ML082830424

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DC-2008-06 - Final Operating Test Outlines
ML082830424
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 06/27/2008
From: Ryan Lantz
Operations Branch IV
To: Keenan J
Pacific Gas & Electric Co
References
50-275/08-301, 50-323/08-301
Download: ML082830424 (11)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Diablo Canyon____________

Date of Examination: __6/16/08_____

Examination Level: RO SRO Operating Test Number: ___1______

Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations 2.1.7 - 4.4 R,N Determine if Channel Check Criteria is Met Conduct of Operations 2.1.5 - 2.9 R,N Application of Overtime Restrictions Equipment Control 2.2.13 - 4.1 R,N Determine Clearance Boundaries and Tagging Requirements Radiation Control 2.3.4 - 3.2 R,N Stay Time Determination Emergency Procedures/Plan N/A N/A 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 Administrative Topics Outline Form ES-301-1 Facility: ___Diablo Canyon____________

Date of Examination: __6/16/08_____

Examination Level: RO SRO Operating Test Number: ___1______

Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations 2.1.5 - 3.9 R,N Determination of Shift Staffing and Overtime Restrictions Conduct of Operations 2.1.40 - 3.9 R,N Approve Movement of Spent Fuel Assemblies Equipment Control 2.2.13 - 4.3 R,N Evaluate Clearance Boundaries and Tagging Requirements Radiation Control 2.3.6 - 3.8 R,N Authorize Gas Decay Tank Discharge Emergency Procedures/Plan 2.4.41 - 4.6 R,N Classify an Earthquake with a Radiation Release 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 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _Diablo Canyon____________________

Date of Examination: _06/16/08_____

Exam Level: RO SRO-I SRO-U Operating Test No.: ____1_________

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. 006/ Increase Accumulator Pressure - LJC-077 - Modified A,EN,M,S 3
b. 007/ Respond to High Pressurizer Relief Tank Pressure - NEW N,S 5
c. 001/ Verify Misaligned Rod is Not Struck - LJC-066 D,S 1
d. 056/ Respond to a Load Transient Bypass - LJC-089 A,D,S 4S
e. 012/ Actions for Reactor Trip caused by a Loss of All AC Power -

LJC-115 A,D,S 7

f. 062/ Restoration of Buses after Loss of Offsite Power - LJC-210 D,S 6
g. 008/ Respond to a Loss of CCW Flow to the RCPs - LJC-127 A,D,S 8
h. 035/ Isolate a Ruptured Steam Generator 1 LJC-031 A,D,S 4P In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. 064/ Perform a Local Start of a Diesel Generator - LJP-038 A,D,E,L 6
j. 039/ Close Main Steam Isolation Valve Locally - LJP-008 D,E,L 4S
k. 004/ Establish Backup Cooling to a Centrifugal Charging Pump -

LJP-130 D,E,L,R 2

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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (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) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _Diablo Canyon____________________

Date of Examination: _06/16/08_____

Exam Level: RO SRO-I SRO-U Operating Test No.: ____1_________

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. 006/ Increase Accumulator Pressure - LJC-077 - Modified A,EN,M,S 3
b. 007/ Respond to High Pressurizer Relief Tank Pressure - NEW N,S 5
c. 001/ Verify Misaligned Rod is Not Struck - LJC-066 D,S 1
d. 056/ Respond to a Load Transient Bypass - LJC-089 A,D,S 4S
e. 012/ Actions for Reactor Trip caused by a Loss of All AC Power -

LJC-115 A,D,S 7

f. 062/ Restoration of Buses after Loss of Offsite Power - LJC-210 D,S 6
g. 008/ Respond to a Loss of CCW Flow to the RCPs - LJC-127 A,D,S 8
h.

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

i. 064/ Perform a Local Start of a Diesel Generator - LJP-038 A,D,E,L 6
j. 039/ Close Main Steam Isolation Valve Locally - LJP-008 D,E,L 4S
k. 004/ Establish Backup Cooling to a Centrifical Charging Pump -

LJP-130 D,E,L,R 2

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

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (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) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _Diablo Canyon____________________

Date of Examination: _06/16/08_____

Exam Level: RO SRO-I SRO-U Operating Test No.: ____1_________

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. 006/ Increase Accumulator Pressure - LJC-077 - Modified A,EN,M,S 3
b. 007/ Respond to High Pressurizer Relief Tank Pressure - NEW N,S 5
c.
d.
e.
f.
g.
h.

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

i. 064/ Perform a Local Start of a Diesel Generator - LJP-038 A,D,E,L 6
j. 039/ Close Main Steam Isolation Valve Locally - LJP-008 D,E,L 4S
k. 004/ Establish Backup Cooling to a Centrifical Charging Pump -

LJP-130 D,E,L,R 2

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

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (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) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility:

Diablo Canyon Scenario No.:

1 Op-Test No.:

L061-1 Examiners:

Operators:

Initial Conditions: 100% Power, MOL, 782 ppm CB Turnover: PRA Status: Green. Protected Equipment - Train B, Buses H& G, Prot. Sets II, III, IV. Sub-Cooled Margin Monitor train B OOS due to PT-403 failure. Swap CCW pps 1-1 and 1-3. U-2 at 100% power.

Event No.

Malf. No.

Event Type*

Event Description and Time Line 1

N Swap CCW Pump 1-1 and 1-3 2

Pmp cnd10 R

Heater 2 Drip Pump trips on over current (programmed ramp to 770 MWE at 40 MW/min).

3 Pmp asw1 C

Auxiliary Saltwater pump 11 trips on over current 3 minutes after generator < 771 MW. (TS 3.7.8.A) 4 xmt tur2 I

PT-505 fails low 10 minutes after ASW pp 12 is started. (TS 3.3.1.T) 5 mal sei1 M

0.28g earthquake 10 minutes after PT-505 failure.

6 mal rcs1 M

DBA LOCA after earthquake.

7 mal ppl1b C

Phase A train B fails to actuate on SI.

8 bkr eps 11 C

Auxiliary Saltwater Pump 1-2 fails to restart on SI.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility:

Diablo Canyon Scenario No.:

2 Op-Test No.:

L061-1 Examiners:

Operators:

Initial Conditions: 50% MOL, 937 ppm CB Turnover: Completed tunnel cleaning and both CWPs in service. Crew is to ramp unit to 60% power per OP L-4. D/G 11 was cleared 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> ago due for lube oil heater replacement. Expected back in 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.

PRA Status is Orange. U2 is at 100% power.

Event No.

Malf. No.

Event Type*

Event Description and Time Line 1

R Ramp to 60% power per OP L-4.

2 vlv pzr6 C

PORV PCV-474 fails to 25% open (TS 3.4.11.B) 5 minutes after ramp started.

3 cnh mss2 I

PCV-19 S/G 11 10% dump controller fails to 100% demand 10 min after PORV block valve 8000A is closed. (TS 3.7.4.A) 4 mal nis6c I

Power range channel NI-43 fails to 200% (TS 3.3.1.D,E) 5 min after PCV-19 b/u air cut-in.

5 loa cnd1 M

Loss of Condenser Vacuum 12 minutes after NI-43 fails high, leads to manual reactor trip.

6 bkr eps13 C

S/U feeder Overcurrent trip for 4KV bus H on bus transfer. (no power AFW pp 12) 7 mal afw1 C

AFW pp 11 trips when started 8

xmt afw3 I

AFW pp 13 discharge pressure transmitter limited to 360 psig, causes AFW LCV-113 & 115 to go closed in AUTO.

9 pmp afw2 C

AFW pp 13 trips on Overcurrent after LCV-113 & 115 taken to manual to restore AFW flow, leads to Loss of Heat Sink.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility:

Diablo Canyon Scenario No.:

3 Op-Test No.:

L061-1 Examiners:

Operators:

Initial Conditions: 25% BOL, 1182 ppm Turnover: PRA Status - Yellow. AFW pp 11 cleared for bearing replacement. CFCU 1-2 is cleared for motor replacement. High Swell Warning in effect. Reduce power to 20% on both units in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Unit 2 power reduction to 20% was completed 10 minutes ago. Ramp to 20% power was delayed by problems with Main Feedwater Bypass valves. Issue has been resolved, continue ramp to 20% Per OP L-4.

Event No.

Malf. No.

Event Type*

Event Description and Time Line 1

N Set 10% Steam Dumps for low power conditions.

2 R

Ramp to 20% power due to high swell warning.

3 pmp ven8 C

CFCU 14 over current trip 2 min after ramp started. (TS 3.6.6) 4 xmt pzr40 I

Controlling Pressurizer level channel LT-459 fails low 7 min after CFCU 14 trip.

(TS 3.3.1) 5 mal ccw2 C

Letdown heat exchanger tube leak 4 min after letdown restored.

6 mal rcs4b M

600 gpm Steam Generator 12 tube rupture after FCV-361 is opened.

7 mal mss3b C

Steam break outside containment on Steam Generator 12 on reactor trip.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility:

Diablo Canyon Scenario No.:

4 Op-Test No.:

L061-1 Examiners:

Operators:

Initial Conditions: 75% BOL, 1251 ppm CB Turnover: PRA - Yellow. Auxiliary Saltwater Pump 11 cleared for motor inspection. Unit has been operating at 75% power for 3 days due to 500kV transmission line problems. Line problems have been resolved, and Cal ISO requests full power output to prevent Stage 3 Involuntary power interruptions.

Direction is to return unit to full power as soon as possible. Unit 2 is at 100% power.

Event No.

Malf. No.

Event Type*

Event Description and Time Line 1

R Ramp to 100% power per OP L-4.

2 mal rod6a I

Continuous rod motion after first rod movement.

3 pmp cvc3 C

Charging Pump 13 over current trip, 7 min after rod problem. (ECG 8.1) 4 dsc rod1 I

Loss of normal DRPI power. (TS 3.1.7) **NOT USED**

5 xmt pzr15 I

Controlling PZR pressure channel (PT-457) fails 5 min after DRPI power is restored. ( TS 3.3.1, 3.3.2, 3.3.3).

6 mal sei1 M

0.25 g Earthquake, 6 min after PT-457 fails low.

7 mal mfw2b C

MFW PP 12 trips on high vibration due to earthquake.

8 mal mss4 M

Main steam line break downstream of MSIVs after MFW pp trip 9

vlv mss9 C

MSIV for SG 13 fails to close 10 mal ppl3a mal ppl3b C

Auto safety injection will not actuate, operators must perform a manual SI.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
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