 4.6 1 assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

2.4.47 Ability to diagnose and recognize trends in an 4.2 1 accurate and timely manner utilizing the appropriate control room reference material.

Category Total: 2 Generic Total: 7 11/12/2008 9:45:23 am 1

ES-401 Record of Rejected K/As Form ES-401-4 l Tier / Randomly Reason for Rejection Group Selected K/A RO-T2/G1 061 K2.03 KA is knowledge of the power supply to AFW diesel driven pump.

This is not applicable at DCPP Replaced with 061 K1.11 interrelationship between AFW/Turbine exh/drains, IR 2.7 RO-T2/G1 076 A1.02 KA is to predict and monitor changes in reactor and turbine building closed cooling water temperatures.

At DCPP, Service Water is ASW which is not supplied to either building. It only supplies cooling to CCW.

Replaced with 008 K2.02- Power to pumps, including emergency B/U IR 3.0*

SRO - W/E12 G2.4.1 KA tests knowledge of EOP entry conditions and immediate actions. There are no T1/G1 immediate actions in the Steam Line Rupture (E-2) EOP.

Replaced with APE 056 2.4.6 - EOP mitigation strategies IR 4.7 SRO APE 005 G2.4.20 knowledge of eop warning, notes, cautions, for stuck rod, T1/G2 not testable at SRO level. replaced with APE 076 G2.2.38 RO T1G1 APE 017G2.2.38 This is a Tech Spec KA, for RCPs there are no Tech Specs (ie <1hr) that are RO knowledge . Replaced with EPE055.G2.1.31 RO T1G2 APE 003AK1.17 theory KA that is not site specific and category 1. Replaced with E14.EK2.2 ES-401, Page 27 of 33

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