ML113000276
| ML113000276 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 10/27/2011 |
| From: | NRC Region 4 |
| To: | Pacific Gas & Electric Co |
| References | |
| 50-275/11-07, 50-323/11-07 | |
| Download: ML113000276 (359) | |
Text
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL091-A1
Title:
CALCULATE ROD WITHDRAWAL HOLD POINTS Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(from NRCADM051-501B)
References:
U-1 OP L-2 Hot Standby to Startup Mode, Rev. 39 U-1 COLR, Rev 4 Vol 9, R19.1T-1, Cycle 17 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 1, 2 Job Designation: RO DCPP Task # / Rating: 818400 4.4 Gen KA # / Rating: GEN 2.1.23 Conduct of Operations 4.3 AUTHOR: GARY HUTCHISON DATE: 04/27/2011 REV. 0
JPM TITLE: CALCULATE ROD WITHDRAWAL HOLD JPM NUMBER: NRCL091-A1 POINTS INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: U-1 OP L-2, Attachments 9.1 and 9.2, and U-1 COLR (pg 12, RIL graph), and Vol 9, fig R19-1T-1.
Initial Conditions: Unit 1 is in mode 3 with the shutdown banks withdrawn. Current ECP is 135 steps on Control Bank D, cycle 17.
Initiating Cue: Calculate the rod withdrawal hold points using Attachments 9.1 and 9.2 of OP L-2.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: See Table Below ECP - 100 steps = D@35 RIL = C@55 ECP = D@135 ECP + 100 steps = D@231 Control Bank A Control Bank B Control Bank C Control Bank D 0
50 100 150 22 200 72 122 172 44 183 (Pause @RIL) = 55 94 144 16 163 (Pause @ ECP - 100) = 35 194 66 116 (ECP) = 135 (ECP + 100) = 231 ARO NRCL091-A1 REV 0.DOC PAGE 2 OF 4 REV. 0
JPM TITLE: CALCULATE ROD WITHDRAWAL HOLD JPM NUMBER: NRCL091-A1 POINTS INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Calculate rod withdrawal hold 1.1 Determines ARO = 231. **
points using Attachments 9.1 and 1.2 Determines ECP-100 = D @ 35. **
9.2.
1.3 Determines RIL = C @ 55. **
1.4 Determines ECP = D@ 135. **
1.5 Determines ECP + 100 =
D @ 231. **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Completes form for remaining 2.1 Determines 50 step hold points per hold points using 50 step answer key: **
increments
- CBA: 0, 50, 100, 150, 200
- CBB: 22, 72, 122, 172, 183
- CBC: 44, 55 (RIL), 94, 144, 163 (ECP - 100), 194
- CBD: 16, 35(ECP-100), 66, 116, 135 (ECP), 231 (ARO)
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A1 REV 0.DOC PAGE 3 OF 4 REV. 0
JPM NUMBER: NRCL091-A1 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is in mode 3 with the shutdown banks withdrawn. Current ECP is 135 steps on Control Bank D, cycle 17.
Initiating Cue: Calculate the rod withdrawal hold points using Attachments 9.1 and 9.2 of OP L-2.
NRCL091-A1 REV 0.DOC PAGE 4 OF 4 REV. 0
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
11/13/04 Page 1 of 2 DIABLO CANYON POWER PLANT TITLE: Rod Control Worksheet OP L-2 ATTACHMENT 9.1 Examinee Handout 1 2 AND Using Attachment 9.2 - Calculate the Rod Control hold points During reactor start up.
Review Volume 9 (R19-1T-1 or R19-2T-1) for ARO rod height ARO =
Use 50 step increments or as directed by RX engineering per STP R-6. Include stops at the RIL and ECP-100 to verify sub-criticality.
ECP - 100 steps = Mandatory Hold Point RIL = Mandatory Hold Point ECP =
ECP + 100 steps =
Control Bank A Control Bank B Control Bank C Control Bank D rad136FB.Doc 02 0816.1203
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
11/13/04 Page 2 of 2 OP L-2 (UNITS 1 AND 2)
ATTACHMENT 9.1 Examinee Handout TITLE: Rod Control Worksheet Sample Worksheet Using Attachment 9.2 - Calculate the Rod Control hold points During reactor start up.
Review Volume 9 (R19-1T-1 or R19-2T-1) for ARO rod height ARO = 228 Example Only Do NOT use for work. Example 1: Withdraw rods in 50 step increments OR as directed by RX engineering per STP R-6. Include momentary pauses at the RIL and ECP-100 to verify sub-criticality.
RIL = C @ 55 Procedure Pause Point ECP - 100 steps = D @ 50 Procedure Pause Point ECP = D @ 150 ECP + 100 steps = D @ 228 Control Bank A Control Bank B Control Bank C Control Bank D 0
50 100 150 22 200 72 122 172 44 183 (Pause @RIL) = 55 94 144 16 178 (Pause @ ECP - 100) = 50 194 66 228 116 (ECP) = 150 (ECP + 100) = 228 ARO rad136FB.Doc 02 0816.1203
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
11/13/04 Page 1 of 3 DIABLO CANYON POWER PLANT TITLE: Bank Overlap Chart OP L-2 ATTACHMENT 9.2 Examinee Handout 1 2 AND All Rods Out (ARO) = 225 steps Bank Behavior In Overlap S1 128 S3 256 S5 384 S2 225 S4 353 S6 481 ARO 225 Tip-2-Tip 128 Overlap 97 BOU Steps CBA CBB CBC CBD Details 0 0 S1 CBB Starts 128 128 0 S2 CBA Stops 225 225 97 S3 CBC Starts 256 128 0 S4 CBB Stops 353 225 97 S5 CBD Starts 384 128 0 S6 CBC Stops 481 225 97 ARO 609 225 Max ARO 615 rad136FB.Doc 02 0816.1203
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
11/13/04 Page 2 of 3 OP L-2 (UNITS 1 AND 2)
ATTACHMENT 9.2 Examinee Handout TITLE: Bank Overlap Chart All Rods Out (ARO) = 228 steps Bank Behavior In Overlap S1 128 S3 256S5 384 S2 228 S4 356S6 484 ARO 228 Tip-2-Tip 128Overlap 100 BOU Steps CBA CBB CBC CBD Details 0 0 S1 CBB Starts 128 128 0 S2 CBA Stops 228 228 100 S3 CBC Starts 256 128 0 S4 CBB Stops 356 228 100 S5 CBD Starts 384 128 0 S6 CBC Stops 484 228 100 ARO 612 228 Max ARO 615 rad136FB.Doc 02 0816.1203
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11/13/04 Page 3 of 3 OP L-2 (UNITS 1 AND 2)
ATTACHMENT 9.2 Examinee Handout TITLE: Bank Overlap Chart All Rods Out (ARO) = 231 steps Bank Behavior In Overlap S1 128 S3 256S5 384 S2 231 S4 359S6 487 ARO 231 Tip-2-Tip 128Overlap 103 BOU Steps CBA CBB CBC CBD Details 0 0 S1 CBB Starts 128 128 0 S2 CBA Stops 231 231 103 S3 CBC Starts 256 128 0 S4 CBB Stops 359 231 103 S5 CBD Starts 384 128 0 S6 CBC Stops 487 231 103 ARO 615 231 Max ARO 615 rad136FB.Doc 02 0816.1203
Examinee Handout
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 4 Examinee Handout PAGE 12 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 225 (0.17,225) (0.68,225) 200 BANK B (1.0, 177) 175 (0.0, 183)
Bank Position (Steps Withdrawn)
BANK C 150 125 100 (0.0, 55) 75 BANK D 50 25 Valid for Fully Withdrawn Rod Positions: >225 Steps And <231 Steps (0.29,0) 0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power Figure 1: Control Bank Insertion Limits Versus Rated Thermal Power radD8DFB.Doc 04B 1020.0724
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL091-A2
Title:
PERFORM SHUTDOWN MARGIN CALCULATION Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(from LJAC0-04R)
References:
STP R-19, Shutdown Margin Determination, Rev. 22 Figure R17-1F-1, Unit 1, Cycle 17, Rev. 16 Table R19-1T-1, Unit 1 Cycle 17, Rev. 21 Table R19-1T-2, Unit 1 Cycle 17, Rev. 21 Table R19-1T-5, Unit 1 Cycle 17, Rev. 19 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment : 50 minutes Critical Steps: 3, 4, 6, 7, 8, 9, 10 Job Designation: RO/SRO DCPP Task # / Rating: 79400 (RO/STA) 4.4 / 4.7 Gen KA # / Rating: GEN 2.1.25 Conduct of Operations 3.9 / 4.2 AUTHOR: GARY HUTCHISON DATE: 04/27/2011 REV. 0
JPM TITLE: PERFORM SHUTDOWN MARGIN JPM NUMBER: NRCL091-A2 CALCULATION INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials:
- STP R-19, Shutdown Margin Determination, Rev. 22
- Figure R17-1F-1, Unit 1, Cycle 17, Rev. 16
- Table R19-1T-1, Unit 1 Cycle 17, Rev. 21
- Table R19-1T-2, Unit 1 Cycle 17, Rev. 21
- Table R19-1T-5, Unit 1 Cycle 17, Rev. 19
- Calculator Initial Conditions: Given:
- Unit 1 tripped from 100% equilibrium power 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago.
- Rod K6 did not insert into the core and is stuck at 231 steps.
- Current conditions are:
- TAVG = 547°F
- CB = 1320 PPM
- Core Burnup (PEP R-5) = 500 MWD/MTU.
- The RCS will remain at NOP/NOT during troubleshooting.
- PZR/RCS boron mixing has been completed.
Initiating Cue: The SFM has assigned you to manually perform STP R-19, Shutdown Margin Determination, taking NO credit for Xe/Sm, and without using APEX.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: SDM Determination completed and submitted to SFM for review. (see ANSWER KEY version of procedure)
NRCL091-A2 rev 0.doc PAGE 2 OF 9 REV. 0
JPM TITLE: PERFORM SHUTDOWN MARGIN JPM NUMBER: NRCL091-A2 CALCULATION INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 Obtains and reviews STP R-19.
Note: Provide exam copy of STP R-19.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Complete the Precautions and 2.1 Enters UNIT (1), OPERATING MODE Limitations. (3), and todays DATE/TIME in the spaces provided.
2.2 Reviews and initials each Precaution and Limitation.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Note: Operator may start to complete Attachment 9.2 now (if so, go to step 5) or wait until procedure step 12.2.6 directs the operator to start entering data (if so, continue with step 4.1).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A2 rev 0.doc PAGE 3 OF 9 REV. 0
JPM TITLE: PERFORM SHUTDOWN MARGIN JPM NUMBER: NRCL091-A2 CALCULATION INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. Complete section 12.2. 4.1 Reads and initials step 12.2.1.
4.2 Checks N/A box for step 12.2.2.
4.3 Reads CAUTION.
4.4 Reads and initials step 12.2.3.
4.5 Checks N/A box for step 12.2.4.
4.6 Reads step 12.2.5 and NOTE.
Determines Condition A applies since SI will not be blocked (RCS will remain at the current conditions during troubleshooting).
4.7 Refers to Table R19-1T-2 (Unit 1) and determines the required boron concentration for 500 MWD/MTU and 547°F is 1204 ppm. **
Note: Provide exam copy of R19-1T-2 (if not already provided).
4.8 Records boron concentration (1204 ppm) and RCS temperature (547°F) in step 12.2.5.a. and initials step.**
4.9 Checks N/A box for step 12.2.5.b.
Note: The Operator may have chosen to wait until step 12.2.6 to start to complete Attachment 9.2.
4.10 Enters the boron concentration from step 12.2.5.a on Attachment 9.2 step E.2 (1204 ppm) and initials step 12.2.6.**
(continued on next page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A2 rev 0.doc PAGE 4 OF 9 REV. 0
JPM TITLE: PERFORM SHUTDOWN MARGIN JPM NUMBER: NRCL091-A2 CALCULATION INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. (continued) 4.11 Enters the RCS temperature from step 12.2.5.a on Attachment 9.2 step E.1 (547ºF) and initials step 12.2.7. **
4.12 Enters conditions for which calculation is valid in remarks section of Attachment 9.2 (e.g., this calculation takes no credit for Xe/Sm, with APEX not available, and SI not blocked) and initials step 12.2.8.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 5. Complete Section A of 5.1 Enters UNIT (1), CYCLE (17), MODE Attachment 9.2. (3), and todays DATE and TIME in the spaces provided.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 6. Complete Section B of 6.1 Enters:
Attachment 9.2.
1320 PPM**
- Core Avg Burnup = 500 MWD/MTU**
- Time Since Shutdown = 7 hrs **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 7. Complete Section C of 7.1 Determines Section C is N/A.**
Attachment 9.2.
7.2 Checks N/A and goes to Step D.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A2 rev 0.doc PAGE 5 OF 9 REV. 0
JPM TITLE: PERFORM SHUTDOWN MARGIN JPM NUMBER: NRCL091-A2 CALCULATION INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 8. Complete Section D of Note: Provide exam copy of R19-1T-1, if Attachment 9.2. not already provided.
8.1 Determines and enters:
- Most reactive rod worth at BOL from R19-1T-1 = 665 PCM **
- Stuck rods = 1 **
- Total stuck rod worth = 665 PCM **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 9. Complete Section E of Note: Operator may have previously Attachment 9.2. completed steps 9.1 and 9.2 per procedure steps 12.2.7 and 12.2.6, respectively (if so, skip to step 9.3).
9.1 Determines RCS Temperature and enters 547°F for E.1.**
Note: Provide exam copy of R19-1T-2.
9.2 Determines minimum required boron concentration and enters 1204 PPM for E.2.**
9.3 Adds 100 PPM and enters 1304 PPM for E.3.**
9.4 Reads NOTE and determines steps E.4 through E.8 cannot be skipped.
Note: Provide exam copy of R19-1T-5, if not already provided.
(continued on next page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A2 rev 0.doc PAGE 6 OF 9 REV. 0
JPM TITLE: PERFORM SHUTDOWN MARGIN JPM NUMBER: NRCL091-A2 CALCULATION INSTRUCTOR WORKSHEET Step Expected Operator Actions
(+/- 5 PCM) for E.4.** Circles BOL.
Note: Provide exam copy of R17-1F-1.
9.6 Determines boron worth multiplier and enters 1 for E.5.**
9.7 Determines boron worth corrected for Xe/Sm and enters -10,380 PCM
(+/- 10 PCM) for E.6.**
9.8 Determines total worth corrections and enters (+) 665 PCM for E.7.**
9.9 Determines net required boron worth and enters (-) 11,045 PCM (+/- 10 PCM) for E.8.**
9.10 Determines required Boron Concentration (by linear interpolation) and enters 1394 PPM (+/- 5 PPM) for E.9.**
9.11 Circles BOL.
9.12 Checks N/A box for E.10.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A2 rev 0.doc PAGE 7 OF 9 REV. 0
JPM TITLE: PERFORM SHUTDOWN MARGIN JPM NUMBER: NRCL091-A2 CALCULATION INSTRUCTOR WORKSHEET Step Expected Operator Actions
+/- 5 PPM).**
10.2 Checks NO box and notifies the SFM that the SDM is NOT ACCEPTABLE.**
Cue: If asked, the SFM will review Technical Specifications and submit a notification.
10.3 Completes REMARKS if not previously done.
10.4 Enters PERFORMED BY and todays DATE and TIME in the spaces provided.
10.5 Submits completed STP R-19 to SFM.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time: ___________
Total Time: ___________ .
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A2 rev 0.doc PAGE 8 OF 9 REV. 0
JPM NUMBER: NRCL091-A2 EXAMINEE CUE SHEET Initial Conditions: Given:
- Unit 1 tripped from 100% equilibrium power 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago.
- Rod K6 did not insert into the core and is stuck at 231 steps.
- Current conditions are:
- TAVG = 547°F
- CB = 1320 PPM
- Core Burnup (PEP R-5) = 500 MWD/MTU.
- The RCS will remain at NOP/NOT during troubleshooting.
- PZR/RCS boron mixing has been completed.
Initiating Cue: The SFM has assigned you to manually perform STP R-19, Shutdown Margin Determination, taking NO credit for Xe/Sm, and without using APEX.
NRCL091-A2 rev 0.doc PAGE 9 OF 9 REV. 0
C:\Documents and Settings\glh1\Local Settings\Temporary Internet Files\Content.IE5\GTY9WV03\rad71D72[1].tiff Examinee Handout 1 of 1
Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 NUCLEAR POWER GENERATION REVISION 22 DIABLO CANYON POWER PLANT PAGE 1 OF 8 SURVEILLANCE TEST PROCEDURE UNITS TITLE: Shutdown Margin Determination Examinee Handout 1 2 AND INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. SCOPE 1.1 This procedure provides guidance on which of the various methods and procedures to use for verification of SDM under the given conditions and provides the requisite methods for calculation of SDM for those cases which are not covered by other procedures (i.e., STPs I-1A, R-6, I-1B and R-17).
- 2. DISCUSSION 2.1 As defined by the Technical Specifications (Tech Specs), SHUTDOWN MARGIN (SDM) is the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all rod cluster control assemblies (RCCAs) are fully inserted, except for the single RCCA of highest reactivity worth which is assumed to be fully withdrawn. Each method of SDM verification is based upon one of the following:
2.1.1 Withdrawn rod worth: With the reactor critical and no untrippable rods, maintaining rods above the RIL ensures adequate SDM. If there are untrippable rods, then the available rod worth for shut down may be calculated (exclusive of untrippable rods) and compared to power defect to determine SDM.
NOTE: Untrippable rods are those which would not fully insert or have not fully inserted in response to an opening of the reactor trip breakers.
2.1.2 ECP calculations: With the reactor subcritical and RCS Tavg at approximately 547°F the critical boron concentration may be calculated for the current core burnup and fission product concentrations with rods positioned at the zero power rod insertion limit (ZPIL). So long as the current RCS boron concentration exceeds the ZPIL critical boron concentration, adequate SDM is ensured regardless of rod position.
2.1.3 Required boron concentration: The minimum boron concentration to provide the required SDM is determined based on temperature, xenon and samarium worths, and core burnup. The actual boron concentration is compared to this value to determine if SDM is adequate. The Westinghouse APEX code, or equivalent, may be used to calculate xenon and samarium worths if the reactor was not at equilibrium prior to shutdown.
2.1.4 Minimum refueling boron concentration: With the RCS borated to these conditions, adequate SDM is ensured for MODE 6. This is conservative for higher RCS temperatures and therefore may be applied in MODES 3, 4, and 5 as well.
rad93B96.Doc 06 0301.1240
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 PAGE 2 OF 8 Examinee Handout TITLE: Shutdown Margin Determination UNITS 1 AND 2
- 3. RESPONSIBILITIES 3.1 Shift foreman (SFM), for collection of required data, performing the required calculations, and approving the results.
3.2 PPE (reactor engineering) for providing technical support as necessary.
- 4. FREQUENCY 4.1 This procedure or other acceptable procedure as specified herein, shall be used to verify SHUTDOWN MARGIN at the following frequencies:
4.1.1 Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when critical in MODE 1 or 2. (Tech Spec 3.1.6) 4.1.2 Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in MODE 1 or 2, with any control bank not fully inserted.
(Tech Spec 3.1.5) 4.1.3 Every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when in MODE 2 with Keff < 1.0, MODES 3, 4, or 5.
(Tech Spec 3.1.1) 4.1.4 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to criticality when subcritical in MODE 2.
NOTE: For conservatism, OP L-1 requires verification of SDM every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with shutdown banks withdrawn when subcritical in MODE 2.
4.1.5 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of detection of an inoperable (untrippable) or misaligned control rod(s). (Tech Spec 3.1.4) 4.2 Additionally, Attachment 9.2, "SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods" should be completed within eight hours of a reactor shutdown and entry into MODE 3.
- 5. TECHNICAL SPECIFICATIONS 5.1 This procedure, in conjunction with the other procedures referenced herein, satisfies the SURVEILLANCE or ACTION requirements of the following:
5.1.1 Tech Spec SR 3.1.1.1 5.1.2 Tech Spec 3.1.4, Actions A.1.1, B.2.1.1, B.2.3, and D.1.1 5.1.3 Tech Spec SR 3.1.5.1 5.1.4 Tech Spec 3.1.5, Action A.1.1.
5.1.5 Tech Spec SR 3.1.6.1, SR 3.1.6.2 and SR 3.1.6.3 5.1.6 Tech Spec 3.1.6, Actions A.1.1 and B.1.1 5.1.7 Tech Spec SR 3.1.8.4 rad93B96.Doc 06 0301.1240
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 3 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2
- 6. ACCEPTANCE CRITERIA 6.1 In MODES 1, 2, 3, and 4 with SI enabled the SDM, less an allowance for any untrippable rods, shall be 1.6% k/k.
6.2 In MODES 3 or 4 with SI blocked the SDM, less an allowance for any untrippable rods, shall be 1.6% k/k at the RCS temperature that corresponds to the most limiting boron concentration determined in step 12.2.5.
6.3 In MODE 5 the SDM, less an allowance for any untrippable rods, shall be 1.6% k/k.
(The actual requirement is 1% k/k. To address the concerns of NSAL-02-014, 1.6% is used.)Ref.7.9
- 7. REFERENCES 7.1 OP L-1, "Plant Heatup From Cold Shutdown to Hot Standby" 7.2 STP I-1A, "Routine Shift Checks Required by Licenses" 7.3 STP I-1B, "Routine Daily Checks Required by Licenses" 7.4 STP R-6, "Low Power Reload Physics Tests" 7.5 STP R-17, "Estimated Critical Position" 7.6 Diablo Canyon Plant Manual, Volume 09B, Curves and Miscellaneous Data 7.7 Plant Operations Package, Current Unit and Cycle 7.8 AR A0695213-05, "Evaluate Boration Practices Shutdown for Refueling 02/09/08" 7.9 AR A0564034, "Assessment of Callaway Plant Event Report 39142" 7.10 Nuclear Design Report, Current Unit and Cycle 7.11 Westinghouse METCOM Manual, 6.10 Shutdown Margin 7.12 SAPN 50280874 7.13 SAPN 50263299
- 8. APPENDICES None
- 9. ATTACHMENTS 9.1 "SHUTDOWN MARGIN Calculation in MODES 1 and 2 with Stuck Control Rods*,"
01/15/09 9.2 "SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods," 03/01/10 9.3 "SHUTDOWN MARGIN Verification, MODE 3 to Pull or with S/D Banks Out or Rod Drop Testing," 01/15/09 9.4 "SHUTDOWN MARGIN Calculation in MODES 1 and 2 with a Dropped Control Rod,"
01/15/09 rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 4 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 START DATA SECTION UNIT OPERATING MODE DATE/TIME /
- 10. PRECAUTIONS AND LIMITATIONS INITIALS 10.1 Wherever a (+) or (-) sign is given on attachments, the correct number may be entered with no other signs. ______
10.2 For the purpose of SDM verification, the reactor is considered to have been at equilibrium conditions if the reactor power level did not vary more than +/-5% RTP in the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before the reactor shutdown. ______
10.3 When performing SR 3.1.1.1, applicable in MODES 2 (with Keff < 1.0), 3, 4, and 5, a current RCS boron concentration sample is required for each SDM determination. ______
10.4 A new RCS boron concentration sample is desired when completing Attachment 9.1 or 9.4 but it is acceptable to use the last sample if the initial SDM calculation must be completed in one hour. A followup calculation should be completed when a new sample is acquired. ______
10.5 Safety injection is blocked in the early stages (approximately 500 °F) of a plant cooldown when pressurizer pressure has dropped below the P-11 setpoint (1915 psig). The assumptions of the steam line break analysis require the RCS to be borated to at least the minimum boron concentration to meet shutdown margin technical specification limits at an RCS temperature of 200 °F (i.e., cold shutdown) prior to blocking steam line low pressure safety injection.Ref.7.9 ______
10.6 While technical specifications only require performance of this surveillance every 24-hours in MODES 3, 4, and 5, it would be non-conservative to commence a plant cooldown without verifying that adequate shutdown margin exists for the entire range of projected plant temperatures. Additionally, depending on power history prior to the shutdown, the reactivity contribution from xenon may become less negative than the pre-shutdown value well prior to the elapse of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, thus reducing the existing shutdown margin. Attachment 9.2 should be completed within eight hours of entry into MODE 3, and every four hours thereafter if credit is taken for xenon/samarium. ______
10.7 The concentration of borated water determined by PEP R-29, when added during vacuum refill, is sufficient to assure that the minimum required boron concentration for SDM is met even if the pressurizer and RCS are not mixed. Following vacuum refill, STP R-19, Attachment 9.2, step E.10, should be marked N/A. ______
- 11. PREREQUISITES None rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 5 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF
- 12. PROCEDURE 12.1 Determine the correct attachment or STP to use:
NOTE: Gray boxes indicate that STP R-19 is not used to document the shutdown margin verification.
for Initial Which MODE With Use Selected 1 Normal conditions STP I-1A 1 Stuck Rod(s) Attachment 9.1 1 a Dropped Rod Attachment 9.4 2 Normal conditions STP I-1A 2 Physics Testing in progress STP R-6 2 ECP Criticality STP R-17 2 Stuck Rod(s) Attachment 9.1 2 a Dropped Rod Attachment 9.4 3 Normal conditions Attachment 9.2 3 Stuck Rod(s) Attachment 9.2 3 Shutdown Banks Out Attachment 9.3 3 Rod Drop Testing Attachment 9.3 3 Refueling Boron Conc. STP I-1B 4 Normal conditions Attachment 9.2 4 Stuck Rod(s) Attachment 9.2 4 Refueling Boron Conc. STP I-1B 5 Normal conditions Attachment 9.2 5 Stuck Rods Attachment 9.2 5 Refueling Boron Conc. STP I-1B 5 For MODE 6 Entry STP I-1B 6 Refueling Boron Conc. STP I-1B rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 6 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF 12.2 If the method is Attachment 9.2: N/A [ ]
12.2.1 Following a reactor shutdown and entry into MODE 3, reactor engineering will provide assistance to the Unit Shift Foreman to determine required boron concentration (refer to OP L-5, "Plant Cooldown From Minimum Load to Cold Shutdown"). Attachment 9.2 should be completed within eight hours of entry into MODE 3. ______
12.2.2 IF the reactor was not at equilibrium conditions (refer to step 10.2) prior to shutdown, THEN consult reactor engineering before continuing. It may be necessary to calculate xenon and samarium worths for section C of the attachment.
N/A [ ] ______
CAUTION: If credit is taken for Xe/Sm, the SDM calculation must be repeated every four hours 12.2.3 For conservatism and ease of calculation, Xe/Sm may be ignored. This will increase the required boron concentration and therefore may not be desirable at EOL.
N/A [ ] ______
12.2.4 If the "APEX" code is used to calculate xenon and samarium worths, assume "N-1" rods and no boron.
N/A [ ] ______
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 7 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF 12.2.5 For certain core burnups, the Isothermal Temperature Coefficient becomes positive as RCS temperature is reduced. In order to ensure that technical specification limits on shutdown margin are met at all temperatures, determine the most limiting required boron concentration as follows:
NOTE: It is permissible to use an intermediate temperature value for the "final" temperature, provided the RCS is not cooled below the intermediate temperature prior to verifying the adequacy of the shutdown margin at a lower RCS temperature.
Choose the appropriate condition (A or B) that yields the highest boron concentration (see Volume 09B, Table R19-1T-2 (Unit 1) or Table R19-2T-2 (Unit 2):
Minimum Required Boron Concentration (PPM) for Shutdown Margin as a Function of Temperature and Burnup).
- a. Condition A: The highest specified boron concentration in the temperature range from 547 °F to the final RCS temperature. Record this boron concentration and temperature.
______ ppm ______°F N/A [ ] ______
- b. Condition B: If safety injection will be blocked, the boron concentration to meet shutdown margin technical specification limits at an RCS temperature of 200 °F. Record this boron concentration.
______ ppm N/A [ ] ______
12.2.6 Enter the boron concentration from the chosen condition (A or B) in E.2. ______
12.2.7 Enter the RCS temperature in E.1 that corresponds to the most limiting required boron concentration determined in step 12.2.5. ______
12.2.8 Include all conditions for which this calculation is valid in the remarks section of the attachment (e.g., Xenon-free, blocking SI, lowest RCS temperature if different than step 12.2.7, etc.) ______
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 8 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2
- 13. PRIMARY REVIEW 13.1 Review completed procedure. If acceptance criteria are not met, refer to the applicable LCO and initiate a Notification.
Notification # _________________________
REMARKS:
Reviewed By: /
Shift Foreman Print Name Signature Date/Time
- 14. SECONDARY REVIEW 14.1 Review test for completeness and acceptability.
REMARKS:
Reviewed By: Date:
Second Reviewer rad93B96.Doc 06 0301.1240
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01/15/09 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout STP R-19 ATTACHMENT 9.1 1 2 AND SHUTDOWN MARGIN Calculation in MODES 1 and 2 with Stuck Control Rods*
UNIT ______ CYCLE ______ MODE ______ DATE ________ TIME ________
- 1. CURRENT CORE CONDITIONS (for time of SDM)
- a. Control bank position c. Power level _________% RTP (bank/step) _____/____ d. Burnup (from PEP R-5) _________MWD/T
- b. Boron concentration _________ ppm e. Number of stuck rods** _________
- 2. AVAILABLE ROD WORTH FOR SHUTDOWN Available rod worth for shutdown from Volume 9B, Section IB at control bank position (step 1.a.) Use Figure R19-1F-2 (Unit 1) or Figure R19-2F-2 (Unit 2) (-)_______ pcm
- 3. POWER DEFECT Total Power Defect from Volume 9B, Section ID, Figure R17-1F-3 (Unit 1) or R17-2F-3 (Unit 2) at power level (step 1.c.), boron concentration (step 1.b.),
and burnup (step 1.d) (+)_______ pcm
- 4. WORTH OF STUCK ROD(S)**
- a. Most reactive rod worth from Volume 9B, Section ID, Table R19-1T-1 (Unit 1) or R19-2T-1 (Unit 2) (+)_______ pcm
- b. Total stuck rod worth (step 4.a. x step 1.e.) (+)_______ pcm
- 5. AVAILABLE SHUTDOWN WORTH Total net worth of withdrawn rod banks, power defect, and stuck rods (step 2 + step 3 + step 4.b) (-)_______ PCM
% K/K Shutdown (step 5 ÷ (-1000)) _________%K/K YES NO
- 7. MINIMUM SHUTDOWN MARGIN DETERMINATION Is the SHUTDOWN MARGIN determined in step 6 greater than or equal to
+1.6% K/K? [ ] [ ]
If the answer is YES, the core has sufficient SHUTDOWN MARGIN. If the answer is NO, immediately follow the appropriate Tech Spec Action Statement, notify the shift foreman, and submit a Notification.
- NOTE: If no immovable or untrippable control rods, use STP I-1A to verify SHUTDOWN MARGIN.
- NOTE: Stuck is defined as untrippable or immovable due to excessive friction or mechanical interference.
REMARKS:
PERFORMED BY: DATE/TIME: /
REVIEWED BY: DATE/TIME: /
SFM REVIEWED BY: DATE:
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03/01/10 Page 1 of 2 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout STP R-19 ATTACHMENT 9.2 1 2 SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods AND A. UNIT CYCLE MODE DATE TIME CAUTION: If credit is taken for Xenon (step C.2), repeat this calculation at least every FOUR hours.
B. CORE CONDITIONS
- 2. Core Avg Burnup (PEP R-5) ________ MWD MTU
- 3. Time Since Plant Shutdown (N/A startup after refueling) [ ] N/A ________ HRS C. XENON AND SAMARIUM WORTH [ ] N/A (If no credit is taken for Xe/Sm, check N/A, and go to step D.)
YES NO N/A
- 1. Power history determined and attached [ ] [ ] [ ]
- 2. If at equilibrium, estimated Xenon worth from R17-1T-2 or R17-2T-2 ( ) _________ PCM Circle Table per B.2: BOL MOL EOL
- 3. If at equilibrium, Samarium worth from R17-1T-3 or R17-2T-3 ( ) _________ PCM
- 4. Total Xe & Sm worth (C.2 + C.3) or computer output or zero ( ) _________ PCM D. WITHDRAWN ROD/BANK WORTH (N/A if computer or all rods fully inserted) [ ] N/A (If any rods not FULLY inserted, do not enter Ø pcm in step D.3.)
- 1. Most reactive rod worth from R19-1T-1 or R19-2T-1 (+) _________ PCM
- 2. Number of stuck rods* _________
- 3. Total stuck rod worth (D.1 x D.2) (+) _________ PCM
- Stuck is defined as untrippable or immovable due to excessive friction or mechanical interference.
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03/01/10 Page 2 of 2 STP R-19 (UNITS 1 AND 2) Examinee Handout ATTACHMENT 9.2 TITLE: SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods E. REQUIRED BORON CONCENTRATION
- 1. RCS Temperature (from step 12.2.7) _________°F
- 3. Add 100 PPM to concentration E.2 _________ PPM NOTE: If steps C & D = N/A, skip steps E.4 through E.8 and enter concentration E.3 in E.9.
- 4. Boron worth for concentration E.3 and Temp E.1 from R19-1T-5 or ( ) _________ PCM R19-2T-5. Circle Table per B.2: BOL MOL EOL
- 5. Boron worth multiplier for worth C.4 from R17-1F-1 or R17-2F-1 _________
(If step C.4 = Ø pcm, enter 1)
- 7. Total worth corrections (C.4 + D.3) ( ) _________ PCM
- 9. Required boron concentration for worth E.8, and Temp E.1 from R19-1T-5 or R19-2T-5 (Select Table per B.2: BOL MOL EOL) or if steps C & D = N/A enter concentration from E.3. _________ PPM
- 10. If not waiting for PZR/RCS boron mixing, (N/A following vacuum refill) multiply E.9 x 1.15 = N/A [ ] _________ PPM F. ACCEPTANCE CRITERIA
- 1. Is the actual boron concentration B.1 greater than or equal to the required concentration E.9 (or E.10 if applicable)? [ ] YES (ACCEPTABLE) [ ] NO (NOT ACCEPTABLE)
If this SDM is NOT ACCEPTABLE immediately follow the appropriate Tech Spec Action Statement, notify the SFM, and submit a Notification.
REMARKS: (See step 12.2.8)
PERFORMED BY: ________________________ DATE: __________ TIME: _________
REVIEWED BY: __________________________ DATE: __________ TIME: _________
SFM REVIEWED BY: __________________________ DATE: __________ TIME: _________
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01/15/09 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout STP R-19 ATTACHMENT 9.3 1 2 AND SHUTDOWN MARGIN Verification, MODE 3 to Pull or with S/D Banks Out or Rod Drop Testing UNIT _______ CYCLE ____________ DATE _______________ TIME _______________
This SHUTDOWN MARGIN verification is for MODE 3 to pull or with Shutdown Banks out or to perform rod drop testing.
CAUTION: If Xenon is present, this calculation should be repeated at least every FOUR hours.
- 1. ACTUAL CORE CONDITIONS (at the time of SDM calculation)
- a. Core average cycle burnup (PEP R-5) __________ MWD/MTU
- b. Moderator average temperature (Tavg) __________ °F
- 2. MINIMUM REQUIRED BORON CONCENTRATION
- a. Obtain the MINIMUM REQUIRED BORON CONCENTRATION for MODE 6 listed on Table R19-1(2)T-1 or perform an ECP calculation per STP R-17. Assume rods are at or above the zero power rod insertion limit for R-17.
- b. Required boron concentration determined in step 2.a. above.
Attach R-17 calculation if performed. __________ ppm YES NO
- c. Is the actual boron concentration in the core (step 1.c) greater than or equal to the required boron concentration (step 2.b)? [ ] [ ]
- d. Is the moderator average temperature (step 1.b) equal to or greater than 541°F? [ ] [ ]
- 3. SHUTDOWN MARGIN ACCEPTABILITY Answers to 2.c and 2.d: [ ] both YES (ACCEPTABLE)
[ ] any NO (NOT ACCEPTABLE)
If this SDM is NOT ACCEPTABLE, immediately comply with the appropriate Technical Specification Action Statement, notify the SFM and submit a Notification.
REMARKS:
PERFORMED BY DATE/TIME /
REVIEWED BY DATE/TIME /
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01/15/09 Page 1 of 2 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout STP R-19 ATTACHMENT 9.4 1 2 AND SHUTDOWN MARGIN Calculation in MODES 1 and 2 with a Dropped Control Rod UNIT ______ CYCLE ______ MODE ______ DATE ________ TIME ________
A. Initial SDM Determination N/A [ ] INITIALS IF Remaining rods are above the RIL for the power level existing before the dropped rod was dropped, ______
AND No RCS boron dilution has occurred since the rod was dropped, ______
AND Tavg is within 1.5 °F of Tref, ______
AND It has been less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> since the rod was dropped, ______
THEN Adequate SDM exists. ______
B. Subsequent SDM Determination N/A [ ]
- 1. CURRENT CORE CONDITIONS (for time of SDM)
- a. Control bank position c. Power level _________% RTP (bank/step) _____/_____ d. Burnup (from PEP R-5) _________MWD/T
- b. Boron concentration _________ ppm e. Number of dropped rods _________
- 2. AVAILABLE ROD WORTH FOR SHUTDOWN Available rod worth for shutdown from Volume 9B Section IB at control bank position (step 1.a.). Use Figure R19-1F-2 (Unit 1) or Figure R19-2F-2 (Unit 2) (-) _______ pcm
- 3. POWER DEFECT Total Power Defect from Volume 9B Section ID, Figure R17-1F-3 (Unit 1) or R17-2F-3 (Unit 2) at power level (step 1.c.), boron concentration (step 1.b.), and burnup (step 1.d) (+) _______ pcm
- 4. MAXIMUM WORTH OF DROPPED ROD(S)
- a. Most reactive rod worth from Volume 9B Section ID, Table R19-1T-1 (Unit 1) or R19-2T-1 (Unit 2) (+) _______ pcm
- b. Total dropped rod worth (step 4.a. x step 1.e.) (+) _______ pcm
- 5. AVAILABLE SHUTDOWN WORTH Total net worth of withdrawn rod banks, power defect, and dropped rods (step 2 + step 3 + step 4.b) (-) _______ PCM
% K/K Shutdown (step 5 ÷ (-1000)) _______%K/K rad93B96.Doc 06 0301.1240
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01/15/09 Page 2 of 2 STP R-19 (UNITS 1 AND 2)
Examinee Handout ATTACHMENT 9.4 TITLE: SHUTDOWN MARGIN Calculation in MODES 1 and 2 with a Dropped Control Rod YES NO
- 7. MINIMUM SHUTDOWN MARGIN DETERMINATION Is the SHUTDOWN MARGIN determined in step 6 greater than or equal to +1.6% K/K? [ ] [ ]
If the answer is YES, the core has sufficient SHUTDOWN MARGIN.
If the answer is NO, immediately comply with the appropriate Technical Specification Action Statement, notify the shift foreman, and submit a Notification.
REMARKS:
PERFORMED BY DATE/TIME /
REVIEWED BY DATE/TIME /
SFM REVIEWED BY DATE PPE rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 NUCLEAR POWER GENERATION REVISION 22 DIABLO CANYON POWER PLANT PAGE 1 OF 8 SURVEILLANCE TEST PROCEDURE UNITS TITLE: Shutdown Margin Determination ANSWER KEY 1 2 AND INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. SCOPE 1.1 This procedure provides guidance on which of the various methods and procedures to use for verification of SDM under the given conditions and provides the requisite methods for calculation of SDM for those cases which are not covered by other procedures (i.e., STPs I-1A, R-6, I-1B and R-17).
- 2. DISCUSSION 2.1 As defined by the Technical Specifications (Tech Specs), SHUTDOWN MARGIN (SDM) is the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all rod cluster control assemblies (RCCAs) are fully inserted, except for the single RCCA of highest reactivity worth which is assumed to be fully withdrawn. Each method of SDM verification is based upon one of the following:
2.1.1 Withdrawn rod worth: With the reactor critical and no untrippable rods, maintaining rods above the RIL ensures adequate SDM. If there are untrippable rods, then the available rod worth for shut down may be calculated (exclusive of untrippable rods) and compared to power defect to determine SDM.
NOTE: Untrippable rods are those which would not fully insert or have not fully inserted in response to an opening of the reactor trip breakers.
2.1.2 ECP calculations: With the reactor subcritical and RCS Tavg at approximately 547°F the critical boron concentration may be calculated for the current core burnup and fission product concentrations with rods positioned at the zero power rod insertion limit (ZPIL). So long as the current RCS boron concentration exceeds the ZPIL critical boron concentration, adequate SDM is ensured regardless of rod position.
2.1.3 Required boron concentration: The minimum boron concentration to provide the required SDM is determined based on temperature, xenon and samarium worths, and core burnup. The actual boron concentration is compared to this value to determine if SDM is adequate. The Westinghouse APEX code, or equivalent, may be used to calculate xenon and samarium worths if the reactor was not at equilibrium prior to shutdown.
2.1.4 Minimum refueling boron concentration: With the RCS borated to these conditions, adequate SDM is ensured for MODE 6. This is conservative for higher RCS temperatures and therefore may be applied in MODES 3, 4, and 5 as well.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 4 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 START DATA SECTION UNIT 1 OPERATING MODE 3 DATE/TIME Today/ Now
- 10. PRECAUTIONS AND LIMITATIONS INITIALS 10.1 Wherever a (+) or (-) sign is given on attachments, the correct GLH number may be entered with no other signs. ______
10.2 For the purpose of SDM verification, the reactor is considered to have been at equilibrium conditions if the reactor power level did not vary more than +/-5% RTP in the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before the reactor GLH shutdown. ______
10.3 When performing SR 3.1.1.1, applicable in MODES 2 (with Keff < 1.0), 3, 4, and 5, a current RCS boron concentration sample GLH is required for each SDM determination. ______
10.4 A new RCS boron concentration sample is desired when completing Attachment 9.1 or 9.4 but it is acceptable to use the last sample if the initial SDM calculation must be completed in one hour. A followup calculation should be completed when a GLH new sample is acquired. ______
10.5 Safety injection is blocked in the early stages (approximately 500 °F) of a plant cooldown when pressurizer pressure has dropped below the P-11 setpoint (1915 psig). The assumptions of the steam line break analysis require the RCS to be borated to at least the minimum boron concentration to meet shutdown margin technical specification limits at an RCS temperature of 200 °F (i.e., cold shutdown) prior to blocking steam line low pressure GLH safety injection.Ref.7.9 ______
10.6 While technical specifications only require performance of this surveillance every 24-hours in MODES 3, 4, and 5, it would be non-conservative to commence a plant cooldown without verifying that adequate shutdown margin exists for the entire range of projected plant temperatures. Additionally, depending on power history prior to the shutdown, the reactivity contribution from xenon may become less negative than the pre-shutdown value well prior to the elapse of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, thus reducing the existing shutdown margin. Attachment 9.2 should be completed within eight hours of entry into MODE 3, and every four hours GLH thereafter if credit is taken for xenon/samarium. ______
10.7 The concentration of borated water determined by PEP R-29, when added during vacuum refill, is sufficient to assure that the minimum required boron concentration for SDM is met even if the pressurizer and RCS are not mixed. Following vacuum refill, GLH STP R-19, Attachment 9.2, step E.10, should be marked N/A. ______
- 11. PREREQUISITES None rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 5 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF
- 12. PROCEDURE 12.1 Determine the correct attachment or STP to use:
NOTE: Gray boxes indicate that STP R-19 is not used to document the shutdown margin verification.
for Initial Which MODE With Use Selected 1 Normal conditions STP I-1A 1 Stuck Rod(s) Attachment 9.1 1 a Dropped Rod Attachment 9.4 2 Normal conditions STP I-1A 2 Physics Testing in progress STP R-6 2 ECP Criticality STP R-17 2 Stuck Rod(s) Attachment 9.1 2 a Dropped Rod Attachment 9.4 3 Normal conditions Attachment 9.2 3 Stuck Rod(s) Attachment 9.2 GLH 3 Shutdown Banks Out Attachment 9.3 3 Rod Drop Testing Attachment 9.3 3 Refueling Boron Conc. STP I-1B 4 Normal conditions Attachment 9.2 4 Stuck Rod(s) Attachment 9.2 4 Refueling Boron Conc. STP I-1B 5 Normal conditions Attachment 9.2 5 Stuck Rods Attachment 9.2 5 Refueling Boron Conc. STP I-1B 5 For MODE 6 Entry STP I-1B 6 Refueling Boron Conc. STP I-1B rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 6 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF 12.2 If the method is Attachment 9.2: N/A [ ]
12.2.1 Following a reactor shutdown and entry into MODE 3, reactor engineering will provide assistance to the Unit Shift Foreman to determine required boron concentration (refer to OP L-5, "Plant Cooldown From Minimum Load to Cold Shutdown"). Attachment 9.2 should be completed within eight hours of entry into MODE 3. GLH 12.2.2 IF the reactor was not at equilibrium conditions (refer to step 10.2) prior to shutdown, THEN consult reactor engineering before continuing. It may be necessary to calculate xenon and samarium worths for section C of the attachment.
N/A [ X] ______
CAUTION: If credit is taken for Xe/Sm, the SDM calculation must be repeated every four hours 12.2.3 For conservatism and ease of calculation, Xe/Sm may be ignored. This will increase the required boron concentration and therefore may not be desirable at EOL.
N/A [ ] GLH 12.2.4 If the "APEX" code is used to calculate xenon and samarium worths, assume "N-1" rods and no boron.
N/A [X] ______
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 7 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF 12.2.5 For certain core burnups, the Isothermal Temperature Coefficient becomes positive as RCS temperature is reduced. In order to ensure that technical specification limits on shutdown margin are met at all temperatures, determine the most limiting required boron concentration as follows:
NOTE: It is permissible to use an intermediate temperature value for the "final" temperature, provided the RCS is not cooled below the intermediate temperature prior to verifying the adequacy of the shutdown margin at a lower RCS temperature.
Choose the appropriate condition (A or B) that yields the highest boron concentration (see Volume 09B, Table R19-1T-2 (Unit 1) or Table R19-2T-2 (Unit 2):
Minimum Required Boron Concentration (PPM) for Shutdown Margin as a Function of Temperature and Burnup).
- a. Condition A: The highest specified boron concentration in the temperature range from 547 °F to the final RCS temperature. Record this boron concentration and temperature.
1204 ppm
______ 547
______°F N/A [ ] GLH OR
- b. Condition B: If safety injection will be blocked, the boron concentration to meet shutdown margin technical specification limits at an RCS temperature of 200 °F. Record this boron concentration.
______ ppm N/A [ X] ______
12.2.6 Enter the boron concentration from the chosen condition (A or B) in E.2. GLH 12.2.7 Enter the RCS temperature in E.1 that corresponds to the most limiting required boron concentration determined in step 12.2.5. GLH 12.2.8 Include all conditions for which this calculation is valid in the remarks section of the attachment (e.g., Xenon-free, blocking SI, lowest RCS temperature if different than step 12.2.7, etc.) GLH rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 8 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2
- 13. PRIMARY REVIEW 13.1 Review completed procedure. If acceptance criteria are not met, refer to the applicable LCO and initiate a Notification.
Notification # _________________________
REMARKS:
Reviewed By: /
Shift Foreman Print Name Signature Date/Time
- 14. SECONDARY REVIEW 14.1 Review test for completeness and acceptability.
REMARKS:
Reviewed By: Date:
Second Reviewer rad93B96.Doc 06 0301.1240
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
03/01/10 Page 1 of 2 DIABLO CANYON POWER PLANT TITLE:
ANSWER KEY STP R-19 ATTACHMENT 9.2 1 2 SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods AND A. UNIT 1 CYCLE 17 MODE 3 DATE Today TIME Now CAUTION: If credit is taken for Xenon (step C.2), repeat this calculation at least every FOUR hours.
B. CORE CONDITIONS
- 2. Core Avg Burnup (PEP R-5) 500
________ MWD MTU
- 3. Time Since Plant Shutdown (N/A startup after refueling) [ ] N/A 7
________ HRS C. XENON AND SAMARIUM WORTH [X] N/A (If no credit is taken for Xe/Sm, check N/A, and go to step D.)
YES NO N/A
- 1. Power history determined and attached [ ] [ ] [ ]
- 2. If at equilibrium, estimated Xenon worth from R17-1T-2 or R17-2T-2 ( ) _________ PCM Circle Table per B.2: BOL MOL EOL
- 3. If at equilibrium, Samarium worth from R17-1T-3 or R17-2T-3 ( ) _________ PCM
- 4. Total Xe & Sm worth (C.2 + C.3) or computer output or zero ( ) _________ PCM D. WITHDRAWN ROD/BANK WORTH (N/A if computer or all rods fully inserted) [ ] N/A (If any rods not FULLY inserted, do not enter Ø pcm in step D.3.)
- 1. Most reactive rod worth from R19-1T-1 or R19-2T-1 (+) 665
_________ PCM
- 2. Number of stuck rods* 1
- 3. Total stuck rod worth (D.1 x D.2) (+) 665
_________ PCM
- Stuck is defined as untrippable or immovable due to excessive friction or mechanical interference.
rad93B96.Doc 06 0301.1240
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03/01/10 Page 2 of 2 STP R-19 (UNITS 1 AND 2)
ATTACHMENT 9.2 TITLE: SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods ANSWER KEY E. REQUIRED BORON CONCENTRATION
- 1. RCS Temperature (from step 12.2.7) 547
_________°F
- 2. Minimum required boron concentration from step 12.2.5. 1204
_________ PPM
- 3. Add 100 PPM to concentration E.2 1304
_________ PPM NOTE: If steps C & D = N/A, skip steps E.4 through E.8 and enter concentration E.3 in E.9.
( ) _________
R19-2T-5. Circle Table per B.2: BOL MOL EOL (+/- 10 pcm)
- 5. Boron worth multiplier for worth C.4 from R17-1F-1 or R17-2F-1 1 (If step C.4 = Ø pcm, enter 1)
(+/- 10 pcm) ( ) _________
- 7. Total worth corrections (C.4 + D.3) 665 PCM
( + ) _________
( - ) _________
(+/- 10 pcm)
- 9. Required boron concentration for worth E.8, and Temp E.1 from R19-1T-5 or R19-2T-5 (Select Table per B.2: BOL MOL EOL) or if steps C & D = N/A enter concentration from E.3. 1394
_________ PPM
(+/- 5 ppm)
- 10. If not waiting for PZR/RCS boron mixing, (N/A following vacuum refill) multiply E.9 x 1.15 = N/A [X] _________ PPM F. ACCEPTANCE CRITERIA
- 1. Is the actual boron concentration B.1 greater than or equal to the required concentration E.9 (or E.10 if applicable)? [ ] YES (ACCEPTABLE) [ X] NO (NOT ACCEPTABLE)
If this SDM is NOT ACCEPTABLE immediately follow the appropriate Tech Spec Action Statement, notify the SFM, and submit a Notification.
REMARKS: (See step 12.2.8)
Mode 3, Xenon free, 547F, 500 MWD, Rod K6 stuck out, Pzr/RCS mixing done (remarks non-critical)
CO PERFORMED BY: ________________________ Today DATE: __________ Now TIME: _________
REVIEWED BY: __________________________ DATE: __________ TIME: _________
SFM REVIEWED BY: __________________________ DATE: __________ TIME: _________
PPE rad93B96.Doc 06 0301.1240
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL091-A3
Title:
PERFORM STP I-1A CHECK ON ACCUMULATOR VOLUME Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
References:
STP I-1A Routine Shift Checks Required by Licenses, Rev. 117 STP C-2, Att 9.1, Rev. 10 Sim GrpDis I-1A, pg 2 (Accum data)
Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 3, 4 Job Designation: RO DCPP Task # / Rating: 796200 (ret) N/A Gen KA # / Rating: GEN 2.2.44 Equipment Control 3.9 AUTHOR: GARY HUTCHISON DATE: 04/27/2011 REV. 0
JPM TITLE: PERFORM STP I-1A CHECK ON JPM NUMBER: NRCL091-A3 ACCUMULATOR VOLUME INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials:
- U-1 STP I-1A (partial procedure OK, min pgs 1, 2, & 3, and Att 12.1 pgs 1, 5, & 19)
- Group display from PPC (I-1A Accum Data)
- STP C-2, Att 9.1 (Accum Data) (two pgs)
Initial Conditions: Unit 1 is at 100% power.
Initiating Cue: Perform RCS Accumulator Volume checks per STP I-1A, step 4.
NRCL091-A3 REV 0.DOC PAGE 2 OF 6 REV. 0
JPM TITLE: PERFORM STP I-1A CHECK ON JPM NUMBER: NRCL091-A3 ACCUMULATOR VOLUME INSTRUCTOR WORKSHEET NOTE: Do NOT provide the student with the Task Standard.
Task Standard: See Table Below CURRENT %
RCS RCS ACCUMULATOR LEVEL C-2 Level Accumulator VB1 IND OR PPC Point % LEVEL % Change LI-950 [ ] LI950R [x ] _65.8 - _65.4_ = _+0.4_
1-1 LI-951 [ ] LI951R [x] __65.6 - _63.1_ = _+2.5_
LI-952 [ ] LI952R [x ] _63.1 - _61.6_ = _+1.5_
1-2 LI-953 [ ] LI953R [x ] __65.0 - __62.6 = _+2.4_
LI-954 [ ] LI954R [x ] __63.1 - __61.9 = _+1.2_
1-3 LI-955 [ ] LI955R [x ] __65.8 - __62.6 = _+3.2_
LI-956 [ ] LI956R [x ] __64.7 - __64.0 = _+0.7_
1-4 LI-957 [ ] LI957R [x ] __64.3 - __63.1 = _+1.2_ _GLH_
- b. Verify all current RCS accumulator levels are 59% and 75%. [52% to 82%] _GLH_
- c. Verify all RCS accumulator level changes are
+3% [5.6%]. _ #1___
- d. If any operational draining or filling of an accumulator occurs or if level increase is unacceptable, request chemistry to perform STP C-2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for affected accumulators. N/A [ ] _GLH_
- 1 in remarks: Accum 13 level change > 3%
NRCL091-A3 REV 0.DOC PAGE 3 OF 6 REV. 0
JPM TITLE: PERFORM STP I-1A CHECK ON JPM NUMBER: NRCL091-A3 ACCUMULATOR VOLUME INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Fills in current Level using PPC 1.1 Places check in PPC point box for data.. each accumulator indicator 1.2 Enters PPC data for each accumulator indicator Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Fills in STP C-2 level data. 2.1 Enters C-2 level data from STP C-2 for each accumulator indicator Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 3. Calculates level change 3.1 Calculates the level change by subtracting the C-2 level from the Current level for each accumulator indicator. **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A3 REV 0.DOC PAGE 4 OF 6 REV. 0
JPM TITLE: PERFORM STP I-1A CHECK ON JPM NUMBER: NRCL091-A3 ACCUMULATOR VOLUME INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. Completes RCS Accumulator 4.1 Determines all accumulator levels Volume checks (note: order of are 59% and 75%.
substep performance in this step is not critical) 4.2 Determines that LI955R level change for Accumulator 1-3 is
> 3%. **
4.3 Requests chemistry to perform STP C-2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Accumulator 1-3. **
4.4 Makes a note in the remarks section for step 4.c.
4.5 Fills in Test performer data on page 19.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A3 REV 0.DOC PAGE 5 OF 6 REV. 0
JPM NUMBER: NRCL091-A3 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is at 100% power.
Initiating Cue: Perform RCS Accumulator Volume checks per STP I-1A, step 4.
NRCL091-A3 REV 0.DOC PAGE 6 OF 6 REV. 0
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP I-1A NUCLEAR POWER GENERATION REVISION 117 DIABLO CANYON POWER PLANT PAGE 1 OF 3 SURVEILLANCE TEST PROCEDURE UNIT TITLE: Routine Shift Checks Required by Licenses Examinee Handout 1
INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. SCOPE 1.1 This test performs the routine shiftly channel checks required by Technical Specifications and ECGs. This procedure also contains numerous other verifications and checks required by various commitments and good engineering practices.
- 2. DISCUSSION 2.1 The checks to be performed are of two basic types. The first type is a CHANNEL CHECK. As defined in the Technical Specifications (Tech Specs), "a CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter." The second type of check performed is a verification that a condition or parameter meets Tech Spec or other requirements.
- 3. RESPONSIBILITIES 3.1 Shift foreman (SFM), for coordination of test, operation of the equipment as required by the test procedure, for obtaining test data, and determination of OPERABILITY.
- 4. FREQUENCY 4.1 Shift checks included in this procedure shall be performed on a nominal 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval with a maximum interval of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> in accordance with Tech Spec SR 3.0.2 and ECG SR 0.2.
4.2 Shift checks are required when the unit is in all MODES and defueled.
4.3 Attachments 12.5, 12.6, and 12.7 are completed on an "As Required" frequency to satisfy ECG SR 23.1.1.
- 5. TECHNICAL SPECIFICATIONS 5.1 The applicable Tech Spec section for each required instrument CHANNEL CHECK or verification is referenced next to the step on procedure attachments. Checks to meet other criteria are so noted.
- 6. ACCEPTANCE CRITERIA 6.1 The acceptance criteria is given in the attachment for each verification. The Tech Spec limits, if different than the acceptance criteria, are shown in brackets [ ]. The acceptance criteria takes into account instrument inaccuracies, gauge readability and possibly other uncertainties.
6.2 Quantitative limits are not applicable for a CHANNEL CHECK.
rad1BA0B.Doc 06 0824.1319
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR PACIFIC GAS AND ELECTRIC COMPANY USE *** NUMBER STP I-1A DIABLO CANYON POWER PLANT REVISION 117 Examinee Handout PAGE 2 OF 3 TITLE: Routine Shift Checks Required by Licenses UNIT 1
- 7. PRECAUTIONS AND LIMITATIONS None
- 8. PREREQUISITES None
- 9. PROCEDURE 9.1 Select proper attachment as follows:
9.1.1 Attachment 12.1 if unit is in MODE 1.
9.1.2 Attachment 12.2 if unit is in MODE 2 or 3.
9.1.3 Attachment 12.3 if unit is in MODE 4 or 5.
9.1.4 Attachment 12.4 if unit is in MODE 6 or defueled.
9.1.5 Attachments 12.5, 12.6, and 12.7 are completed "As Required" in any MODE.
9.2 Record data specified on the appropriate attachment. The applicable operating MODE(S), specific check to be made, and acceptance criteria are specified on each step of the attachment.
The sequence of steps is arbitrary and may be performed out of order, unless otherwise specified in the step.
9.3 Unless otherwise specified, the quality of PPC data used in surveillances must be one of the following:
- Good (green color value)
- HI (yellow color value, HI letter code)
- LOLO (red color value, LL letter code)
- HIHI (red color value, HH letter code)
- Alarm Suppressed (yellow color value, DA letter code) 9.4 Indicate a step is acceptable or performed with your initials. Check the boxes provided within a step to indicate the equipment used to verify the surveilled parameter, the current condition of the equipment, or the parameter or instrument is satisfactory. A step is not acceptable if any part of the check or verification is unacceptable for any reason. If a step is not acceptable, make a note as to why in the remarks for the section the step is in and include the tracking document number, which should be the Tech Spec sheet number for all Tech Spec or ECG items. Include any Notification and Order number(s) in the note.
Then enter the note number in the unacceptable portion(s) of the step. Indicate N/A for checks not required.
9.5 Add any additional shift checks required at the end of the section as may be required by inoperable plant equipment or instrumentation.
9.6 Sign and date the checklist when completed.
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- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR PACIFIC GAS AND ELECTRIC COMPANY USE *** NUMBER STP I-1A DIABLO CANYON POWER PLANT REVISION 117 Examinee Handout PAGE 3 OF 3 TITLE: Routine Shift Checks Required by Licenses UNIT 1
- 10. DATA REDUCTION AND REPORTING OF RESULTS 10.1 (SFM) Ensure all required checks meet Tech Spec requirements for present operating MODE. If going to a higher MODE, ensure the required checks in the next MODE also meet Tech Specs.
10.2 (SFM) For any check found not acceptable, review applicable Tech Specs or references, carry out any actions required; as necessary, notify management, and initiate a Notification. List applicable Tech Spec sheet number, Notification number or other appropriate tracking documentation in the remarks.
- 11. REFERENCES 11.1 AR A0655600, "TS LCO 3.4.1 Tavg Limit Inconsistent With Current Analysis"
- 12. ATTACHMENTS 12.1 Form 69-20232, "MODE 1 Shift Checklist," 08/24/10 12.2 Form 69-20233, "MODES 2 and 3 Shift Checklist," 08/24/10 12.3 Form 69-20234, "MODES 4 and 5 Shift Checklist," 08/24/10 12.4 Form 69-20235, "MODE 6 or Defueled Shift Checklist," 08/24/10 12.5 Form 69-20236, ""As Required" Check of Electrical Room Temperatures," 11/11/09 12.6 Form 69-20237, ""As Required" Check of ESF Equipment Room Temperatures,"
11/11/09 12.7 ""As Required" Check of ASW Pump Room Area Temperatures," 11/11/09 rad1BA0B.Doc 06 0824.1319
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR 69-20232 08/24/10 USE *** Page 1 of 25 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout MODE 1 Shift Checklist STP I-1A ATTACHMENT 12.1 1
1 TODAY NOW OPERATING MODE DATE TIME INSTRUCTIONS: Indicate a step is acceptable or performed with your initials. Check the boxes provided within a step to indicate the equipment used to verify the surveilled parameter, the current condition of the equipment, or the parameter or instrument is satisfactory. A step is not acceptable if any part of the check or verification is unacceptable for any reason. If a step is not acceptable, make a note as to why in the remarks for the section the step is in and include the tracking document number, which should be the Tech Spec sheet number for all Tech Spec or ECG items. Include any Notification and Order number(s) in the note. Then enter the note number in the unacceptable portion(s) of the step. Indicate N/A for checks not required.
APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.6.4.1 1. Containment Pressure
- a. Record containment pressure from narrow range containment pressure recorder (YR-26) [ ], or PPC Point (P0706A) [ x]. GLH 0.03 psig
- b. If plant instrumentation is not available, use M&TE sensing containment pressure, calibrated to 0.1%FS, with vacuum range 0-30"Hg or pressure range 0-30 psig, or equivalent. Note location of pressure measurement in remarks. N/A [ x] ______
M&TE ID NO._____________Cal due____________
Containment Press/Vac____________psig/"Hg
- c. Verify recorded pressure is between
-0.8 (1.628"Hg) and +1.0 psig [-1.0 and +1.2 psig]. GLH rad1BA0B.Doc 06 0824.1319
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ATTACHMENT 12.1 Examinee Handout TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.5.1.2 4. RCS Accumulator Volume SR 3.5.1.4
- a. Record current RCS accumulator volume and latest STP C-2 volume, then calculate volume change.
Check the indicator used.
CURRENT %
RCS RCS ACCUMULATOR LEVEL C-2 Level Accumulator VB1 IND OR PPC Point % LEVEL % Change LI-950 [ ] LI950R [ ] ______ - ______ = ______
1-1 LI-951 [ ] LI951R [ ] ______ - ______ = ______
LI-952 [ ] LI952R [ ] ______ - ______ = ______
1-2 LI-953 [ ] LI953R [ ] ______ - ______ = ______
LI-954 [ ] LI954R [ ] ______ - ______ = ______
1-3 LI-955 [ ] LI955R [ ] ______ - ______ = ______
LI-956 [ ] LI956R [ ] ______ - ______ = ______
1-4 LI-957 [ ] LI957R [ ] ______ - ______ = ______ ______
- b. Verify all current RCS accumulator levels are 59% and 75%. [52% to 82%] ______
- c. Verify all RCS accumulator level changes are +3%
[5.6%]. ______
- d. If any operational draining or filling of an accumulator occurs or if level increase is unacceptable, request chemistry to perform STP C-2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for affected accumulators. N/A [ ] ______
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ATTACHMENT 12.1 Examinee Handout TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 ECG SR 23.7.1 44. Perform a CHANNEL CHECK on Control Room pressurization system radiation monitors:
RM-51 [ ]
RM-52 [ ]
RM-53 [ ]
RM-54 [ ] ______
REMARKS:
Test performers and verifiers:
Name Signature Date/Time Init G. L. Hutchison Today / 0707 GLH
/
/
/
rad1BA0B.Doc 06 0824.1319
C:\Documents and Settings\glh1\Local Settings\Temporary Internet Files\Content.IE5\8TYZKDAX\Z101115.001.00000-0010[1].tif Examinee Handout 7/10/11 1 of 2
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Examinee Handout NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL091-A4
Title:
EVALUATE RELEASE UNDER CHANGING PLANT CONDITIONS Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(new)
References:
OP G-1:II Discharge of Liquid Radwaste Rev. 36 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 3 Job Designation: RO/SRO DCPP Task # / Rating: N53650 3.0 Gen KA # / Rating: GEN 2.3.11 Radiation Control 3.8 / 4.3 AUTHOR: JOHN F. BUCKLEY DATE: 04/28/2011 REV. 0
JPM TITLE: EVALUATE RELEASE UNDER CHANGING JPM NUMBER: NRCL091-A4 PLANT CONDITIONS INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Marked up of OP G-1:II (sec 12) and Discharge Permit for PWR 0-2 (CAP A-5), and calculator.
Initial Conditions: Given:
- A discharge of PWR 0-2 is in progress (has been in progress for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />). OP G-1:II is complete through step 12.21.4 (chemistry notified that release is in progress).
- Plant status:
- U-1 is at 50% power, with a normal full power equipment lineup, except that MFP 1-1 is OOS for a control oil leak (RTS is 4 hrs).
Initiating Cue: CWP 1-1 alarmed on ground overcurrent and was shutdown per procedure for evaluation/repair. Evaluate the effect (if any) of this failure on the discharge of PWR 0-2. If any actions are required as the result of this failure, list them on the answer/cue sheet.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Determines that dilution flow is below the minimum required for the release, and takes the following actions (exact words not required)
(note: these actions are found in step 6.9 of OP G-1:II):
- Select OFF on the discharge pump control switch
- Set HCV-647 to zero demand
- (may notify the SFM and chemistry of stopping the discharge, as well as completing the discharge permit, but these actions are not part of the task standard.)
NRCL091-A4 REV 0.DOC PAGE 2 OF 5 REV. 0
JPM TITLE: EVALUATE RELEASE UNDER CHANGING JPM NUMBER: NRCL091-A4 PLANT CONDITIONS INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Reviews OP G-1:II, step 12.21.5, 1.1 Determines that the radwaste criteria for problems during the discharge filter and RE-18 are not a discharge problem.
1.2 Determines that a loss of a CWP will affect dilution flow, and requires evaluation.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Re-evaluates dilution flow for 2.1 Reviews discharge permit, and notes discharge that the required flow is 1.29E6 gpm.
2.2 Using table on step 12.15 of OP G-1:II, determines that dilution flow is less than the amount required by the discharge permit.
2.2 Determines that step 12.21.5 (4th bullet) is met, and goes to step 6.9.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A4 REV 0.DOC PAGE 3 OF 5 REV. 0
JPM TITLE: EVALUATE RELEASE UNDER CHANGING JPM NUMBER: NRCL091-A4 PLANT CONDITIONS INSTRUCTOR WORKSHEET Step Expected Operator Actions
3.1 Select OFF on the discharge pump control switch. **
3.2 Set HCV-647 to zero demand. **
3.3 Notify the SFM that discharge has been terminated due to inadequate dilution flow.
3.4 Notify Chemistry that discharge has been terminated due to inadequate dilution flow.
3.5 Complete the discharge permit and note the reason for discharge termination in the comments section.
Cue: (once the other step 6.9 actions are written down or verbalized)
Another operator will complete the discharge paperwork (G-1:II and CAP A-5).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A4 REV 0.DOC PAGE 4 OF 5 REV. 0
JPM NUMBER: NRCL091-A4 EXAMINEE CUE SHEET Initial Conditions: Given:
A discharge of PWR 0-2 is in progress (has been in progress for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
OP G-1:II is complete through step 12.21.4 (chemistry notified that release is in progress).
- Plant status:
- U-1 is at 50% power, with a normal full power equipment lineup, except that MFP 1-1 is OOS for a control oil leak (RTS is 4 hrs).
Initiating Cue: CWP 1-1 alarmed on ground overcurrent and was shutdown per procedure for evaluation/repair. Evaluate the effect (if any) of this failure on the discharge of PWR 0-2. If any actions are required as the result of this failure, list them on the answer/cue sheet.
ANSWER SHEET (circle one of the two answers (below left), and fill in any actions required, as applicable)
NO ACTION N/A REQUIRED ACTION REQUIRED NRCL091-A4 REV 0.DOC PAGE 5 OF 5 REV. 0
- ISSUED FOR USE BY: _______________________ DATE: ____________ EXPIRES: ____________ ***
1&2 D IABLO C ANYON P OWER P LANT OP G-1:II OPERATING PROCEDURE Rev. 36 UNITS Page 1 of 45 Liquid Radwaste System - Discharge of Liquid Radwaste Examinee Handout 08/25/09 Effective Date QUALITY RELATED Table of Contents
- 1. SCOPE ........................................................................................................... 1
- 2. DISCUSSION.................................................................................................. 1
- 3. RESPONSIBILITIES ....................................................................................... 2
- 4. PREREQUISITES........................................................................................... 2
- 5. PRECAUTIONS AND LIMITATIONS .............................................................. 2
- 6. INSTRUCTIONS ............................................................................................. 3
- 7. REFERENCES ............................................................................................... 5
- 8. RECORDS...................................................................................................... 5
- 9. Discharging Chemical Drain Tank 0-1 (0-2) .................................................... 6
- 10. Discharging Laundry and Hot Shower Tank 0-1 (0-2).................................... 12
- 11. Discharging Floor Drain Receiver 0-1 (0-2) ................................................... 18
- 12. Discharging Process Waste Receiver 0-1 (0-2)............................................. 25
- 13. Discharging Demineralizer Regen Receiver 0-1 (0-2) ................................... 32
- 14. Discharging Laundry/Distillate Tank 0-1 (0-2) ............................................... 39
- 1. SCOPE 1.1 This procedure provides instructions to safely discharge liquid radwaste.
- 2. DISCUSSION 2.1 The primary goal of this procedure is to control liquid radwaste (LRW) discharges and prevent an inadvertent or unmonitored release.
2.2 This procedure should be performed in conjunction with CAP A-5, "Liquid Radwaste Discharge Management."
2.3 This procedure should be performed in conjunction with CAP A-11, "Liquid Radwaste Processing System Selection."
2.4 Liquid radwaste discharges are performed using an "Authorization for Discharge of Liquid Radwaste Batch," Form 69-20877, referred to as the "discharge permit" throughout this procedure.
2.5 Valves for LRW alignment and discharge are controlled by the Aux Board Human-Machine Interface (HMI).
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 2 of 45 Examinee Handout UNITS 1&2 2.6 In a section containing steps with more than one column, select the one column corresponding to the evolution to be performed, and perform only that column throughout the section.
- 3. RESPONSIBILITIES 3.1 Operations personnel are responsible for operation of equipment per this procedure.
3.2 The Shift Foreman (SFM) is responsible for compliance with applicable Technical Specifications and Equipment Control Guidelines (ECGs), and authorizing the discharge permit.
3.3 Chemistry is responsible for sampling of tank contents and preparation of the discharge permit.
- 4. PREREQUISITES 4.1 Verify the Liquid Radwaste System is aligned per OP G-1:I, "Liquid Radwaste System - Make Available and Place in Service."
4.2 Dilution water flowrate is adequate per Discharge Authorization requirements.
- 5. PRECAUTIONS AND LIMITATIONS 5.1 Only one LRW discharge can be performed at a time.
5.2 Only a tank NOT aligned for fill can be discharged.
5.3 Verify dilution water flow is maintained throughout the discharge.
5.4 Limit discharge flowrate to 90% of authorized flowrate.
5.5 If for any reason discharge flow is stopped, HIC-647 controller shall be adjusted to 20% demand prior to reinitiating flow.
5.6 Liquid Radwaste Filters 0-1 through 0-5 D/P shall not exceed 50 psid.
5.7 This procedure operates sealed components. Obtain a sealed component change form for use in operating these components.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 3 of 45 Examinee Handout UNITS 1&2
6.2 Discharge Laundry and Hot Shower Tank (LHST) 6.2.1 PERFORM Section 10 to discharge a LHST.
6.3 Discharge Floor Drain Receiver (FDR) 6.3.1 PERFORM Section 11 to discharge a FDR.
6.4 Discharge Processed Waste Receiver (PWR) 6.4.1 PERFORM Section 12 to discharge a PWR.
6.5 Discharge Demineralizer Regen Receiver (DRR) 6.5.1 PERFORM Section 13 to discharge a DRR.
6.6 Discharge Laundry/Distillate Tank (L/DT) 6.6.1 PERFORM Section 14 to discharge a L/DT.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 4 of 45 Examinee Handout UNITS 1&2 6.7 RE-18 high radiation alarm 6.7.1 Check closed 0-RCV-18.
6.7.2 Check open 0-FCV-477.
6.7.3 Select OFF on the discharge pump control switch.
6.7.4 Set HCV-647 to zero demand.
6.7.5 Notify the SFM that discharge has been terminated due to RE-18 alarm.
6.7.6 Notify Chemistry that discharge has been terminated due to RE-18 alarm.
6.7.7 Complete the discharge permit and note the reason for discharge termination in the comments section.
6.8 RE-18 component failure 6.8.1 Check closed 0-RCV-18.
6.8.2 Check open 0-FCV-477.
6.8.3 Select OFF on the discharge pump control switch.
6.8.4 Set HCV-647 to zero demand.
6.8.5 Notify the SFM that discharge has been terminated due to RE-18 failure.
6.8.6 Notify Chemistry that discharge has been terminated due to RE-18 failure.
6.8.7 Complete the discharge permit and note the reason for discharge termination in the comments section.
6.9 Inadequate dilution flowrate 6.9.1 Select OFF on the discharge pump control switch.
6.9.2 Set HCV-647 to zero demand.
6.9.3 Notify the SFM that discharge has been terminated due to inadequate dilution flow.
6.9.4 Notify Chemistry that discharge has been terminated due to inadequate dilution flow.
6.9.5 Complete the discharge permit and note the reason for discharge termination in the comments section.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 5 of 45 Examinee Handout UNITS 1&2
- 7. REFERENCES
7.1 Drawings
7.1.1 106719, "OVID-Liquid Radwaste System"
7.2 Procedures
7.2.1 OP G-1, "Liquid Radwaste System" 7.2.2 OP G-1:III, "Liquid Radwaste System-Clearing System Components" 7.2.3 CAP A-5, "Liquid Radwaste Discharge Management" 7.2.4 CAP A-11, "Liquid Radwaste Processing System Selection"
7.3 Notifications
7.3.1 AR A0217279, "FDR 0-2 Leak Into FDR 0-1"
7.4 Other
7.4.1 ECG 39.3, "Radioactive Liquid Effluent Monitoring Instrumentation"
- 8. RECORDS 8.1 Applicable Checklists SHOULD be attached to the Discharge Permit and forwarded to Chemistry for their review and disposition.
8.2 The Discharge Permit is archived in RMS and SHOULD have the applicable Checklist attached.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 25 of 45 Examinee Handout U1&2 Section 12: Page 1 of 7
- 12. Discharging Process Waste Receiver 0-1 (0-2) PERF VERF 12.1 Check parts 1 and 2 of the discharge permit are complete and signed by GLH BLS Chemistry.
12.2 Refer to Part 1a of discharge permit to verify appropriate tank for GLH BLS discharge:
PWR 0-1 OR PWR 0-2 12.3 IF RE-18 high alarm setpoint (HASP) requires adjustment, N/A THEN direct Chemistry to initiate the setpoint change.
12.4 IF FIT-243 is NOT OPERABLE, N/A THEN perform the following:
12.4.1 Log date and time FIT-243 is declared INOPERABLE in the shift log. _____
12.4.2 Initiate a notification for repair of FIT-243. _____
12.4.3 Review applicable portions of ECG 39.3. _____
12.5 Perform the following to align the discharge flowpath to a unit with an in-service CCW HX:
Table 12.5 Valve Unit with CCW in service (circle one and perform that column only)
U1 U2 LWS-0-436, Fltr Disch to U1 Overboard OPEN CLOSED GLH
_____ BLS LWS-0-439, Fltr Disch to U2 Overboard CLOSED OPEN GLH
_____ BLS 12.6 Check closed LWS-0-1065, L/DT Pp 0-1 and 0-2 disch to LRW. GLH 12.7 Check closed LWS-0-935, PWR Pp 0-1 Educ Isol. GLH 12.8 Check closed LWS-0-936, PWR Pp 0-2 Educ Isol. GLH 12.9 Check open PWR Pp Disch (second off):
PWR 0-1 OR PWR 0-2 LWS-0-934 LWS-0-937 GLH OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 26 of 45 Examinee Handout U1&2 Section 12: Page 2 of 7 12.10 Perform and independently verify the following Auxiliary Saltwater checklist:
Table 12.10 Valve CCW HX in service (circle one and perform that column only)
HX 1-1 HX 1-2 HX 2-1 HX 2-2 SW-1-67, Fltr Disch to 1-1 ASW Ovbd. OPEN CLOSED CLOSED CLOSED GLH
_____ BLS SW-1-68, Fltr Disch to 1-2 ASW Ovbd. CLOSED OPEN CLOSED CLOSED GLH
_____ BLS SW-2-67, Fltr Disch to 2-1 ASW Ovbd. CLOSED CLOSED OPEN CLOSED GLH
_____ BLS SW-2-68, Fltr Disch to 2-2 ASW Ovbd. CLOSED CLOSED CLOSED OPEN GLH
_____ BLS 12.11 Verify OP K-10L, "Sealed Valve Checklist for Liquid Radwaste Discharge System" complete. GLH 12.12 Verify CCW HX aligned for discharge to be in service by D/P indication (VB1). GLH 12.13 Verify RE-18 is operable by performing the following:
12.13.1 Verify the instrument calibration has NOT expired.
12.13.2 Perform a channel check as follows:
- Check Power On light is lit.
- Check Operation Selector switch in "Operate."
- Check Range Selector switch in "Wide."
- Check Low Alarm (red) light is NOT lit.
- Check RE-18 is being recorded on RR-102 at RMS Cabinet III.
N/A 12.13.3 IF RR-102 recorder is INOPERABLE, THEN monitor RE-18 output on the U2 PPC (address R0001A) continuously or by printing out in intervals not to exceed 5 minutes.
12.13.4 Perform a source check on RE-18 as follows:
- a. Notify Control Operator to expect PK 11-23, "RADIATION MON SYS IN TEST."
- b. While holding the Operation Selector switch in the "CHECK SOURCE" position, read the source count rate. 3 x 104
- c. Return Operation Selector switch to "OPERATE."
- d. Record the source count rate on Part 3 of the discharge permit.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 27 of 45 Examinee Handout U1&2 Section 12: Page 3 of 7 12.14 IF RE-18 is NOT OPERABLE, THEN perform the following: N/A 12.14.1 Log date and time RE-18 is declared INOPERABLE in the shift log. _____
12.14.2 Initiate a notification for repair of RE-18. _____
12.14.3 Review applicable portions of ECG 39.3. _____
12.15 Compare the specified "Minimum dilution water flowrate" (Section 2.d of discharge permit) with the current dilution flow, using the following table:
Circ Wtr Pp 1-1 0.425 X 106 gpm Circ Wtr Pp 2-1 0.433 X 106 gpm Circ Wtr Pp 1-2 0.413 X 106 gpm Circ Wtr Pp 2-2 0.433 X 106 gpm ASW Pp 1-1 0.011 X 106 gpm ASW Pp 2-1 0.011 X 106 gpm ASW Pp 1-2 0.011 X 106 gpm ASW Pp 2-2 0.011 X 106 gpm 12.16 IF dilution water flowrate is inadequate, N/A THEN contact Chemistry prior to continuing.
12.17 Verify complete and sign Part 3 of the discharge permit.
12.18 Obtain SFM review and authorization of the discharge permit.
USFM Today / 0712 Shift Foreman Date Time 12.19 Navigate to the Processed Waste Receivers Screen.
12.19.1 Verify Fill Select Switch selected to:
PWR 0-1 OR PWR 0-2 TK 0-2 TK 0-1 12.19.2 Under the Mode Selector menu:
- a. Select Discharge .
- b. Check FIT-243 in service.
- c. Check RM-18 in service.
- d. Select YES .
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 28 of 45 Examinee Handout U1&2 Section 12: Page 4 of 7
- e. Perform the following in the "Warning" pop-up:
- 1. Select Operator .
- 2. Enter "Performing Operator ID."
- 3. Select OK .
- 4. Select Shift Foreman .
- 5. Enter name of "Authorizing SFM."
- 6. Select OK .
- 7. Select Batch Number.
- 8. Enter "Discharge Permit Batch Number."
- 9. Select OK .
- 10. Select Click when Entries Made to Continue .
- 11. Verify all entries correct and select YES .
12.19.3 Select Open Controls .
- a. Perform the following in the "Discharge Control-Processed Waste Receiver System" pop-up:
- 1. Select Set Valves and verify OPEN FCV-446.
- 2. IF a pre discharge flush is required, THEN select YES .
OTHERWISE select NO and GO TO step 12.21.
- 3. Verify flush lineup desired and select YES .
- 4. Select Set Valves and verify the following:
- FCV-477 OPEN
- RCV-18 CLOSED OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 29 of 45 Examinee Handout U1&2 Section 12: Page 5 of 7 NOTE: Section 3.b.2 of the discharge permit will specify the volume to be flushed.
Flush volume can be monitored by noting tank level.
12.20 Flush PWR 0-1 or PWR 0-2:
12.20.1 Set HCV-647 to 20%.
12.20.2 Select ON on the appropriate PWR Pp control switch to start flush:
PWR 0-1 OR PWR 0-2 PWRP 0-1 PWRP 0-2 12.20.3 Adjust HCV-647 as desired.
12.20.4 WHEN necessary tank volume has been flushed, THEN select OFF on the running PWR Pp control switch to stop flush.
12.20.5 Set HCV-647 to 20%.
12.20.6 In the "Discharge Control-Processed Waste Receiver System" pop-up:
- a. Select Secure Flush and verify the following:
- FCV-477 CLOSED
12.21.1 Navigate to the Processed Waste Receivers Screen.
- a. Verify HCV-647 set to 20%.
- b. Select ON on the appropriate PWR Pp control switch to commence discharge:
PWR 0-1 OR PWR 0-2 PWRP 0-1 PWRP 0-2
- c. Adjust HCV-647 to 90% of limiting batch flowrate specified on discharge permit.
NOTE: Filter quality can be monitored by observing discharge flowrate, Filter 0-3 (PY-42), and Filter 0-4 (PY-1044) D/P.
12.21.2 Log time and batch number in the shift log.
12.21.3 Record the release information required on the discharge permit.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 30 of 45 Examinee Handout U1&2 Section 12: Page 6 of 7 12.21.4 Notify Chemistry the discharge has commenced.
12.21.5 During the discharge if necessary, perform the desired action from the table below:
IF: THEN:
- Discharge filter D/P is excessive GO TO step 12.22
- RE-18 alarms due to high rad GO TO step 6.7
- RE-18 has a component failure GO TO step 6.8
- There is inadequate dilution flow GO TO step 6.9 CAUTION: Do not allow Processed Waste Receiver level to fall below 10%. Damage to pump may result.
12.22 Secure discharge of PWR 0-1 or PWR 0-2.
12.22.1 Navigate to the Processed Waste Receivers Screen.
- a. Select OFF on the running PWR Pp control switch to secure discharge.
- b. Adjust HCV-647 to zero demand.
12.22.2 Refer to OP G-1:III for radwaste filter change if necessary.
12.22.3 IF discharge is complete, THEN GO TO step 12.22.4.
OTHERWISE resume discharge as desired per step 12.21.
12.22.4 Document FM-20 totalizer reading on the discharge permit.
12.22.5 In the "Discharge Control-Processed Waste System" pop-up, select Secure Discharge and verify CLOSED FCV-446. _____ _____
12.23 Complete the discharge permit form as required.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 31 of 45 Examinee Handout U1&2 Section 12: Page 7 of 7 COMMENTS:
Batch No:
Checklist Complete: Date/Time: /
SFM Review: Date/Time: /
Hutchison /
____________________________ GLH
_____ Today PRINT LAST NAME/SIGNATURE INIT DATE PRINT LAST NAME/SIGNATURE INIT DATE Sizemore /
____________________________ BLS
_____ Today PRINT LAST NAME/SIGNATURE INIT DATE PRINT LAST NAME/SIGNATURE INIT DATE OP_G-1~IIu3r36.DOC 0820.1606
C:\Documents and Settings\glh1\Local Settings\Temporary Internet Files\Content.IE5\MNYF2NA1\Z110118.001.00000-0100[1].tif Examinee Handout 2011-0-87 Today /
Now Today /
Now Today / 0600 2 of 22
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR 69-20877 06/16/09 USE *** Page 2 of 2 CAP A-5 (UNITS 1 AND 2)
Examinee Handout ATTACHMENT 11.1 TITLE: Authorization for Discharge of Liquid Radwaste Batch Batch No. 2011 87
- 3. RELEASE INFORMATION AND APPROVAL
- a. RE-18 Instrument Check Calibration Expiration Date 10/3/2011 4
Source check reading 3.0 x 10 cpm (If inoperable, refer to OP G-1:II.)
Operable [x] Inoperable [ ]
FIT-243: Operable [ x] Inoperable [ ] (If inoperable, refer to OP G-1:II.)
- b. The following requirements must be met prior to the release:
- 1) Never discharge via cartridge filter 0-2 unless authorized by senior chemistry engineer.
- 2) Flush 3 % of tank contents back to an EDR/DRR per OP G-1:II.
- c. Signed Joe Operator Today / 0710 Approved George USFM Today / 0712 Operator Date/Time Shift Foreman Date/Time CAUTION: If the tank level is different by >1% prior to flush from the tank level stated previously in Section 1.b., THEN THIS PERMIT IS INVALID.
Discharge Adequate Start Time Adequate Start Time Adequate Start Time Adequate Start Time Dilution? +3 hours Dilution? +6 hours Dilution? +9 hours Dilution?
today/0753 [x] Yes [ ] No [ ] Yes [ ] No [ ] Yes [ ] No [ ] Yes [ ] No If at any time during discharge dilution flow rate is NOT adequate, immediately refer to OP G-1:II
- d. Flow totalizer FM-20 at end of discharge Date/Time /
Total elapsed time Min.
Total time discharge is interrupted (e.g., filter changeout) Min.
Actual discharge time (beginning - end - interruptions) Min.
- e. Perform channel check on flow transmitter FIT-243 (or FY-243) Date/Time today / 0801 Verify flow is recording during the release period.
- f. Tank Level prior to flush 97 %
Tank level prior to discharge 94 % = 13,943 gal Tank level after discharge % = gal Volume Discharged = gal
- g. Performed By /
Operator (signature) Date/Time
- h. Comments
- i. Reviewed: / Noted Shift Foreman Date/Time Chemistry Supervision Date radF9D5D.Doc 08 0927.1608
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL091-A5
Title:
VERIFY ROD WITHDRAWAL HOLD POINTS Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(from NRCADM051-501B)
References:
U-1 OP L-2 Hot Standby to Startup Mode, Rev. 39 U-1 COLR, Rev 4 Vol 9, R19.1T-1, Cycle 17 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 1, 2 Job Designation: SRO DCPP Task # / Rating: 818400 4.4 Gen KA # / Rating: GEN 2.1.23 Conduct of Operations 4.4 AUTHOR: GARY HUTCHISON DATE: 04/27/2011 REV. 0
JPM TITLE: VERIFY ROD WITHDRAWAL HOLD POINTS JPM NUMBER: NRCL091-A5 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The task standard will NOT be read to the student. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.
Required Materials: U-1 OP L-2, Attachments 9.1 and 9.2, and U-1 COLR (pg 12, RIL graph), and Vol 9, fig R19-1T-1.
Initial Conditions: Unit 1 is in mode 3 with the shutdown banks withdrawn. Current ECP is 135 steps on Control Bank D, cycle 17. An ECP has been calculated.
Initiating Cue: Verify the rod withdrawal hold point calculations using Attachments 9.1 and 9.2 of OP L-2, and correct any errors encountered.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: See Table Below ECP - 100 steps = D@35 RIL = C@55 ECP = D@135 ECP + 100 steps = D@185 X - should be D@231 Control Bank A Control Bank B Control Bank C Control Bank D 0
50 100 150 22 200 72 122 172 44 X - should be 183 192 (Pause @RIL) = 55 94 144 16 163 (Pause @ ECP - 100) = 35 194 66 116 (ECP) = 135 X - should be 231 (ECP +
100) =185 NRCL091-A5 REV 0.DOC PAGE 2 OF 4 REV. 0
JPM TITLE: VERIFY ROD WITHDRAWAL HOLD POINTS JPM NUMBER: NRCL091-A5 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Verifies correct rod withdrawal 1.1 Determines ARO = 231.
hold points using Attachments 9.1 1.2 Determines ECP-100 = D @ 35.
and 9.2.
1.3 Determines RIL = C @ 55.
1.4 Determines ECP = D@ 135.
1.5 Determines ECP + 100 = D @ 185 is wrong. (should be D@231) **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Reviews form for remaining hold 2.1 Determines 50 step hold points:
points using 50 step increments
- CBA: 0, 50, 100, 150, 200
- CBB: 22, 72, 122, 172,
- CBB Determines last hold point should be 183 steps, not 192 steps. **
- CBC: 44, 55(RIL), 94, 144, 163 (ECP - 100), 194
- CBD: 16, 35(ECP-100), 66, 116, 135 (ECP),
- CBD Determines last hold point should be 231(ARO) steps, not 185 steps. **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
NRCL091-A5 REV 0.DOC PAGE 3 OF 4 REV. 0
JPM NUMBER: NRCL091-A5 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is in mode 3 with the shutdown banks withdrawn. Current ECP is 135 steps on Control Bank D, cycle 17. An ECP has been calculated.
Initiating Cue: Verify the rod withdrawal hold point calculations using Attachments 9.1 and 9.2 of OP L-2, and correct any errors encountered.
NRCL091-A5 REV 0.DOC PAGE 4 OF 4 REV. 0
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
11/13/04 Page 1 of 2 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout Rod Control Worksheet OP L-2 ATTACHMENT 9.1 1 2 AND Using Attachment 9.2 - Calculate the Rod Control hold points During reactor start up.
Review Volume 9 (R19-1T-1 or R19-2T-1) for ARO rod height ARO = 231 Use 50 step increments or as directed by RX engineering per STP R-6. Include stops at the RIL and ECP-100 to verify sub-criticality.
ECP - 100 steps = D@35 Mandatory Hold Point RIL = C@55 Mandatory Hold Point ECP = D@135 ECP + 100 steps = D@185 Control Bank A Control Bank B Control Bank C Control Bank D 0
50 100 150 22 200 72 122 172 44 192 55 94 144 16 163 35 194 66 116 135 185 rad136FB.Doc 02 0816.1203
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
11/13/04 Page 2 of 2 OP L-2 (UNITS 1 AND 2)
ATTACHMENT 9.1 Examinee Handout TITLE: Rod Control Worksheet Sample Worksheet Using Attachment 9.2 - Calculate the Rod Control hold points During reactor start up.
Review Volume 9 (R19-1T-1 or R19-2T-1) for ARO rod height ARO = 228 Example Only Do NOT use for work. Example 1: Withdraw rods in 50 step increments OR as directed by RX engineering per STP R-6. Include momentary pauses at the RIL and ECP-100 to verify sub-criticality.
RIL = C @ 55 Procedure Pause Point ECP - 100 steps = D @ 50 Procedure Pause Point ECP = D @ 150 ECP + 100 steps = D @ 228 Control Bank A Control Bank B Control Bank C Control Bank D 0
50 100 150 22 200 72 122 172 44 183 (Pause @RIL) = 55 94 144 16 178 (Pause @ ECP - 100) = 50 194 66 228 116 (ECP) = 150 (ECP + 100) = 228 ARO rad136FB.Doc 02 0816.1203
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
11/13/04 Page 1 of 3 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout Bank Overlap Chart OP L-2 ATTACHMENT 9.2 1 2 AND All Rods Out (ARO) = 225 steps Bank Behavior In Overlap S1 128 S3 256 S5 384 S2 225 S4 353 S6 481 ARO 225 Tip-2-Tip 128 Overlap 97 BOU Steps CBA CBB CBC CBD Details 0 0 S1 CBB Starts 128 128 0 S2 CBA Stops 225 225 97 S3 CBC Starts 256 128 0 S4 CBB Stops 353 225 97 S5 CBD Starts 384 128 0 S6 CBC Stops 481 225 97 ARO 609 225 Max ARO 615 rad136FB.Doc 02 0816.1203
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
11/13/04 Page 2 of 3 OP L-2 (UNITS 1 AND 2)
ATTACHMENT 9.2 Examinee Handout TITLE: Bank Overlap Chart All Rods Out (ARO) = 228 steps Bank Behavior In Overlap S1 128 S3 256S5 384 S2 228 S4 356S6 484 ARO 228 Tip-2-Tip 128Overlap 100 BOU Steps CBA CBB CBC CBD Details 0 0 S1 CBB Starts 128 128 0 S2 CBA Stops 228 228 100 S3 CBC Starts 256 128 0 S4 CBB Stops 356 228 100 S5 CBD Starts 384 128 0 S6 CBC Stops 484 228 100 ARO 612 228 Max ARO 615 rad136FB.Doc 02 0816.1203
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
11/13/04 Page 3 of 3 OP L-2 (UNITS 1 AND 2)
ATTACHMENT 9.2 Examinee Handout TITLE: Bank Overlap Chart All Rods Out (ARO) = 231 steps Bank Behavior In Overlap S1 128 S3 256S5 384 S2 231 S4 359S6 487 ARO 231 Tip-2-Tip 128Overlap 103 BOU Steps CBA CBB CBC CBD Details 0 0 S1 CBB Starts 128 128 0 S2 CBA Stops 231 231 103 S3 CBC Starts 256 128 0 S4 CBB Stops 359 231 103 S5 CBD Starts 384 128 0 S6 CBC Stops 487 231 103 ARO 615 231 Max ARO 615 rad136FB.Doc 02 0816.1203
Examinee Handout
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 4 Examinee Handout PAGE 12 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 225 (0.17,225) (0.68,225) 200 BANK B (1.0, 177) 175 (0.0, 183)
Bank Position (Steps Withdrawn)
BANK C 150 125 100 (0.0, 55) 75 BANK D 50 25 Valid for Fully Withdrawn Rod Positions: >225 Steps And <231 Steps (0.29,0) 0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power Figure 1: Control Bank Insertion Limits Versus Rated Thermal Power radD8DFB.Doc 04B 1020.0724
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL091-A6
Title:
VERIFY SHUTDOWN MARGIN CALCULATION Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(from LJAC0-04S, modified)
References:
STP R-19, Shutdown Margin Determination, Rev. 22 Figure R17-1F-1, Unit 1, Cycle 17, Rev. 16 Table R19-1T-1, Unit 1 Cycle 17, Rev. 21 Table R19-1T-2, Unit 1 Cycle 17, Rev. 21 Table R19-1T-5, Unit 1 Cycle 17, Rev. 19 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 40 minutes Critical Steps: 3, 8, 9 Job Designation: RO/SRO DCPP Task # / Rating: 79400 (RO/STA) 4.4 / 4.7 Gen KA # / Rating: GEN 2.1.25 Conduct of Operations 3.9 / 4.2 AUTHOR: JOHN F. BUCKLEY DATE: 04/27/2011 REV. 0
JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: NRCL091-A6 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials:
- STP R-19, Shutdown Margin Determination, Rev. 22
- Figure R17-1F-1, Unit 1, Cycle 17, Rev. 16
- Table R19-1T-1, Unit 1 Cycle 17, Rev. 21
- Table R19-1T-2, Unit 1 Cycle 17, Rev. 21
- Table R19-1T-5, Unit 1 Cycle 17, Rev. 19
- Calculator Initial Conditions: Given:
- Unit 1 tripped from 100% equilibrium power 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago.
- Rod K6 did not insert into the core and is stuck at 231 steps.
- Current conditions are:
- TAVG = 547°F
- CB = 1353 PPM
- Core Burnup (PEP R-5) = 500 MWD/MTU.
- The RCS will remain at NOP/NOT during troubleshooting.
- PZR/RCS boron mixing has been completed.
Initiating Cue: The CO just completed a manually performed STP R-19, Shutdown Margin Determination, taking NO credit for Xe/Sm, and without using APEX. You are directed to perform the SFM review of the SDM calculation. Errors encountered, if any, should be corrected on the procedure/calculation provided, and the SFM notified.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: The SDM calculation has been reviewed, and the errors have been corrected (see procedure KEY).
NRCL091-A6 rev 0.doc PAGE 2 OF 9 REV. 0
JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: NRCL091-A6 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Reviews the Precautions and 1.1 Verifies UNIT (1), OPERATING MODE Limitations. (3), and todays DATE/TIME are correct.
1.2 Reviews Precaution and Limitations.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Verifies the correct 2.1 Verifies that Attachment 9.2 of STP attachment or STP was used. R-19 is correct for these conditions.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A6 rev 0.doc PAGE 3 OF 9 REV. 0
JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: NRCL091-A6 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. Reviews section 12.2. 3.1 Reviews steps 12.2.1 - 12.2.3.
3.2 Verifies N/A box for step 12.2.4 is correct.
3.3 Reads step 12.2.5 and NOTE, and verifies Condition A is correct.
3.4 Refers to Table R19-1T-2 (Unit 1) and determines the required boron concentration for 500 MWD/MTU and 547°F is 1204 ppm, and that the number on the form and in the step is an error. **
Note: Provide exam copy of R19-1T-2 (if not already provided).
Note: The above error will cascade throughout the rest of the calculation.
3.5 Verifies the correct RCS temperature (547°F) in step 12.2.5.a.
3.6 Records the correct boron concentration (1204 ppm) in step 12.2.5.a. and initials step.**
3.7 Verifies that N/A is correct for step 12.2.5.b.
(continued on next page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A6 rev 0.doc PAGE 4 OF 9 REV. 0
JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: NRCL091-A6 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. (continued) 3.8 Enters the corrected boron concentration from step 12.2.5.a on Attachment 9.2 step E.2 (1204 ppm).**
3.9 Verifies the RCS temperature from step 12.2.5.a on Attachment 9.2 step E.1 (547ºF) at step 12.2.7.
Note: Operator may check the form data now, or once the form step is reached. The order/time checked is not critical during this review).
3.10 Verifies remarks are entered, per step 12.2.8.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 4. Reviews Section A of 4.1 Verifies UNIT (1), CYCLE (17), MODE Attachment 9.2. (3), and todays DATE and TIME in the spaces provided.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 5. Reviews Section B of 5.1 Verifies the following:
Attachment 9.2.
1353 PPM
- Core Avg Burnup = 500 MWD/MTU
- Time Since Shutdown = 7 hrs Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A6 rev 0.doc PAGE 5 OF 9 REV. 0
JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: NRCL091-A6 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 6. Reviews Section C of 6.1 Determines Section C is correctly marked Attachment 9.2. as N/A.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 7. Reviews Section D of Note: Provide exam copy of R19-1T-1, if Attachment 9.2. not already provided.
7.1 Verifies the following data:
- Most reactive rod worth at BOL from R19-1T-1 = 665 PCM
- Stuck rods = 1
- Total stuck rod worth = 665 PCM Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 8. Reviews Section E of Note: Provide exam copy of R19-1T-2.
Attachment 9.2.
8.1 Enters the corrected min boron concentration of 1204 PPM for E.2.**
8.2 Adds 100 PPM and enters a new concentration of 1304 PPM for E.3.**
8.3 Reads NOTE and verifies that steps E.4 through E.8 cannot be skipped.
Note: Provide exam copy of R19-1T-5, if not already provided.
(continued on next page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A6 rev 0.doc PAGE 6 OF 9 REV. 0
JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: NRCL091-A6 INSTRUCTOR WORKSHEET Step Expected Operator Actions
(+/- 10 PCM) for E.4.** (number changes due to previous error)
Note: Provide exam copy of R17-1F-1.
8.5 Verifies BOL is circled.
8.6 Verifies boron worth multiplier of 1 for E.5.
8.7 Determines boron worth corrected for Xe/Sm and enters -10,380 PCM (+/- 10 PCM) for E.6.** (number changes due to previous error) 8.8 Verifies total worth corrections are correct for E.7.
8.9 Determines net required boron worth and enters (-) 11,045 PCM (+/- 10 PCM) for E.8.** (number changes due to previous error) 8.10 Determines required Boron Concentration (by linear interpolation) and enters 1394 PPM (+/- 5 PPM) for E.9.** (number changes due to previous error) 8.11 Verifies BOL is circled.
8.12 Checks N/A box for E.10.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A6 rev 0.doc PAGE 7 OF 9 REV. 0
JPM TITLE: VERIFY SHUTDOWN MARGIN CALCULATION JPM NUMBER: NRCL091-A6 INSTRUCTOR WORKSHEET Step Expected Operator Actions
+/- 5 PPM).** (changed due to previous error) 9.2 Checks NO box (and unchecks YES box),
and notifies the SFM that the SDM is NOT ACCEPTABLE.** (changed due to previous error)
Cue: The WCSFM will submit a notification. Another SFM will address any applicable Tech Specs.
9.3 Reviews REMARKS section, if not previously done.
9.4 Enters REVIEWED BY and todays DATE and TIME in the spaces provided.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time: ___________
Total Time: ___________ .
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A6 rev 0.doc PAGE 8 OF 9 REV. 0
JPM NUMBER: NRCL091-A6 EXAMINEE CUE SHEET Initial Conditions: Given:
- Unit 1 tripped from 100% equilibrium power 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago.
- Rod K6 did not insert into the core and is stuck at 231 steps.
- Current conditions are:
- TAVG = 547°F
- CB = 1353 PPM
- Core Burnup (PEP R-5) = 500 MWD/MTU.
- The RCS will remain at NOP/NOT during troubleshooting.
- PZR/RCS boron mixing has been completed.
Initiating Cue: The CO just completed a manually performed STP R-19, Shutdown Margin Determination, taking NO credit for Xe/Sm, and without using APEX. You are directed to perform the SFM review of the SDM calculation. Errors encountered, if any, should be corrected on the procedure/calculation provided, and the SFM notified.
NRCL091-A6 rev 0.doc PAGE 9 OF 9 REV. 0
C:\Documents and Settings\glh1\Local Settings\Temporary Internet Files\Content.IE5\GTY9WV03\rad71D72[1].tiff Examinee Handout 1 of 1
Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout Examinee Handout
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 NUCLEAR POWER GENERATION REVISION 22 DIABLO CANYON POWER PLANT PAGE 1 OF 8 SURVEILLANCE TEST PROCEDURE UNITS TITLE: Shutdown Margin Determination Examinee Handout 1 2 AND INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. SCOPE 1.1 This procedure provides guidance on which of the various methods and procedures to use for verification of SDM under the given conditions and provides the requisite methods for calculation of SDM for those cases which are not covered by other procedures (i.e., STPs I-1A, R-6, I-1B and R-17).
- 2. DISCUSSION 2.1 As defined by the Technical Specifications (Tech Specs), SHUTDOWN MARGIN (SDM) is the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all rod cluster control assemblies (RCCAs) are fully inserted, except for the single RCCA of highest reactivity worth which is assumed to be fully withdrawn. Each method of SDM verification is based upon one of the following:
2.1.1 Withdrawn rod worth: With the reactor critical and no untrippable rods, maintaining rods above the RIL ensures adequate SDM. If there are untrippable rods, then the available rod worth for shut down may be calculated (exclusive of untrippable rods) and compared to power defect to determine SDM.
NOTE: Untrippable rods are those which would not fully insert or have not fully inserted in response to an opening of the reactor trip breakers.
2.1.2 ECP calculations: With the reactor subcritical and RCS Tavg at approximately 547°F the critical boron concentration may be calculated for the current core burnup and fission product concentrations with rods positioned at the zero power rod insertion limit (ZPIL). So long as the current RCS boron concentration exceeds the ZPIL critical boron concentration, adequate SDM is ensured regardless of rod position.
2.1.3 Required boron concentration: The minimum boron concentration to provide the required SDM is determined based on temperature, xenon and samarium worths, and core burnup. The actual boron concentration is compared to this value to determine if SDM is adequate. The Westinghouse APEX code, or equivalent, may be used to calculate xenon and samarium worths if the reactor was not at equilibrium prior to shutdown.
2.1.4 Minimum refueling boron concentration: With the RCS borated to these conditions, adequate SDM is ensured for MODE 6. This is conservative for higher RCS temperatures and therefore may be applied in MODES 3, 4, and 5 as well.
rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 4 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 START DATA SECTION UNIT 1 OPERATING MODE 3 DATE/TIME Today/ Now
- 10. PRECAUTIONS AND LIMITATIONS INITIALS 10.1 Wherever a (+) or (-) sign is given on attachments, the correct GLH number may be entered with no other signs. ______
10.2 For the purpose of SDM verification, the reactor is considered to have been at equilibrium conditions if the reactor power level did not vary more than +/-5% RTP in the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before the reactor GLH shutdown. ______
10.3 When performing SR 3.1.1.1, applicable in MODES 2 (with Keff < 1.0), 3, 4, and 5, a current RCS boron concentration sample GLH is required for each SDM determination. ______
10.4 A new RCS boron concentration sample is desired when completing Attachment 9.1 or 9.4 but it is acceptable to use the last sample if the initial SDM calculation must be completed in one hour. A followup calculation should be completed when a GLH new sample is acquired. ______
10.5 Safety injection is blocked in the early stages (approximately 500 °F) of a plant cooldown when pressurizer pressure has dropped below the P-11 setpoint (1915 psig). The assumptions of the steam line break analysis require the RCS to be borated to at least the minimum boron concentration to meet shutdown margin technical specification limits at an RCS temperature of 200 °F (i.e., cold shutdown) prior to blocking steam line low pressure GLH safety injection.Ref.7.9 ______
10.6 While technical specifications only require performance of this surveillance every 24-hours in MODES 3, 4, and 5, it would be non-conservative to commence a plant cooldown without verifying that adequate shutdown margin exists for the entire range of projected plant temperatures. Additionally, depending on power history prior to the shutdown, the reactivity contribution from xenon may become less negative than the pre-shutdown value well prior to the elapse of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, thus reducing the existing shutdown margin. Attachment 9.2 should be completed within eight hours of entry into MODE 3, and every four hours GLH thereafter if credit is taken for xenon/samarium. ______
10.7 The concentration of borated water determined by PEP R-29, when added during vacuum refill, is sufficient to assure that the minimum required boron concentration for SDM is met even if the pressurizer and RCS are not mixed. Following vacuum refill, GLH STP R-19, Attachment 9.2, step E.10, should be marked N/A. ______
- 11. PREREQUISITES None rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 5 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF
- 12. PROCEDURE 12.1 Determine the correct attachment or STP to use:
NOTE: Gray boxes indicate that STP R-19 is not used to document the shutdown margin verification.
for Initial Which MODE With Use Selected 1 Normal conditions STP I-1A 1 Stuck Rod(s) Attachment 9.1 1 a Dropped Rod Attachment 9.4 2 Normal conditions STP I-1A 2 Physics Testing in progress STP R-6 2 ECP Criticality STP R-17 2 Stuck Rod(s) Attachment 9.1 2 a Dropped Rod Attachment 9.4 3 Normal conditions Attachment 9.2 3 Stuck Rod(s) Attachment 9.2 GLH 3 Shutdown Banks Out Attachment 9.3 3 Rod Drop Testing Attachment 9.3 3 Refueling Boron Conc. STP I-1B 4 Normal conditions Attachment 9.2 4 Stuck Rod(s) Attachment 9.2 4 Refueling Boron Conc. STP I-1B 5 Normal conditions Attachment 9.2 5 Stuck Rods Attachment 9.2 5 Refueling Boron Conc. STP I-1B 5 For MODE 6 Entry STP I-1B 6 Refueling Boron Conc. STP I-1B rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT Examinee Handout REVISION 22 PAGE 6 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF 12.2 If the method is Attachment 9.2: N/A [ ]
12.2.1 Following a reactor shutdown and entry into MODE 3, reactor engineering will provide assistance to the Unit Shift Foreman to determine required boron concentration (refer to OP L-5, "Plant Cooldown From Minimum Load to Cold Shutdown"). Attachment 9.2 should be completed within eight hours of entry into MODE 3. GLH 12.2.2 IF the reactor was not at equilibrium conditions (refer to step 10.2) prior to shutdown, THEN consult reactor engineering before continuing. It may be necessary to calculate xenon and samarium worths for section C of the attachment.
N/A [ X] ______
CAUTION: If credit is taken for Xe/Sm, the SDM calculation must be repeated every four hours 12.2.3 For conservatism and ease of calculation, Xe/Sm may be ignored. This will increase the required boron concentration and therefore may not be desirable at EOL.
N/A [ ] GLH 12.2.4 If the "APEX" code is used to calculate xenon and samarium worths, assume "N-1" rods and no boron.
N/A [X] ______
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 7 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF 12.2.5 For certain core burnups, the Isothermal Temperature Coefficient becomes positive as RCS temperature is reduced. In order to ensure that technical specification limits on shutdown margin are met at all temperatures, determine the most limiting required boron concentration as follows:
NOTE: It is permissible to use an intermediate temperature value for the "final" temperature, provided the RCS is not cooled below the intermediate temperature prior to verifying the adequacy of the shutdown margin at a lower RCS temperature.
Choose the appropriate condition (A or B) that yields the highest boron concentration (see Volume 09B, Table R19-1T-2 (Unit 1) or Table R19-2T-2 (Unit 2):
Minimum Required Boron Concentration (PPM) for Shutdown Margin as a Function of Temperature and Burnup).
- a. Condition A: The highest specified boron concentration in the temperature range from 547 °F to the final RCS temperature. Record this boron concentration and temperature.
1155
______ ppm 547
______°F N/A [ ] GLH OR
- b. Condition B: If safety injection will be blocked, the boron concentration to meet shutdown margin technical specification limits at an RCS temperature of 200 °F. Record this boron concentration.
______ ppm N/A [ X] ______
12.2.6 Enter the boron concentration from the chosen condition (A or B) in E.2. GLH 12.2.7 Enter the RCS temperature in E.1 that corresponds to the most limiting required boron concentration determined in step 12.2.5. GLH 12.2.8 Include all conditions for which this calculation is valid in the remarks section of the attachment (e.g., Xenon-free, blocking SI, lowest RCS temperature if different than step 12.2.7, etc.) GLH rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 Examinee Handout PAGE 8 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2
- 13. PRIMARY REVIEW 13.1 Review completed procedure. If acceptance criteria are not met, refer to the applicable LCO and initiate a Notification.
Notification # _________________________
REMARKS:
Reviewed By: /
Shift Foreman Print Name Signature Date/Time
- 14. SECONDARY REVIEW 14.1 Review test for completeness and acceptability.
REMARKS:
Reviewed By: Date:
Second Reviewer rad93B96.Doc 06 0301.1240
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03/01/10 Page 1 of 2 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout STP R-19 ATTACHMENT 9.2 1 2 SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods AND A. UNIT 1 CYCLE 17 MODE 3 DATE Today TIME Now CAUTION: If credit is taken for Xenon (step C.2), repeat this calculation at least every FOUR hours.
B. CORE CONDITIONS
________ PPM
- 2. Core Avg Burnup (PEP R-5) 500
________ MWD MTU
- 3. Time Since Plant Shutdown (N/A startup after refueling) [ ] N/A 7
________ HRS C. XENON AND SAMARIUM WORTH [X] N/A (If no credit is taken for Xe/Sm, check N/A, and go to step D.)
YES NO N/A
- 1. Power history determined and attached [ ] [ ] [ ]
- 2. If at equilibrium, estimated Xenon worth from R17-1T-2 or R17-2T-2 ( ) _________ PCM Circle Table per B.2: BOL MOL EOL
- 3. If at equilibrium, Samarium worth from R17-1T-3 or R17-2T-3 ( ) _________ PCM
- 4. Total Xe & Sm worth (C.2 + C.3) or computer output or zero ( ) _________ PCM D. WITHDRAWN ROD/BANK WORTH (N/A if computer or all rods fully inserted) [ ] N/A (If any rods not FULLY inserted, do not enter Ø pcm in step D.3.)
- 1. Most reactive rod worth from R19-1T-1 or R19-2T-1 (+) 665
_________ PCM
- 2. Number of stuck rods* 1
- 3. Total stuck rod worth (D.1 x D.2) (+) 665
_________ PCM
- Stuck is defined as untrippable or immovable due to excessive friction or mechanical interference.
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03/01/10 Page 2 of 2 STP R-19 (UNITS 1 AND 2) Examinee Handout ATTACHMENT 9.2 TITLE: SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods E. REQUIRED BORON CONCENTRATION
- 1. RCS Temperature (from step 12.2.7) 547
_________°F
- 2. Minimum required boron concentration from step 12.2.5. 1204
_________ PPM
- 3. Add 100 PPM to concentration E.2 1304
_________ PPM NOTE: If steps C & D = N/A, skip steps E.4 through E.8 and enter concentration E.3 in E.9.
( ) _________
R19-2T-5. Circle Table per B.2: BOL MOL EOL
- 5. Boron worth multiplier for worth C.4 from R17-1F-1 or R17-2F-1 1 (If step C.4 = Ø pcm, enter 1)
( ) _________
- 7. Total worth corrections (C.4 + D.3) 665 PCM
( + ) _________
( - ) _________
- 9. Required boron concentration for worth E.8, and Temp E.1 from R19-1T-5 or R19-2T-5 (Select Table per B.2: BOL MOL EOL) or if steps C & D = N/A enter concentration from E.3. 1394
_________ PPM
- 10. If not waiting for PZR/RCS boron mixing, (N/A following vacuum refill) multiply E.9 x 1.15 = N/A [X] _________ PPM F. ACCEPTANCE CRITERIA
- 1. Is the actual boron concentration B.1 greater than or equal to the required concentration E.9 (or E.10 if applicable)? [X] YES (ACCEPTABLE) [ ] NO (NOT ACCEPTABLE)
If this SDM is NOT ACCEPTABLE immediately follow the appropriate Tech Spec Action Statement, notify the SFM, and submit a Notification.
REMARKS: (See step 12.2.8)
Mode 3, Xenon free, 547F, 500 MWD, Rod K6 stuck out, Pzr/RCS mixing done (remarks non-critical)
CO PERFORMED BY: ________________________ Today DATE: __________ Now TIME: _________
REVIEWED BY: __________________________ DATE: __________ TIME: _________
SFM REVIEWED BY: __________________________ DATE: __________ TIME: _________
PPE rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 NUCLEAR POWER GENERATION REVISION 22 DIABLO CANYON POWER PLANT PAGE 1 OF 8 SURVEILLANCE TEST PROCEDURE UNITS TITLE: Shutdown Margin Determination ANSWER KEY 1 2 AND INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. SCOPE 1.1 This procedure provides guidance on which of the various methods and procedures to use for verification of SDM under the given conditions and provides the requisite methods for calculation of SDM for those cases which are not covered by other procedures (i.e., STPs I-1A, R-6, I-1B and R-17).
- 2. DISCUSSION 2.1 As defined by the Technical Specifications (Tech Specs), SHUTDOWN MARGIN (SDM) is the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all rod cluster control assemblies (RCCAs) are fully inserted, except for the single RCCA of highest reactivity worth which is assumed to be fully withdrawn. Each method of SDM verification is based upon one of the following:
2.1.1 Withdrawn rod worth: With the reactor critical and no untrippable rods, maintaining rods above the RIL ensures adequate SDM. If there are untrippable rods, then the available rod worth for shut down may be calculated (exclusive of untrippable rods) and compared to power defect to determine SDM.
NOTE: Untrippable rods are those which would not fully insert or have not fully inserted in response to an opening of the reactor trip breakers.
2.1.2 ECP calculations: With the reactor subcritical and RCS Tavg at approximately 547°F the critical boron concentration may be calculated for the current core burnup and fission product concentrations with rods positioned at the zero power rod insertion limit (ZPIL). So long as the current RCS boron concentration exceeds the ZPIL critical boron concentration, adequate SDM is ensured regardless of rod position.
2.1.3 Required boron concentration: The minimum boron concentration to provide the required SDM is determined based on temperature, xenon and samarium worths, and core burnup. The actual boron concentration is compared to this value to determine if SDM is adequate. The Westinghouse APEX code, or equivalent, may be used to calculate xenon and samarium worths if the reactor was not at equilibrium prior to shutdown.
2.1.4 Minimum refueling boron concentration: With the RCS borated to these conditions, adequate SDM is ensured for MODE 6. This is conservative for higher RCS temperatures and therefore may be applied in MODES 3, 4, and 5 as well.
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 4 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 START DATA SECTION UNIT 1 OPERATING MODE 3 DATE/TIME Today/ Now
- 10. PRECAUTIONS AND LIMITATIONS INITIALS 10.1 Wherever a (+) or (-) sign is given on attachments, the correct GLH number may be entered with no other signs. ______
10.2 For the purpose of SDM verification, the reactor is considered to have been at equilibrium conditions if the reactor power level did not vary more than +/-5% RTP in the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before the reactor GLH shutdown. ______
10.3 When performing SR 3.1.1.1, applicable in MODES 2 (with Keff < 1.0), 3, 4, and 5, a current RCS boron concentration sample GLH is required for each SDM determination. ______
10.4 A new RCS boron concentration sample is desired when completing Attachment 9.1 or 9.4 but it is acceptable to use the last sample if the initial SDM calculation must be completed in one hour. A followup calculation should be completed when a GLH new sample is acquired. ______
10.5 Safety injection is blocked in the early stages (approximately 500 °F) of a plant cooldown when pressurizer pressure has dropped below the P-11 setpoint (1915 psig). The assumptions of the steam line break analysis require the RCS to be borated to at least the minimum boron concentration to meet shutdown margin technical specification limits at an RCS temperature of 200 °F (i.e., cold shutdown) prior to blocking steam line low pressure GLH safety injection.Ref.7.9 ______
10.6 While technical specifications only require performance of this surveillance every 24-hours in MODES 3, 4, and 5, it would be non-conservative to commence a plant cooldown without verifying that adequate shutdown margin exists for the entire range of projected plant temperatures. Additionally, depending on power history prior to the shutdown, the reactivity contribution from xenon may become less negative than the pre-shutdown value well prior to the elapse of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, thus reducing the existing shutdown margin. Attachment 9.2 should be completed within eight hours of entry into MODE 3, and every four hours GLH thereafter if credit is taken for xenon/samarium. ______
10.7 The concentration of borated water determined by PEP R-29, when added during vacuum refill, is sufficient to assure that the minimum required boron concentration for SDM is met even if the pressurizer and RCS are not mixed. Following vacuum refill, GLH STP R-19, Attachment 9.2, step E.10, should be marked N/A. ______
- 11. PREREQUISITES None rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 5 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF
- 12. PROCEDURE 12.1 Determine the correct attachment or STP to use:
NOTE: Gray boxes indicate that STP R-19 is not used to document the shutdown margin verification.
for Initial Which MODE With Use Selected 1 Normal conditions STP I-1A 1 Stuck Rod(s) Attachment 9.1 1 a Dropped Rod Attachment 9.4 2 Normal conditions STP I-1A 2 Physics Testing in progress STP R-6 2 ECP Criticality STP R-17 2 Stuck Rod(s) Attachment 9.1 2 a Dropped Rod Attachment 9.4 3 Normal conditions Attachment 9.2 3 Stuck Rod(s) Attachment 9.2 GLH 3 Shutdown Banks Out Attachment 9.3 3 Rod Drop Testing Attachment 9.3 3 Refueling Boron Conc. STP I-1B 4 Normal conditions Attachment 9.2 4 Stuck Rod(s) Attachment 9.2 4 Refueling Boron Conc. STP I-1B 5 Normal conditions Attachment 9.2 5 Stuck Rods Attachment 9.2 5 Refueling Boron Conc. STP I-1B 5 For MODE 6 Entry STP I-1B 6 Refueling Boron Conc. STP I-1B rad93B96.Doc 06 0301.1240
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR USE ***
PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 6 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF 12.2 If the method is Attachment 9.2: N/A [ ]
12.2.1 Following a reactor shutdown and entry into MODE 3, reactor engineering will provide assistance to the Unit Shift Foreman to determine required boron concentration (refer to OP L-5, "Plant Cooldown From Minimum Load to Cold Shutdown"). Attachment 9.2 should be completed within eight hours of entry into MODE 3. GLH 12.2.2 IF the reactor was not at equilibrium conditions (refer to step 10.2) prior to shutdown, THEN consult reactor engineering before continuing. It may be necessary to calculate xenon and samarium worths for section C of the attachment.
N/A [ X] ______
CAUTION: If credit is taken for Xe/Sm, the SDM calculation must be repeated every four hours 12.2.3 For conservatism and ease of calculation, Xe/Sm may be ignored. This will increase the required boron concentration and therefore may not be desirable at EOL.
N/A [ ] GLH 12.2.4 If the "APEX" code is used to calculate xenon and samarium worths, assume "N-1" rods and no boron.
N/A [X] ______
rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 7 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2 PERF 12.2.5 For certain core burnups, the Isothermal Temperature Coefficient becomes positive as RCS temperature is reduced. In order to ensure that technical specification limits on shutdown margin are met at all temperatures, determine the most limiting required boron concentration as follows:
NOTE: It is permissible to use an intermediate temperature value for the "final" temperature, provided the RCS is not cooled below the intermediate temperature prior to verifying the adequacy of the shutdown margin at a lower RCS temperature.
Choose the appropriate condition (A or B) that yields the highest boron concentration (see Volume 09B, Table R19-1T-2 (Unit 1) or Table R19-2T-2 (Unit 2):
Minimum Required Boron Concentration (PPM) for Shutdown Margin as a Function of Temperature and Burnup).
- a. Condition A: The highest specified boron concentration in the temperature range from 547 °F to the final RCS temperature. Record this boron concentration and temperature.
1204 ppm
______ 547
______°F N/A [ ] GLH OR
- b. Condition B: If safety injection will be blocked, the boron concentration to meet shutdown margin technical specification limits at an RCS temperature of 200 °F. Record this boron concentration.
______ ppm N/A [ X] ______
12.2.6 Enter the boron concentration from the chosen condition (A or B) in E.2. GLH 12.2.7 Enter the RCS temperature in E.1 that corresponds to the most limiting required boron concentration determined in step 12.2.5. GLH 12.2.8 Include all conditions for which this calculation is valid in the remarks section of the attachment (e.g., Xenon-free, blocking SI, lowest RCS temperature if different than step 12.2.7, etc.) GLH rad93B96.Doc 06 0301.1240
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP R-19 DIABLO CANYON POWER PLANT REVISION 22 ANSWER KEY PAGE 8 OF 8 TITLE: Shutdown Margin Determination UNITS 1 AND 2
- 13. PRIMARY REVIEW 13.1 Review completed procedure. If acceptance criteria are not met, refer to the applicable LCO and initiate a Notification.
Notification # _________________________
REMARKS:
Reviewed By: /
Shift Foreman Print Name Signature Date/Time
- 14. SECONDARY REVIEW 14.1 Review test for completeness and acceptability.
REMARKS:
Reviewed By: Date:
Second Reviewer rad93B96.Doc 06 0301.1240
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03/01/10 Page 1 of 2 DIABLO CANYON POWER PLANT TITLE:
ANSWER KEY STP R-19 ATTACHMENT 9.2 1 2 SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods AND A. UNIT 1 CYCLE 17 MODE 3 DATE Today TIME Now CAUTION: If credit is taken for Xenon (step C.2), repeat this calculation at least every FOUR hours.
B. CORE CONDITIONS
________ PPM
- 2. Core Avg Burnup (PEP R-5) 500
________ MWD MTU
- 3. Time Since Plant Shutdown (N/A startup after refueling) [ ] N/A 7
________ HRS C. XENON AND SAMARIUM WORTH [X] N/A (If no credit is taken for Xe/Sm, check N/A, and go to step D.)
YES NO N/A
- 1. Power history determined and attached [ ] [ ] [ ]
- 2. If at equilibrium, estimated Xenon worth from R17-1T-2 or R17-2T-2 ( ) _________ PCM Circle Table per B.2: BOL MOL EOL
- 3. If at equilibrium, Samarium worth from R17-1T-3 or R17-2T-3 ( ) _________ PCM
- 4. Total Xe & Sm worth (C.2 + C.3) or computer output or zero ( ) _________ PCM D. WITHDRAWN ROD/BANK WORTH (N/A if computer or all rods fully inserted) [ ] N/A (If any rods not FULLY inserted, do not enter Ø pcm in step D.3.)
- 1. Most reactive rod worth from R19-1T-1 or R19-2T-1 (+) 665
_________ PCM
- 2. Number of stuck rods* 1
- 3. Total stuck rod worth (D.1 x D.2) (+) 665
_________ PCM
- Stuck is defined as untrippable or immovable due to excessive friction or mechanical interference.
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03/01/10 Page 2 of 2 STP R-19 (UNITS 1 AND 2)
ATTACHMENT 9.2 TITLE: SHUTDOWN MARGIN in MODES 3, 4, and 5, All Rods In or Stuck Rods ANSWER KEY E. REQUIRED BORON CONCENTRATION
- 1. RCS Temperature (from step 12.2.7) 547
_________°F
- 2. Minimum required boron concentration from step 12.2.5. 1204
_________ PPM
- 3. Add 100 PPM to concentration E.2 1304
_________ PPM NOTE: If steps C & D = N/A, skip steps E.4 through E.8 and enter concentration E.3 in E.9.
( ) _________
R19-2T-5. Circle Table per B.2: BOL MOL EOL (+/- 10 pcm)
- 5. Boron worth multiplier for worth C.4 from R17-1F-1 or R17-2F-1 1 (If step C.4 = Ø pcm, enter 1)
(+/- 10 pcm) ( ) _________
- 7. Total worth corrections (C.4 + D.3) 665 PCM
( + ) _________
( - ) _________
(+/- 10 pcm)
- 9. Required boron concentration for worth E.8, and Temp E.1 from R19-1T-5 or R19-2T-5 (Select Table per B.2: BOL MOL EOL) or if steps C & D = N/A enter concentration from E.3. 1394
_________ PPM
(+/- 5 ppm)
- 10. If not waiting for PZR/RCS boron mixing, (N/A following vacuum refill) multiply E.9 x 1.15 = N/A [X] _________ PPM F. ACCEPTANCE CRITERIA
- 1. Is the actual boron concentration B.1 greater than or equal to the required concentration E.9 (or E.10 if applicable)? [ ] YES (ACCEPTABLE) [ X] NO (NOT ACCEPTABLE)
If this SDM is NOT ACCEPTABLE immediately follow the appropriate Tech Spec Action Statement, notify the SFM, and submit a Notification.
REMARKS: (See step 12.2.8)
Mode 3, Xenon free, 547F, 500 MWD, Rod K6 stuck out, Pzr/RCS mixing done (remarks non-critical)
CO PERFORMED BY: ________________________ Today DATE: __________ Now TIME: _________
REVIEWED BY: __________________________ DATE: __________ TIME: _________
SFM REVIEWED BY: __________________________ DATE: __________ TIME: _________
PPE rad93B96.Doc 06 0301.1240
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL091-A7
Title:
VERIFY STP I-1A CHECK ON ACCUMULATOR VOLUME Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
References:
STP I-1A Routine Shift Checks Required by Licenses, Rev. 117 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 3, 4 Job Designation: SRO DCPP Task # / Rating: 796200 (ret) N/A Gen KA # / Rating: GEN 2.2.44 Equipment Control 4.2 AUTHOR: GARY HUTCHISON DATE: 04/27/2011 REV. 0
JPM TITLE: VERIFY STP I-1A CHECK ON JPM NUMBER: NRCL091-A7 ACCUMULATOR VOLUME INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials:
- U-1 STP I-1A (partial procedure OK, min pgs 1, 2, & 3, and Att 12.1 pgs 1 & 5, with pg 5 filled in)
- Group display from PPC (I-1A Accum Data)
- STP C-2, Att 9.1 (Accum Data) (two pgs, with data filled in)
Initial Conditions: Unit 1 is at 100% power.
Initiating Cue: Review the RCS Accumulator Volume check per STP I-1A, step 4, for accuracy. Note any errors encountered on cue sheet answer area (if none, so state).
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: The following errors are noted (dont have to be exact wording):
- LI-955R level change is wrong (may specify 3.2%), and is > the 3%
tolerance)
- Step 4.c should not be initialed (should reference a note/remark or remark number)
- Step 4.d should not be checked N/A, (and should be initialed)
- (not required for credit) may mention calling chemistry, say to put a remark in the back of the procedure, and/or sign as a reviewer (these are not part of task, but may be mentioned)
NRCL091-A7 REV 0.DOC PAGE 2 OF 5 REV. 0
JPM TITLE: VERIFY STP I-1A CHECK ON JPM NUMBER: NRCL091-A7 ACCUMULATOR VOLUME INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Checks data from PPC. 1.1 Verifies PPC point box for each accumulator indicator is checked.
1.2 Verifies PPC data for each accumulator indicator is entered correctly for each point (optional).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Reviews STP C-2 level data input 2.1 Verifies C-2 level data from STP C-2 to STP I-1A. for each accumulator indicator.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 3. Verifies/reviews level changes 3.1 Verifies calculations for previous vs current accumulator levels (for all indicators except LI955R) to be accurate.
3.2 Determines that LI955R calculation is in error (the real value to be +
3.2%). **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A7 REV 0.DOC PAGE 3 OF 5 REV. 0
JPM TITLE: VERIFY STP I-1A CHECK ON JPM NUMBER: NRCL091-A7 ACCUMULATOR VOLUME INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. Completes RCS Accumulator 4.1 Verifies all accumulator levels are Volume checks 59% and 75%.
4.2 Determines that LI955R level change for Accumulator 1-3 is
> a 3% change. **
4.3 Determines a reference to a remark or note for step 4.c is needed, and should not be initialed as complete. **
Note: See task standard for additional notes on performance criteria.
4.4 Notes that step 4.d should NOT be checked N/A. **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A7 REV 0.DOC PAGE 4 OF 5 REV. 0
JPM NUMBER: NRCL091-A7 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is at 100% power.
Initiating Cue: Review the RCS Accumulator Volume check per STP I-1A, step 4, for accuracy. Note any errors encountered on cue sheet answer area (if none, so state).
Answer NRCL091-A7 REV 0.DOC PAGE 5 OF 5 REV. 0
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PACIFIC GAS AND ELECTRIC COMPANY NUMBER STP I-1A NUCLEAR POWER GENERATION REVISION 117 DIABLO CANYON POWER PLANT PAGE 1 OF 3 SURVEILLANCE TEST PROCEDURE UNIT TITLE: Routine Shift Checks Required by Licenses Examinee Handout 1
INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. SCOPE 1.1 This test performs the routine shiftly channel checks required by Technical Specifications and ECGs. This procedure also contains numerous other verifications and checks required by various commitments and good engineering practices.
- 2. DISCUSSION 2.1 The checks to be performed are of two basic types. The first type is a CHANNEL CHECK. As defined in the Technical Specifications (Tech Specs), "a CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter." The second type of check performed is a verification that a condition or parameter meets Tech Spec or other requirements.
- 3. RESPONSIBILITIES 3.1 Shift foreman (SFM), for coordination of test, operation of the equipment as required by the test procedure, for obtaining test data, and determination of OPERABILITY.
- 4. FREQUENCY 4.1 Shift checks included in this procedure shall be performed on a nominal 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval with a maximum interval of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> in accordance with Tech Spec SR 3.0.2 and ECG SR 0.2.
4.2 Shift checks are required when the unit is in all MODES and defueled.
4.3 Attachments 12.5, 12.6, and 12.7 are completed on an "As Required" frequency to satisfy ECG SR 23.1.1.
- 5. TECHNICAL SPECIFICATIONS 5.1 The applicable Tech Spec section for each required instrument CHANNEL CHECK or verification is referenced next to the step on procedure attachments. Checks to meet other criteria are so noted.
- 6. ACCEPTANCE CRITERIA 6.1 The acceptance criteria is given in the attachment for each verification. The Tech Spec limits, if different than the acceptance criteria, are shown in brackets [ ]. The acceptance criteria takes into account instrument inaccuracies, gauge readability and possibly other uncertainties.
6.2 Quantitative limits are not applicable for a CHANNEL CHECK.
rad1BA0B.Doc 06 0824.1319
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR PACIFIC GAS AND ELECTRIC COMPANY USE *** NUMBER STP I-1A DIABLO CANYON POWER PLANT REVISION 117 Examinee Handout PAGE 2 OF 3 TITLE: Routine Shift Checks Required by Licenses UNIT 1
- 7. PRECAUTIONS AND LIMITATIONS None
- 8. PREREQUISITES None
- 9. PROCEDURE 9.1 Select proper attachment as follows:
9.1.1 Attachment 12.1 if unit is in MODE 1.
9.1.2 Attachment 12.2 if unit is in MODE 2 or 3.
9.1.3 Attachment 12.3 if unit is in MODE 4 or 5.
9.1.4 Attachment 12.4 if unit is in MODE 6 or defueled.
9.1.5 Attachments 12.5, 12.6, and 12.7 are completed "As Required" in any MODE.
9.2 Record data specified on the appropriate attachment. The applicable operating MODE(S), specific check to be made, and acceptance criteria are specified on each step of the attachment.
The sequence of steps is arbitrary and may be performed out of order, unless otherwise specified in the step.
9.3 Unless otherwise specified, the quality of PPC data used in surveillances must be one of the following:
- Good (green color value)
- HI (yellow color value, HI letter code)
- LOLO (red color value, LL letter code)
- HIHI (red color value, HH letter code)
- Alarm Suppressed (yellow color value, DA letter code) 9.4 Indicate a step is acceptable or performed with your initials. Check the boxes provided within a step to indicate the equipment used to verify the surveilled parameter, the current condition of the equipment, or the parameter or instrument is satisfactory. A step is not acceptable if any part of the check or verification is unacceptable for any reason. If a step is not acceptable, make a note as to why in the remarks for the section the step is in and include the tracking document number, which should be the Tech Spec sheet number for all Tech Spec or ECG items. Include any Notification and Order number(s) in the note.
Then enter the note number in the unacceptable portion(s) of the step. Indicate N/A for checks not required.
9.5 Add any additional shift checks required at the end of the section as may be required by inoperable plant equipment or instrumentation.
9.6 Sign and date the checklist when completed.
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- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR PACIFIC GAS AND ELECTRIC COMPANY USE *** NUMBER STP I-1A DIABLO CANYON POWER PLANT Examinee Handout REVISION 117 PAGE 3 OF 3 TITLE: Routine Shift Checks Required by Licenses UNIT 1
- 10. DATA REDUCTION AND REPORTING OF RESULTS 10.1 (SFM) Ensure all required checks meet Tech Spec requirements for present operating MODE. If going to a higher MODE, ensure the required checks in the next MODE also meet Tech Specs.
10.2 (SFM) For any check found not acceptable, review applicable Tech Specs or references, carry out any actions required; as necessary, notify management, and initiate a Notification. List applicable Tech Spec sheet number, Notification number or other appropriate tracking documentation in the remarks.
- 11. REFERENCES 11.1 AR A0655600, "TS LCO 3.4.1 Tavg Limit Inconsistent With Current Analysis"
- 12. ATTACHMENTS 12.1 Form 69-20232, "MODE 1 Shift Checklist," 08/24/10 12.2 Form 69-20233, "MODES 2 and 3 Shift Checklist," 08/24/10 12.3 Form 69-20234, "MODES 4 and 5 Shift Checklist," 08/24/10 12.4 Form 69-20235, "MODE 6 or Defueled Shift Checklist," 08/24/10 12.5 Form 69-20236, ""As Required" Check of Electrical Room Temperatures," 11/11/09 12.6 Form 69-20237, ""As Required" Check of ESF Equipment Room Temperatures,"
11/11/09 12.7 ""As Required" Check of ASW Pump Room Area Temperatures," 11/11/09 rad1BA0B.Doc 06 0824.1319
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR 69-20232 08/24/10 USE *** Page 1 of 25 DIABLO CANYON POWER PLANT STP I-1A TITLE:
Examinee Handout MODE 1 Shift Checklist ATTACHMENT 12.1 1
OPERATING MODE 3 DATE Today TIME Now INSTRUCTIONS: Indicate a step is acceptable or performed with your initials. Check the boxes provided within a step to indicate the equipment used to verify the surveilled parameter, the current condition of the equipment, or the parameter or instrument is satisfactory. A step is not acceptable if any part of the check or verification is unacceptable for any reason. If a step is not acceptable, make a note as to why in the remarks for the section the step is in and include the tracking document number, which should be the Tech Spec sheet number for all Tech Spec or ECG items. Include any Notification and Order number(s) in the note. Then enter the note number in the unacceptable portion(s) of the step. Indicate N/A for checks not required.
APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.6.4.1 1. Containment Pressure
- a. Record containment pressure from narrow range containment pressure recorder (YR-26) [ ], or PPC Point (P0706A) [ x]. ______
GLH 0.03 psig
- b. If plant instrumentation is not available, use M&TE sensing containment pressure, calibrated to 0.1%FS, with vacuum range 0-30"Hg or pressure range 0-30 psig, or equivalent. Note location of pressure measurement in remarks. N/A [ x] ______
M&TE ID NO._____________Cal due____________
Containment Press/Vac____________psig/"Hg
- c. Verify recorded pressure is between
-0.8 (1.628"Hg) and +1.0 psig [-1.0 and +1.2 psig]. ______
GLH rad1BA0B.Doc 06 0824.1319
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR 69-20232 08/24/10 USE *** Page 5 of 25 STP I-1A (UNIT 1)
ATTACHMENT 12.1 Examinee Handout TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 SR 3.5.1.2 4. RCS Accumulator Volume SR 3.5.1.4
- a. Record current RCS accumulator volume and latest STP C-2 volume, then calculate volume change.
Check the indicator used.
CURRENT %
RCS RCS ACCUMULATOR LEVEL C-2 Level Accumulator VB1 IND OR PPC Point % LEVEL % Change LI-950 [ ] LI950R [X] 65.8 -
______ GLH
______ = GLH 1-1 LI-951 [ ] LI951R [ X]
65.6 GLH
______ =
GLH LI-952 [ ] LI952R [ X]
63.1 GLH
______ =
GLH 1-2 LI-953 [ ] LI953R [X]
65.0 GLH
______ =
GLH LI-954 [ ] LI954R [X]
63.1 1
______ = ______
1 1-3 LI-955 [ ] LI955R [ X]
65.8 665 ______
______ =
11,045 LI-956 [ ] LI956R [X]
64.7 64.0
______ =
+0.7 1-4 LI-957 [ ] LI957R [X]
64.3 63.1
______ =
+1.2 GLH
- b. Verify all current RCS accumulator levels are 59% and 75%. [52% to 82%]
GLH
- c. Verify all RCS accumulator level changes are +3%
[5.6%].
GLH
- d. If any operational draining or filling of an accumulator occurs or if level increase is unacceptable, request chemistry to perform STP C-2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for affected accumulators.
GLH N/A [X] ______
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ATTACHMENT 12.1 Examinee Handout TITLE: MODE 1 Shift Checklist APPL TECH SPEC MODE REFERENCE A. CHECK / VERIFICATION FROM CONTROL ROOM PERF 1 ECG SR 23.7.1 44. Perform a CHANNEL CHECK on Control Room pressurization system radiation monitors:
RM-51 [ ]
RM-52 [ ]
RM-53 [ ]
RM-54 [ ] ______
REMARKS:
Test performers and verifiers:
Name Signature Date/Time Init G. L. Hutchison G. L. Hutchison Today / 0700 GLH
/
/
/
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C:\Documents and Settings\glh1\Local Settings\Temporary Internet Files\Content.IE5\8TYZKDAX\Z101115.001.00000-0010[1].tif Examinee Handout 7/10/11 1 of 2
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Examinee Handout NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL091-A8
Title:
EVALUATE RELEASE UNDER CHANGING PLANT CONDITIONS Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(new)
References:
OP G-1:II Discharge of Liquid Radwaste Rev. 36 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 3 Job Designation: RO/SRO DCPP Task # / Rating: N53650 3.0 Gen KA # / Rating: GEN 2.3.11 Radiation Control 3.8 / 4.3 AUTHOR: JOHN F. BUCKLEY DATE: 04/28/2011 REV. 0
JPM TITLE: EVALUATE RELEASE UNDER CHANGING JPM NUMBER: NRCL091-A8 PLANT CONDITIONS INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Marked up of OP G-1:II (sec 12) and Discharge Permit for PWR 0-2 (CAP A-5), and calculator.
Initial Conditions: Given:
- A discharge of PWR 0-2 is in progress (has been in progress for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />). OP G-1:II is complete through step 12.21.4 (chemistry notified that release is in progress).
- Plant status:
- U-1 is at 50% power, with a normal full power equipment lineup, except that MFP 1-1 is OOS for a control oil leak (RTS is 4 hrs).
Initiating Cue: CWP 1-1 alarmed on ground overcurrent and was shutdown per procedure for evaluation/repair. Evaluate the effect (if any) of this failure on the discharge of PWR 0-2. If any actions are required as the result of this failure, list them on the answer/cue sheet.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Determines that dilution flow is below the minimum required for the release, and takes the following actions (exact words not required)
(note: these actions are found in step 6.9 of OP G-1:II):
- Select OFF on the discharge pump control switch
- Set HCV-647 to zero demand
- (may notify the SFM and chemistry of stopping the discharge, as well as completing the discharge permit, but these actions are not part of the task standard.)
NRCL091-A8 REV 0.DOC PAGE 2 OF 5 REV. 0
JPM TITLE: EVALUATE RELEASE UNDER CHANGING JPM NUMBER: NRCL091-A8 PLANT CONDITIONS INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Reviews OP G-1:II, step 12.21.5, 1.1 Determines that the radwaste criteria for problems during the discharge filter and RE-18 are not a discharge problem.
1.2 Determines that a loss of a CWP will affect dilution flow, and requires evaluation.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Re-evaluates dilution flow for 2.1 Reviews discharge permit, and notes discharge that the required flow is 1.29E6 gpm.
2.2 Using table on step 12.15 of OP G-1:II, determines that dilution flow is less than the amount required by the discharge permit.
2.2 Determines that step 12.21.5 (4th bullet) is met, and goes to step 6.9.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A8 REV 0.DOC PAGE 3 OF 5 REV. 0
JPM TITLE: EVALUATE RELEASE UNDER CHANGING JPM NUMBER: NRCL091-A8 PLANT CONDITIONS INSTRUCTOR WORKSHEET Step Expected Operator Actions
3.1 Select OFF on the discharge pump control switch. **
3.2 Set HCV-647 to zero demand. **
3.3 Notify the SFM that discharge has been terminated due to inadequate dilution flow.
3.4 Notify Chemistry that discharge has been terminated due to inadequate dilution flow.
3.5 Complete the discharge permit and note the reason for discharge termination in the comments section.
Cue: (once the other step 6.9 actions are written down or verbalized)
Another operator will complete the discharge paperwork (G-1:II and CAP A-5).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A8 REV 0.DOC PAGE 4 OF 5 REV. 0
JPM NUMBER: NRCL091-A8 EXAMINEE CUE SHEET Initial Conditions: Given:
A discharge of PWR 0-2 is in progress (has been in progress for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
OP G-1:II is complete through step 12.21.4 (chemistry notified that release is in progress).
- Plant status:
- U-1 is at 50% power, with a normal full power equipment lineup, except that MFP 1-1 is OOS for a control oil leak (RTS is 4 hrs).
Initiating Cue: CWP 1-1 alarmed on ground overcurrent and was shutdown per procedure for evaluation/repair. Evaluate the effect (if any) of this failure on the discharge of PWR 0-2. If any actions are required as the result of this failure, list them on the answer/cue sheet.
ANSWER SHEET (circle one of the two answers (below left), and fill in any actions required, as applicable)
NO ACTION N/A REQUIRED ACTION REQUIRED NRCL091-A8 REV 0.DOC PAGE 5 OF 5 REV. 0
- ISSUED FOR USE BY: _______________________ DATE: ____________ EXPIRES: ____________ ***
1&2 D IABLO C ANYON P OWER P LANT OP G-1:II OPERATING PROCEDURE Rev. 36 UNITS Page 1 of 45 Liquid Radwaste System - Discharge of Liquid Radwaste Examinee Handout 08/25/09 Effective Date QUALITY RELATED Table of Contents
- 1. SCOPE ........................................................................................................... 1
- 2. DISCUSSION.................................................................................................. 1
- 3. RESPONSIBILITIES ....................................................................................... 2
- 4. PREREQUISITES........................................................................................... 2
- 5. PRECAUTIONS AND LIMITATIONS .............................................................. 2
- 6. INSTRUCTIONS ............................................................................................. 3
- 7. REFERENCES ............................................................................................... 5
- 8. RECORDS...................................................................................................... 5
- 9. Discharging Chemical Drain Tank 0-1 (0-2) .................................................... 6
- 10. Discharging Laundry and Hot Shower Tank 0-1 (0-2).................................... 12
- 11. Discharging Floor Drain Receiver 0-1 (0-2) ................................................... 18
- 12. Discharging Process Waste Receiver 0-1 (0-2)............................................. 25
- 13. Discharging Demineralizer Regen Receiver 0-1 (0-2) ................................... 32
- 14. Discharging Laundry/Distillate Tank 0-1 (0-2) ............................................... 39
- 1. SCOPE 1.1 This procedure provides instructions to safely discharge liquid radwaste.
- 2. DISCUSSION 2.1 The primary goal of this procedure is to control liquid radwaste (LRW) discharges and prevent an inadvertent or unmonitored release.
2.2 This procedure should be performed in conjunction with CAP A-5, "Liquid Radwaste Discharge Management."
2.3 This procedure should be performed in conjunction with CAP A-11, "Liquid Radwaste Processing System Selection."
2.4 Liquid radwaste discharges are performed using an "Authorization for Discharge of Liquid Radwaste Batch," Form 69-20877, referred to as the "discharge permit" throughout this procedure.
2.5 Valves for LRW alignment and discharge are controlled by the Aux Board Human-Machine Interface (HMI).
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Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 2 of 45 Examinee Handout UNITS 1&2 2.6 In a section containing steps with more than one column, select the one column corresponding to the evolution to be performed, and perform only that column throughout the section.
- 3. RESPONSIBILITIES 3.1 Operations personnel are responsible for operation of equipment per this procedure.
3.2 The Shift Foreman (SFM) is responsible for compliance with applicable Technical Specifications and Equipment Control Guidelines (ECGs), and authorizing the discharge permit.
3.3 Chemistry is responsible for sampling of tank contents and preparation of the discharge permit.
- 4. PREREQUISITES 4.1 Verify the Liquid Radwaste System is aligned per OP G-1:I, "Liquid Radwaste System - Make Available and Place in Service."
4.2 Dilution water flowrate is adequate per Discharge Authorization requirements.
- 5. PRECAUTIONS AND LIMITATIONS 5.1 Only one LRW discharge can be performed at a time.
5.2 Only a tank NOT aligned for fill can be discharged.
5.3 Verify dilution water flow is maintained throughout the discharge.
5.4 Limit discharge flowrate to 90% of authorized flowrate.
5.5 If for any reason discharge flow is stopped, HIC-647 controller shall be adjusted to 20% demand prior to reinitiating flow.
5.6 Liquid Radwaste Filters 0-1 through 0-5 D/P shall not exceed 50 psid.
5.7 This procedure operates sealed components. Obtain a sealed component change form for use in operating these components.
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Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 3 of 45 Examinee Handout UNITS 1&2
6.2 Discharge Laundry and Hot Shower Tank (LHST) 6.2.1 PERFORM Section 10 to discharge a LHST.
6.3 Discharge Floor Drain Receiver (FDR) 6.3.1 PERFORM Section 11 to discharge a FDR.
6.4 Discharge Processed Waste Receiver (PWR) 6.4.1 PERFORM Section 12 to discharge a PWR.
6.5 Discharge Demineralizer Regen Receiver (DRR) 6.5.1 PERFORM Section 13 to discharge a DRR.
6.6 Discharge Laundry/Distillate Tank (L/DT) 6.6.1 PERFORM Section 14 to discharge a L/DT.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 4 of 45 Examinee Handout UNITS 1&2 6.7 RE-18 high radiation alarm 6.7.1 Check closed 0-RCV-18.
6.7.2 Check open 0-FCV-477.
6.7.3 Select OFF on the discharge pump control switch.
6.7.4 Set HCV-647 to zero demand.
6.7.5 Notify the SFM that discharge has been terminated due to RE-18 alarm.
6.7.6 Notify Chemistry that discharge has been terminated due to RE-18 alarm.
6.7.7 Complete the discharge permit and note the reason for discharge termination in the comments section.
6.8 RE-18 component failure 6.8.1 Check closed 0-RCV-18.
6.8.2 Check open 0-FCV-477.
6.8.3 Select OFF on the discharge pump control switch.
6.8.4 Set HCV-647 to zero demand.
6.8.5 Notify the SFM that discharge has been terminated due to RE-18 failure.
6.8.6 Notify Chemistry that discharge has been terminated due to RE-18 failure.
6.8.7 Complete the discharge permit and note the reason for discharge termination in the comments section.
6.9 Inadequate dilution flowrate 6.9.1 Select OFF on the discharge pump control switch.
6.9.2 Set HCV-647 to zero demand.
6.9.3 Notify the SFM that discharge has been terminated due to inadequate dilution flow.
6.9.4 Notify Chemistry that discharge has been terminated due to inadequate dilution flow.
6.9.5 Complete the discharge permit and note the reason for discharge termination in the comments section.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 5 of 45 Examinee Handout UNITS 1&2
- 7. REFERENCES
7.1 Drawings
7.1.1 106719, "OVID-Liquid Radwaste System"
7.2 Procedures
7.2.1 OP G-1, "Liquid Radwaste System" 7.2.2 OP G-1:III, "Liquid Radwaste System-Clearing System Components" 7.2.3 CAP A-5, "Liquid Radwaste Discharge Management" 7.2.4 CAP A-11, "Liquid Radwaste Processing System Selection"
7.3 Notifications
7.3.1 AR A0217279, "FDR 0-2 Leak Into FDR 0-1"
7.4 Other
7.4.1 ECG 39.3, "Radioactive Liquid Effluent Monitoring Instrumentation"
- 8. RECORDS 8.1 Applicable Checklists SHOULD be attached to the Discharge Permit and forwarded to Chemistry for their review and disposition.
8.2 The Discharge Permit is archived in RMS and SHOULD have the applicable Checklist attached.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 25 of 45 Examinee Handout U1&2 Section 12: Page 1 of 7
- 12. Discharging Process Waste Receiver 0-1 (0-2) PERF VERF 12.1 Check parts 1 and 2 of the discharge permit are complete and signed by GLH BLS Chemistry.
12.2 Refer to Part 1a of discharge permit to verify appropriate tank for GLH BLS discharge:
PWR 0-1 OR PWR 0-2 12.3 IF RE-18 high alarm setpoint (HASP) requires adjustment, N/A THEN direct Chemistry to initiate the setpoint change.
12.4 IF FIT-243 is NOT OPERABLE, N/A THEN perform the following:
12.4.1 Log date and time FIT-243 is declared INOPERABLE in the shift log. _____
12.4.2 Initiate a notification for repair of FIT-243. _____
12.4.3 Review applicable portions of ECG 39.3. _____
12.5 Perform the following to align the discharge flowpath to a unit with an in-service CCW HX:
Table 12.5 Valve Unit with CCW in service (circle one and perform that column only)
U1 U2 LWS-0-436, Fltr Disch to U1 Overboard OPEN CLOSED GLH
_____ BLS LWS-0-439, Fltr Disch to U2 Overboard CLOSED OPEN GLH
_____ BLS 12.6 Check closed LWS-0-1065, L/DT Pp 0-1 and 0-2 disch to LRW. GLH 12.7 Check closed LWS-0-935, PWR Pp 0-1 Educ Isol. GLH 12.8 Check closed LWS-0-936, PWR Pp 0-2 Educ Isol. GLH 12.9 Check open PWR Pp Disch (second off):
PWR 0-1 OR PWR 0-2 LWS-0-934 LWS-0-937 GLH OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 26 of 45 Examinee Handout U1&2 Section 12: Page 2 of 7 12.10 Perform and independently verify the following Auxiliary Saltwater checklist:
Table 12.10 Valve CCW HX in service (circle one and perform that column only)
HX 1-1 HX 1-2 HX 2-1 HX 2-2 SW-1-67, Fltr Disch to 1-1 ASW Ovbd. OPEN CLOSED CLOSED CLOSED GLH
_____ BLS SW-1-68, Fltr Disch to 1-2 ASW Ovbd. CLOSED OPEN CLOSED CLOSED GLH
_____ BLS SW-2-67, Fltr Disch to 2-1 ASW Ovbd. CLOSED CLOSED OPEN CLOSED GLH
_____ BLS SW-2-68, Fltr Disch to 2-2 ASW Ovbd. CLOSED CLOSED CLOSED OPEN GLH
_____ BLS 12.11 Verify OP K-10L, "Sealed Valve Checklist for Liquid Radwaste Discharge System" complete. GLH 12.12 Verify CCW HX aligned for discharge to be in service by D/P indication (VB1). GLH 12.13 Verify RE-18 is operable by performing the following:
12.13.1 Verify the instrument calibration has NOT expired.
12.13.2 Perform a channel check as follows:
- Check Power On light is lit.
- Check Operation Selector switch in "Operate."
- Check Range Selector switch in "Wide."
- Check Low Alarm (red) light is NOT lit.
- Check RE-18 is being recorded on RR-102 at RMS Cabinet III.
N/A 12.13.3 IF RR-102 recorder is INOPERABLE, THEN monitor RE-18 output on the U2 PPC (address R0001A) continuously or by printing out in intervals not to exceed 5 minutes.
12.13.4 Perform a source check on RE-18 as follows:
- a. Notify Control Operator to expect PK 11-23, "RADIATION MON SYS IN TEST."
- b. While holding the Operation Selector switch in the "CHECK SOURCE" position, read the source count rate. 3 x 104
- c. Return Operation Selector switch to "OPERATE."
- d. Record the source count rate on Part 3 of the discharge permit.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 27 of 45 Examinee Handout U1&2 Section 12: Page 3 of 7 12.14 IF RE-18 is NOT OPERABLE, THEN perform the following: N/A 12.14.1 Log date and time RE-18 is declared INOPERABLE in the shift log. _____
12.14.2 Initiate a notification for repair of RE-18. _____
12.14.3 Review applicable portions of ECG 39.3. _____
12.15 Compare the specified "Minimum dilution water flowrate" (Section 2.d of discharge permit) with the current dilution flow, using the following table:
Circ Wtr Pp 1-1 0.425 X 106 gpm Circ Wtr Pp 2-1 0.433 X 106 gpm Circ Wtr Pp 1-2 0.413 X 106 gpm Circ Wtr Pp 2-2 0.433 X 106 gpm ASW Pp 1-1 0.011 X 106 gpm ASW Pp 2-1 0.011 X 106 gpm ASW Pp 1-2 0.011 X 106 gpm ASW Pp 2-2 0.011 X 106 gpm 12.16 IF dilution water flowrate is inadequate, N/A THEN contact Chemistry prior to continuing.
12.17 Verify complete and sign Part 3 of the discharge permit.
12.18 Obtain SFM review and authorization of the discharge permit.
USFM Today / 0712 Shift Foreman Date Time 12.19 Navigate to the Processed Waste Receivers Screen.
12.19.1 Verify Fill Select Switch selected to:
PWR 0-1 OR PWR 0-2 TK 0-2 TK 0-1 12.19.2 Under the Mode Selector menu:
- a. Select Discharge .
- b. Check FIT-243 in service.
- c. Check RM-18 in service.
- d. Select YES .
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Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 28 of 45 Examinee Handout U1&2 Section 12: Page 4 of 7
- e. Perform the following in the "Warning" pop-up:
- 1. Select Operator .
- 2. Enter "Performing Operator ID."
- 3. Select OK .
- 4. Select Shift Foreman .
- 5. Enter name of "Authorizing SFM."
- 6. Select OK .
- 7. Select Batch Number.
- 8. Enter "Discharge Permit Batch Number."
- 9. Select OK .
- 10. Select Click when Entries Made to Continue .
- 11. Verify all entries correct and select YES .
12.19.3 Select Open Controls .
- a. Perform the following in the "Discharge Control-Processed Waste Receiver System" pop-up:
- 1. Select Set Valves and verify OPEN FCV-446.
- 2. IF a pre discharge flush is required, THEN select YES .
OTHERWISE select NO and GO TO step 12.21.
- 3. Verify flush lineup desired and select YES .
- 4. Select Set Valves and verify the following:
- FCV-477 OPEN
- RCV-18 CLOSED OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 29 of 45 Examinee Handout U1&2 Section 12: Page 5 of 7 NOTE: Section 3.b.2 of the discharge permit will specify the volume to be flushed.
Flush volume can be monitored by noting tank level.
12.20 Flush PWR 0-1 or PWR 0-2:
12.20.1 Set HCV-647 to 20%.
12.20.2 Select ON on the appropriate PWR Pp control switch to start flush:
PWR 0-1 OR PWR 0-2 PWRP 0-1 PWRP 0-2 12.20.3 Adjust HCV-647 as desired.
12.20.4 WHEN necessary tank volume has been flushed, THEN select OFF on the running PWR Pp control switch to stop flush.
12.20.5 Set HCV-647 to 20%.
12.20.6 In the "Discharge Control-Processed Waste Receiver System" pop-up:
- a. Select Secure Flush and verify the following:
- FCV-477 CLOSED
12.21.1 Navigate to the Processed Waste Receivers Screen.
- a. Verify HCV-647 set to 20%.
- b. Select ON on the appropriate PWR Pp control switch to commence discharge:
PWR 0-1 OR PWR 0-2 PWRP 0-1 PWRP 0-2
- c. Adjust HCV-647 to 90% of limiting batch flowrate specified on discharge permit.
NOTE: Filter quality can be monitored by observing discharge flowrate, Filter 0-3 (PY-42), and Filter 0-4 (PY-1044) D/P.
12.21.2 Log time and batch number in the shift log.
12.21.3 Record the release information required on the discharge permit.
OP_G-1~IIu3r36.DOC 0820.1606
Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 30 of 45 Examinee Handout U1&2 Section 12: Page 6 of 7 12.21.4 Notify Chemistry the discharge has commenced.
12.21.5 During the discharge if necessary, perform the desired action from the table below:
IF: THEN:
- Discharge filter D/P is excessive GO TO step 12.22
- RE-18 alarms due to high rad GO TO step 6.7
- RE-18 has a component failure GO TO step 6.8
- There is inadequate dilution flow GO TO step 6.9 CAUTION: Do not allow Processed Waste Receiver level to fall below 10%. Damage to pump may result.
12.22 Secure discharge of PWR 0-1 or PWR 0-2.
12.22.1 Navigate to the Processed Waste Receivers Screen.
- a. Select OFF on the running PWR Pp control switch to secure discharge.
- b. Adjust HCV-647 to zero demand.
12.22.2 Refer to OP G-1:III for radwaste filter change if necessary.
12.22.3 IF discharge is complete, THEN GO TO step 12.22.4.
OTHERWISE resume discharge as desired per step 12.21.
12.22.4 Document FM-20 totalizer reading on the discharge permit.
12.22.5 In the "Discharge Control-Processed Waste System" pop-up, select Secure Discharge and verify CLOSED FCV-446. _____ _____
12.23 Complete the discharge permit form as required.
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Liquid Radwaste System - Discharge of Liquid OP G-1:II R36 Radwaste Page 31 of 45 Examinee Handout U1&2 Section 12: Page 7 of 7 COMMENTS:
Batch No:
Checklist Complete: Date/Time: /
SFM Review: Date/Time: /
Hutchison /
____________________________ GLH
_____ Today PRINT LAST NAME/SIGNATURE INIT DATE PRINT LAST NAME/SIGNATURE INIT DATE Sizemore /
____________________________ BLS
_____ Today PRINT LAST NAME/SIGNATURE INIT DATE PRINT LAST NAME/SIGNATURE INIT DATE OP_G-1~IIu3r36.DOC 0820.1606
C:\Documents and Settings\glh1\Local Settings\Temporary Internet Files\Content.IE5\MNYF2NA1\Z110118.001.00000-0100[1].tif Examinee Handout 2011-0-87 Today /
Now Today /
Now Today / 0600 2 of 22
- UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORM WORK or ISSUE FOR 69-20877 06/16/09 USE *** Page 2 of 2 CAP A-5 (UNITS 1 AND 2)
Examinee Handout ATTACHMENT 11.1 TITLE: Authorization for Discharge of Liquid Radwaste Batch Batch No. 2011 87
- 3. RELEASE INFORMATION AND APPROVAL
- a. RE-18 Instrument Check Calibration Expiration Date 10/3/2011 4
Source check reading 3.0 x 10 cpm (If inoperable, refer to OP G-1:II.)
Operable [x] Inoperable [ ]
FIT-243: Operable [ x] Inoperable [ ] (If inoperable, refer to OP G-1:II.)
- b. The following requirements must be met prior to the release:
- 1) Never discharge via cartridge filter 0-2 unless authorized by senior chemistry engineer.
- 2) Flush 3 % of tank contents back to an EDR/DRR per OP G-1:II.
- c. Signed Joe Operator Today / 0710 Approved George USFM Today / 0712 Operator Date/Time Shift Foreman Date/Time CAUTION: If the tank level is different by >1% prior to flush from the tank level stated previously in Section 1.b., THEN THIS PERMIT IS INVALID.
Discharge Adequate Start Time Adequate Start Time Adequate Start Time Adequate Start Time Dilution? +3 hours Dilution? +6 hours Dilution? +9 hours Dilution?
today/0753 [x] Yes [ ] No [ ] Yes [ ] No [ ] Yes [ ] No [ ] Yes [ ] No If at any time during discharge dilution flow rate is NOT adequate, immediately refer to OP G-1:II
- d. Flow totalizer FM-20 at end of discharge Date/Time /
Total elapsed time Min.
Total time discharge is interrupted (e.g., filter changeout) Min.
Actual discharge time (beginning - end - interruptions) Min.
- e. Perform channel check on flow transmitter FIT-243 (or FY-243) Date/Time today / 0801 Verify flow is recording during the release period.
- f. Tank Level prior to flush 97 %
Tank level prior to discharge 94 % = 13,943 gal Tank level after discharge % = gal Volume Discharged = gal
- g. Performed By /
Operator (signature) Date/Time
- h. Comments
- i. Reviewed: / Noted Shift Foreman Date/Time Chemistry Supervision Date radF9D5D.Doc 08 0927.1608
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL091-A9
Title:
PERFORM AN OFF-SITE DOSE ASSESSMENT - GDT RUPTURE Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
References:
EP R-2, Release of Airborne Radioactive Materials Initial Assessment, Rev. 28 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2, 4 Job Designation: SRO DCPP Task # / Rating: 148400 4.2 Gen KA # / Rating: GEN 2.4.38 Emergency Procedures / Plan 4.4 (SRO)
AUTHOR: GARY HUTCHISON DATE: 04/27/2011 REV. 0
JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - JPM NUMBER: NRCL091-A9 GDT RUPTURE INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials:
- EP R-2, Release of Airborne Radioactive Materials Initial Assessment
- Calculator Initial Conditions: Unit 1 was operating at 100% power near EOC when GDT 1-1 rupture disk failed and the relief valve lifted.
The following plant conditions exist:
- Relief valve failed to reseat after lifting.
- Plant Vent Flow Rate on FR-12 is 230,000 CFM.
- RE14/14R/87 are over-ranged.
- RE-29 is reading 4.0 mR/hr.
- PDN program EPR2net is not available.
- No MET tower data is available.
Initiating Cue: The Shift Manager directs you to perform an Off-Site Dose Calculation in accordance with EP R-2, Release of Airborne Radioactive Materials Initial Assessment.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Off-Site Dose Calculation has been completed. (see ANSWER KEY at end of JPM)
NRCL091-A9 REV 0.DOC PAGE 2 OF 9 REV. 0
JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - JPM NUMBER: NRCL091-A9 GDT RUPTURE INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain correct procedure. 1.1 References EP R-2.
Note: Provide exam copy of EP R-2 including attachments.
- 2. Determine the Total Effluent 2.1 Determines release is a Plant Vent Release Rate Release and starts with Attachment 10.1, page 1.
2.2 Fills out section 1.
2.3 In section 2A, enters DIRECT -
Plant Vent Flow Rate as 230,000 CFM. Leaves section 2B blank (may carry 2A rate to flowrate box below 2B as well).
Note: Scientific or other (ie; 230K) notation may be used where appropriate when completing the attachments.
2.4 Reads CAUTION and fills out section 3A as follows:
- Enters 4.0 mR/hr for RE-29.
- Enters 230,000 CFM for plant vent flow rate.
- Calculates and enters a Noble Gas Release Rate of 4.34
(+/-0.04) Ci/sec.
(continued on next page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A9 REV 0.DOC PAGE 3 OF 9 REV. 0
JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - JPM NUMBER: NRCL091-A9 GDT RUPTURE INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 2. (continued) 2.5 Fills out section 3B as follow:
- Enters Noble Gas Release Rate of 4.34 (+/-0.04) Ci/sec.
- Refers to Attachment 10.1, page 3 to determine the correct source term is RCS and circles RCS in Attachment 10.1 section 3B, on page 1.
- Calculates and enters a Total Effluent Release Rate of 4.34
(+/-0.04) Ci/sec.**
Note: Page 2 of 2 of Att 10.1 (atmospheric steam release) will be blank.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 3. Select source term. 3.1 References Attachment 10.1, page 3.
3.2 Places a mark in the GDT Rupture box.
Note: This step may have been done earlier when selecting the source term for Attachment 10.1, page 1. Note that this release rate will not be used, since real data is available.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A9 REV 0.DOC PAGE 4 OF 9 REV. 0
JPM TITLE: PERFORM AN OFF-SITE DOSE ASSESSMENT - JPM NUMBER: NRCL091-A9 GDT RUPTURE INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. Perform dose calculations. 4.1 References Attachment 10.2.
4.2 Fills out section 1.
4.3 Determine MET data is not available and chooses to use DEFAULT /Q value in section 2.
4.4 Reads section 3 and circles appropriate DCF RCS in section 4A.
4.5 Fills out section 4A as follows:
- Enters 4.34 (+/-0.04) Ci/sec
- Enters 5.29E-04 Sec/m3
- Calculates TEDE of 252 (250 to 254) mrem/hr
- Enters 3 hr for default release duration
- Calculates 756 (750 to 764) mrem for TEDE.**
4.6 Does not complete section 4B due to being a GDT rupture.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCL091-A9 REV 0.DOC PAGE 5 OF 9 REV. 0
JPM NUMBER: NRCL091-A9 ANSWER SHEET (4.30 - 4.38)
(4.30 - 4.38)
NRCL091-A9 REV 0.DOC PAGE 6 OF 9 REV. 0
JPM NUMBER: NRCL091-A9 ANSWER SHEET NRCL091-A9 REV 0.DOC PAGE 7 OF 9 REV. 0
JPM NUMBER: NRCL091-A9 ANSWER SHEET (250-254) (752-764)
NRCL091-A9 REV 0.DOC PAGE 8 OF 9 REV. 0
JPM NUMBER: NRCL091-A9 EXAMINEE CUE SHEET Initial Conditions: Unit 1 was operating at 100% power near EOC when GDT 1-1 rupture disk failed and the relief valve lifted.
The following plant conditions exist:
- Relief valve failed to reseat after lifting.
- Plant Vent Flow Rate on FR-12 is 230,000 CFM.
- RE14/14R/87 are over-ranged.
- RE-29 is reading 4.0 mR/hr.
- PDN program EPR2net is not available.
- No MET tower data is available.
Initiating Cue: The Shift Manager directs you to perform an Off-Site Dose Calculation in accordance with EP R-2, Release of Airborne Radioactive Materials Initial Assessment.
NRCL091-A9 REV 0.DOC PAGE 9 OF 9 REV. 0
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 NUCLEAR POWER GENERATION REVISION 28 DIABLO CANYON POWER PLANT PAGE 1 OF 5 EMERGENCY PLAN IMPLEMENTING PROCEDURE UNITS TITLE: Release of Airborne Radioactive Materials Initial Assessment Examinee Handout 1 2 AND INFO ONLY EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED
- 1. SCOPE 1.1 This procedure describes the steps to be taken by on-shift personnel to initially evaluate the off-site consequences of an accidental airborne release that may result in Emergency Plan Activation.
1.2 It does not describe the operation of the plant equipment necessary to terminate or minimize the release. This latter subject is covered in the appropriate E, ECA, and FR series Emergency Procedures for the particular release mechanism.
- 2. DISCUSSION 2.1 An accidental airborne release of radioactive materials that may result in site boundary dose rates in excess of the limits specified in the EP G-1 shall require a prompt initial assessment by the operating staff. This initial release rate and dose assessment is performed using either the Plant Data Network (PDN) program "EPR2net", or manually using Section 7 of this procedure.
2.2 This procedure shall only be used by Control Room personnel to perform initial accident dose assessments. This procedure shall not be used to evaluate compliance with Technical Specification limits during planned effluent releases conducted as part of normal plant operations. The methodology contained in this procedure is intended to provide a rapid and conservative calculation of the projected off-site doses due to an accidental release of airborne radioactive materials. More advanced methodologies are contained in procedures EP RB-9 and EP RB-11 or the appropriate chemistry procedures.
- 3. DEFINITIONS 3.1 Accidental Release: A release of radioactive material unrelated to any planned effluent release evolutions.
3.2 Committed Dose Equivalent (CDE): The dose to the organs or tissues that would be received from an intake of radioactive material by an individual during the 50 years following the intake.
3.3 Committed Effective Dose Equivalent (CEDE): The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the CDE to these organs or tissues.
EP_R-2u3r28.DOC 03B 0419.0958
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 DIABLO CANYON POWER PLANT REVISION 28 Examinee Handout PAGE 2 OF 5 TITLE: Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment 3.4 Deep Dose Equivalent (DDE): Dose associated with exposure of the whole body (depth of 1 cm).
3.5 Total Effective Dose Equivalent (TEDE): The sum of the DDE (for external exposure) and CEDE (for internal exposure).
3.6 TEDE Rate: The time rate of change of Total Effective Dose Equivalent as a function of immersion and inhalation exposure time.
3.7 Thyroid CDE Rate: The time rate of change of Thyroid Committed Dose Equivalent as a function of immersion and inhalation exposure time.
- 4. RESPONSIBILITIES 4.1 Emergency Evaluation Coordinator (EEC) is responsible for performing an initial assessment of an airborne radiological release when directed by the SM.
4.2 Shift Manager (SM) is responsible for determining when an assessment is needed and directing the EEC to implement this procedure based on emergency evaluation priorities.
- 5. PREREQUISITES 5.1 Unified Dose Assessment Center (UDAC) is not activated and performing the function of radiological assessment.
5.2 Shift Manager (SM) has determined, based on plant accident conditions or symptoms of an accidental radiological release, that an initial assessment of projected off-site doses has priority over other actions being performed by the EEC.
The following listed symptoms indicate that an airborne release may be occurring from within the RCA as guidance to the SM:
- There is actual or suspected leakage of water, steam, or noncondensible gases from any vessel or piping system containing primary coolant, liquid radwaste, or gaseous radwaste.
- Damage occurs to a submerged, irradiated fuel assembly with the resultant release of significant quantities of noncondensible gases.
- Alarms occur on in-plant continuous air monitors (CAM)s.
- A fire occurs involving radioactive materials.Ref 11.8
- Verified alarm on radiation monitors RE-14/14R, RE-28/28R, RE-29, RE-15/15R, or RE-24/24R.
- A major radioactive material spill occurs.
EP_R-2u3r28.DOC 03B 0419.0958
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 DIABLO CANYON POWER PLANT REVISION 28 Examinee Handout PAGE 3 OF 5 TITLE: Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment
- 6. PRECAUTIONS 6.1 Do not use SPDS to obtain RMS readings. Radiological Monitor readings off SPDS may be based on different units of measurement than required as input to the calculations.
6.2 If the Main Condenser is available during a SGTR event with a stuck open Safety Relief or 10% Steam Dump to atmosphere, there are two release pathways until the affected SG is isolated. The MSL monitor reading on the affected steam generator encompasses the total release rate of the simultaneous release paths.
6.3 Default release rates are extremely conservative and may result in higher classifications or PARs than would be warranted if actual release indications were available.
6.4 N-16 will be detected on the MSL Radiation Monitors while at power and may cause a false high off-site dose calculation.
6.5 This procedure shall not be used to evaluate compliance to Technical Specifications during planned effluent releases. Such evaluations shall be performed by the Chemistry Department.
6.6 Fuel Handling Accident (FHA) in Containment with Equipment Hatch open is a special case. Use the analyzed default dose rates and doses listed in Attachment 10.1 and go directly to EP G-1 for comparison to the Emergency Action Levels (EALs).
6.7 For plant vent releases, including short duration puff releases such as a ruptured gas decay tank, TRS values for RM-14/14R (cpm) and RM-87 (amps) should be verified and the peak value used for performing the long hand EP R-2 calculation using attachments to this procedure.
- 7. INSTRUCTIONS This calculation can be performed using the Plant Data Network (PDN) program "EPR2net" or by long hand, as follows:
7.1 Release Rate Calculations 7.1.1 Obtain a working copy of Attachment 10.1.
7.1.2 Determine release source location as Plant Vent, Atmospheric Steam Release, or Unmonitored.
CAUTION: Do NOT use SPDS to obtain radiation monitor readings.
7.1.3 Gather and record the required information in accordance with the appropriate section of the form.
NOTE: Plant Vent Extended Range Rad Monitor RE-87 will automatically activate if the Normal Range Gas Monitors RE-14/14R approach their maximum reading.
7.1.4 Perform the required calculation to determine the release rate of Total Effluent and record the results in both this Attachment and Attachment 10.2.
EP_R-2u3r28.DOC 03B 0419.0958
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 DIABLO CANYON POWER PLANT REVISION 28 Examinee Handout PAGE 4 OF 5 TITLE: Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment 7.1.5 If it is not possible to calculate a release rate, refer to the "Default Release Rates" on Page 3 of Attachment 10.1 and choose the most appropriate value for input to Attachment 10.2. For an FHA in containment with equipment hatch open, use default dose rates and doses from Attachment 10.1 and go directly to EP G-1 for comparison to the EALs.
7.2 Off-Site Dose Calculations Calculations may be performed using the Plant Data Network (PDN) program "EPR2net,"
or by long hand, as follows:
7.2.1 Obtain a working copy of Attachment 10.2.
7.2.2 Gather and record the required information in accordance with the appropriate section of the form.
NOTE: Plant Process Computer (PPC) Meteorological Data turn on codes are "METP" (Primary Data) and "METB" (Back-up Data).
7.2.3 Determine the appropriate activity source term and circle the associated Dose Conversion Factor (DCF) to be used in Section 4A and 4B.
7.2.4 Perform the required calculations to determine the TEDE and Thyroid CDE Rates.
7.2.5 Project the Release Duration in hours as input to determining projected doses.
7.2.6 If a duration cannot be projected, use the Default Duration of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
7.2.7 Perform the required calculations to determine the TEDE and Thyroid CDE at the Site Boundary (800 meters).
7.2.8 Obtain an independent verification of your calculation whenever time permits to confirm no errors or incorrect assumptions about plant conditions.
7.3 Reporting the Results 7.3.1 REFER TO EP G-1 and compare the results of the above calculations with the Emergency Action Levels.
7.3.2 REFER TO EP RB-10 and compare the results of the dose calculations with the PAR determination criteria.
7.4 Advise the SM of any EAL thresholds that are exceeded based on site boundary dose rates and doses, or the need to revise PARs due to changing conditions.
7.5 Continuous Actions 7.5.1 As directed by the SM, continue to perform assessment of airborne releases to support evaluation of EAL status and PARs by repeating the above instructions.
7.5.2 Contact Chemistry to request:
- a. A sample of the radioactive effluent (if possible) and in-plant airborne activity.
- b. A confirmatory assessment of the site boundary dose rate from the release.
EP_R-2u3r28.DOC 03B 0419.0958
PACIFIC GAS AND ELECTRIC COMPANY NUMBER EP R-2 DIABLO CANYON POWER PLANT REVISION 28 Examinee Handout PAGE 5 OF 5 TITLE: Release of Airborne Radioactive Materials Initial UNITS 1 AND 2 Assessment
- 8. RECORDS 8.1 All checklists generated during activation of the EOF for drills and exercises are non-quality Good Business Records and shall be retained by Emergency Planning Group for three years.
8.2 All checklists generated during activation of the EOF for a real event are non-quality records and shall be retained in RMS in accordance with AD10.ID2.
- 9. APPENDICES None
- 10. ATTACHMENTS 10.1 "Release Rate Calculations," 02/03/09 10.2 "Off-Site Dose Calculations," 08/05/94 10.3 "EPR2NET Application," 10/20/08 10.4 "Plant Vent Release," 05/12/09 10.5 "Atmospheric Steam Release," 05/12/09
- 11. REFERENCES 11.1 CP M-6, "Fire" 11.2 EP G-1, "Emergency Classification and Emergency Plan Activation" 11.3 EP G-2, "Interim Emergency Response Organization" 11.4 EP RB-9, "Calculation of Release Rate" 11.5 EP RB-10, "Protective Action Recommendations" 11.6 EP RB-11, "Emergency Off-site Dose Calculations."
11.7 EP RB-12, "Plant Vent Iodine and Particulate Sampling During Accident Conditions" 11.8 AR A0595224, "PPC EPR-2 Not Valid for FHA in Containment with Hatch Open" 11.9 PG&E Calculation PAM-0-04-517, Rev. 4, 4/6/97 "Steam Generator Narrow Range Level Uncertainty."
11.10 PG&E Calculation STA-160, Freq., "Estimate of Expected Exposures Associated with a Fuel Handling Accident with Containment Open."
11.11 NRS-RES Calculation No. RA 93-12, New Dose Conversion Factors for EP R-2 and RB-11, Validation and Verification, Rev. 1, 12/15/93.
11.12 NOS-RECE Calculation No. RA 93-04, EP RB-9, Calculation of Release Rate, Rev. 7 and R-2, Release of Airborne Radioactive Materials, Rev. 12, Validation and Verification, Rev. 0, 4/12/93.
11.13 SH&ES Calculation No. EP-94-01, Rev 0, EP R-2, Release of Airborne Radioactive Materials, Rev 17, Validation and Verification.
EP_R-2u3r28.DOC 03B 0419.0958
02/03/09 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE: Release Rate Calculations EP R-2 ATTACHMENT 10.1 Examinee Handout 1 2 AND PLANT VENT RELEASE
- 1. GENERAL INFORMATION Date: Time: Assessment No.
Assessment By: Unit Releasing
- 2. PLANT VENT FLOW RATE DETERMINATION A. DIRECT - Plant Vent Flow Rate FR-12 (0-30x104 CFM (CFM) = (CFM)
OR B. ALTERNATE - Operating Ventilation Equipment (Max No. possible) #Fans (CFM/Fan)
FHB Exhaust (1) x 35,750 = (CFM)
Aux Bldg Exhaust (2) x 73,500 = (CFM)
GE/GW Area (1) x 25,000 = (CFM)
Cont. Purge (1) x 55,000 = (CFM)
Cont. Hydrogen (1) x 300 = (CFM)
Plant Vent Flow Rate = (CFM)
- 3. RELEASE RATE CALCULATION CAUTION: Do NOT use SPDS to obtain monitor readings.
A. NOBLE GAS RELEASE RATE Circle Reading (Units) Conversion Plant Vent Noble Gas Monitor Factor Flow Rate Release Used (CFM) Rate (Ci/sec)
Primary RE-14/14R/87 Ci/cc x 4.72E-04 x Backup RE-29 mR/hr x 4.72E-06 x =
B. TOTAL EFFLUENT RELEASE RATE NOTE: Refer to Page 3 for criteria in choosing RCS, GAP, or CORE below.
Noble Gas Release Total Effluent Total Effluent Rate (Ci/sec) Conversion Factor Release Rate (Ci/sec) x 1.00 (RCS) =
1.11 (GAP) 1.50 (CORE)
NOTE: If it is not possible to calculate a release rate, refer to the DEFAULT RELEASE RATES on Page 3 of this attachment.
GO TO ATTACHMENT 10.2 EP_R-2u3r28.DOC 03B 0419.0958
02/03/09 Page 2 of 2 EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.1 Examinee Handout TITLE: Release Rate Calculations
- 1. GENERAL INFORMATION ATMOSPHERIC STEAM RELEASE Date: Time: Assessment No.
Assessment By: Unit Releasing CAUTION: When critical, N-16 activity seen by MSL Rad Monitors causes invalid readings for offsite dose.
Post-trip, RE-7X reading is valid if the RE-7X monitor showed an initial N-16 response, or responds to checksource.
NOTE: If it is not possible to calculate a release rate, refer to the DEFAULT RELEASE RATES on Page 3.
- 2. STEAM RELEASES - Use this form to calculate steam releases to the atmosphere WHEN NOT critical.
A. Required Information (RUPTURED GENERATOR ONLY)
Check MSL Rad Reading S/G Lvl Level S/G Flow Flow Rate Ruptured S/G Monitor (cpm) Narrow (%) Rate (lbs/hr)
Range If <4E5 use 4E5
[ ] SG 1 RE-71 LI-517 FI-512
[ ] SG 2 RE-72 LI-527 FI-522
[ ] SG 3 RE-73 LI-537 FI-532
[ ] SG 4 RE-74 LI-547 FI-542 B. Alternate Steam Flow Rate (Only if the RUPTURED S/G Flow Rate is otherwise not available)
Valve Type # Valves Lifted Capacity (lbs/hr) Flow Rate (lbs/hr) 10% Steam Dump (1 per S/G) x 4.0E+05 =
Safety Reliefs (5 per S/G) x 8.5E+05 =
Total Steam Flow Rate (lbs/hr) = (lbs/hr)
- 3. RADIATION MONITOR FACTORS (Determined based on S/G NR Level indication) (Enter in Section 4 below.)
S/G Level EMPTY NORMAL FLOODED Narrow Range < 13% 13% - 96% > 96%
Monitor Factor 6.08E-10 6.75E-10 3.07E-10 (DEFAULT)
- 4. RELEASE RATE CALCULATIONS A. TOTAL EFFLUENT RELEASE RATE (RE-7x)
MSL Monitor Reading Flow Rate Monitor Factor Total Effluent Release (cpm) (lbs/hr) Rate (Ci/sec) x x =
GO TO ATTACHMENT 10.2 EP_R-2u3r28.DOC 03B 0419.0958
02/03/09 Page 3 of 3 EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.1 Examinee Handout TITLE: Release Rate Calculations
- 1. SOURCE TERM SELECTION AND DEFAULT RELEASE RATES NOTE: Use default release rate only if actual data is not available or if the release is not being monitored.
A. Check the accident type which most closely resembles the current event.
Default Release Source Rate (Ci/sec) Term Accident Source Condition
[ ] LOCA (w/ core melt) 1.74 E+1 RE-30 or 31 >300R/hr CORE
[ ] LOCA (w/o core melt) 5.74 E+0 RE-30 or RE-31 <300R/hr GAP RE-30 or RE-31 not on scale RCS
[ ] Main Steam Line Break 8.61 E-3 RCS
[ ] Feedwater Line Break 8.61 E-3 RCS
[ ] Blackout 8.62 E-1 RCS
[ ] Locked Rotor 1.57 E-2 GAP
[ ] FHB Accident 1.45 E+1 GAP
[ ] Rod Ejection 1.08 E-2 GAP
[ ] GDT Rupture 4.14 E+1 RCS
[ ] LHUT Rupture 3.10 E+1 RCS
[ ] S/G Tube Rupture 1.65 E+0 NR S/G Level <13% SG - Empty NR S/G Level 13-96% SG - Normal NR S/G Level >96% SG - Flooded
[ ] Containment FHA S.B. Dose TEDE = 13.4 mrem/hr Go Accident with Equip. Rates Thy. CDE = 51.4 mrem/hr Directly to Hatch Open S.B. Doses TEDE = 6.7 mrem EP G-1 Thy. CDE = 25.7 mrem B. Record the Default Release Rate in Attachment 10.2, Section 4 and use the DCF choice that is listed for the specific accident source above.
GO TO ATTACHMENT 10.2 EP_R-2u3r28.DOC 03B 0419.0958
08/05/94 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout Off-Site Dose Calculations EP R-2 ATTACHMENT 10.2 1 2 AND
- 1. GENERAL INFORMATION Date: Time: Assessment No.
Assessment By: Unit Releasing
- 2. METEOROLOGICAL DATA - PPC (Plant Process Computer)
Turn On Codes for Met Data are "METP" (Primary Data) or "METB" (Back-up Data)
Parameter Reading Units DEFAULT Wind Speed (10 Meter Level) meters/sec Wind Direction (10 Meter Level) Degrees Site Boundary X/Q (0.8 km) Sec/m3 5.29E-04
- 3. DCF Determination - Select the most appropriate source term for the DCF using the criteria in Attachment 10.1. Circle the corresponding DCF in Section 4 below.
- 4. DOSE CALCULATIONS - (From data calculated using Attachment 10.1)
A. TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE)
Total Effluent or Site Boundary Projected TEDE Default Release X/Q (0.8 km) DCF TEDE Release (mrem)
Rate (Sec/m3) (circle one) Rate Duration (hr)
(Ci/sec) (mrem/hr) (DEFAULT 3 hrs) 1.1E + 05 (RCS) 3.0E + 06 (Gap )
x x 1.1E + 07 (Core) = x =
Attachment 10.1 1.1E + 05 (SG-Empty) 4.3E + 04 (SG-Normal )
9.3E + 05 (SG-Flooded)
B. THYROID COMMITTED DOSE EQUIVALENT (CDE) (DO NOT COMPLETE FOR GDT, LHUT, OR VCT RUPTURE)
Total Effluent or Site Boundary Projected Default Release X/Q (0.8 km) DCF Thyroid Release Thyroid Rate (Sec/m3) (circle one) CDE Rate Duration (hr) CDE (Ci/sec) (mrem/hr) (DEFAULT 3 hrs) (mrem) 1.5E + 06 (RCS) 6.5E + 07 (Gap )
x x 7.7E + 07 (Core) = x =
Attachment 10.1 1.5E + 06 (SG-Empty) 1.5E + 05 (SG-Normal )
1.4E + 07 (SG-Flooded)
- 5. REPORTING THE RESULTS - (Refer to Section 7.3 of Instructions for details)
A. Refer to EP G-1 for EAL criteria.
B. Implement EP RB-10 for PAR criteria EP_R-2u3r28.DOC 03B 0419.0958
10/20/08 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout EPR2NET Application EP R-2 ATTACHMENT 10.3 1 2 AND
- 1. Start EPR2NET
- a. OPEN the epr2net application:
- 1) Click on the "epr2net" icon on the PDN Console
- 2) IF icon is unavailable, THEN type <http://172.16.20.2/epr2net> in the Internet Explorer "address" field and press ENTER .
- b. Select the Unit Specific release path button Plant Vent or Steam Release
- c. For Plant Vent Release data entry, GO TO Attachment 10.4.
- d. For Atmospheric Steam Release data entry, GO TO Attachment 10.5.
EP_R-2u3r28.DOC 03B 0419.0958
05/12/09 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout Plant Vent Release EP R-2 ATTACHMENT 10.4 1 2AND PLANT VENT RELEASE DATA ENTRY:
- 1. General Information
- a. Enter the "Assessment" number
- 2. Plant Vent Flow Rate Determination:
- a. Validate "DIRECT" plant vent flow rate indicates "OK" in the box to the right of the flow rate.
- b. IF the box says: "UNREL" instead of "OK",
THEN Click on "ALTERNATE", and Place a check mark in the box next to all the fans that are operating.
- 3. Release Rate Calculation:
- a. Noble Gas Release Rate For Ongoing Release:
- 1) IF on scale, AND indicates "OK" to the right of the activity value, THEN select RM-14 or RM-14R, which ever is higher
- 2) IF both RM-14 and RM-14R indicate "UNREL" AND RM-87 equals 1E-12 amps THEN select RM-29.
- 3) IF RM-14 or RM-14R is off scale (5E6 cpm is top of scale)
AND indicates "OK" to the right of the activity value, THEN select RM-87 if it indicates "OK" to the right of the RM-87 activity value.
- 4) IF RM-87 indicates "UNREL" instead of "OK",
THEN select RM-29.
For a Fuel Handling accident or Tank Rupture Release:
- 1) Attempt to perform the calculation at the peak monitor reading (RM-14, RM-87 or RM-29 as appropriate) for the duration of the release.
- b. Release Rate Calculation, Total Effluent Release Rate
- 1) Select the appropriate source term (click on "HELP" for guidance).
- 2) Single Click the "NEXT" button at the bottom of the page. This will open a Dose Calculations window.
CAUTION: Every time you click the "NEXT" button at the bottom of this page, the program creates another Dose Calculations window.
- 3) IF more than one Dose Calculations window is open, THEN close all open Dose Calculations windows and click the "NEXT" button at the bottom of the Plant Vent Release page. This will open a Dose Calculations window.
EP_R-2u3r28.DOC 03B 0419.0958
05/12/09 Page 2 of 2 EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.4 Examinee Handout TITLE: Plant Vent Release DOSE CALCULATIONS DATA ENTRY:
- 1. General Information
- a. Validate current date and time, assessment number, and unit releasing number are the same as the Plant Vent Release page.
- 2. Meteorological Data - PPC
- a. Select Desired Met Data (Primary or Backup)
- 1) Primary is preferred to backup.
- 2) Do not select if any of the 3 parameters indicates "UNREL"
- 3) If both met towers have "UNREL" data, perform a long hand calculation using Attachment 10.1.
- 3. DCF Determination
- a. This carries over from the Plant Vent Release page (do not edit).
- 4. Dose Calculations, Total Effective Dose Equivalent(TEDE)
- a. Total Effective Dose Equivalent (TEDE)
- 1) Verify the projected release duration (default 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />).
a) Enter 0.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> for a release under 15 minutes.
- 2) Enter the calculated TEDE rate in block 10 of the ENF if off-site dose rates are not available form FMTs or PICs.
- 3) Compare the release duration "Total TEDE" against dose values in EALs RG1.2 and RS.1.2 for classification.
- b. Thyroid Committed Dose Equivalent (CDE)
- 1) Compare the release duration "Total CDE" against dose values in EALs RG1.2 and RS.1.2 for classification.
- 5. Print the Plant Vent Release page and the Dose Calculations page.
- 6. Enter the Assessors name at the top of each page.
- 7. Submit the calculation to the SM for approval. Signature on each page.
EP_R-2u3r28.DOC 03B 0419.0958
05/12/09 Page 1 of 1 DIABLO CANYON POWER PLANT TITLE:
Examinee Handout Atmospheric Steam Release EP R-2 ATTACHMENT 10.5 1 2 AND ATMOSPHERIC STEAM RELEASE DATA ENTRY:
- 1. General Information
- a. Enter the "Assessment" number.
- 2. Steam Release Rate
- a. Select the faulted ruptured SG.
- b. Type in the number of relief "valves lifted"
- 3. Radiation Monitor Factors
- a. This section is Information only - no editable fields.
- 4. Release Rate Calculations
- a. No entry required in this section. The monitor factor is changed based on SG level (%) indication in Section 2, Steam Release Rate above. This carries over to the DCF section on the Dose Calculations page.
- 5. Single click the "NEXT" button at the bottom of the page. This will open a Dose Calculations window.
CAUTION: Every time you click the "NEXT" button at the bottom of this page, the program creates another Dose Calculations window.
- 6. IF more than one Dose Calculations window is open, THEN close all open Dose Calculations windows and click the "NEXT" button at the bottom of the Atmosphere Steam Release page. This will open a new Dose Calculations window.
EP_R-2u3r28.DOC 03B 0419.0958
05/12/09 Page 2 of 2 EP R-2 (UNITS 1 AND 2)
ATTACHMENT 10.5 Examinee Handout TITLE: Atmospheric Steam Release DOSE CALCULATIONS DATA ENTRY:
- 1. General Information
- a. Validate current date and time, assessment number, and unit releasing number are the same as the Atmospheric Steam Release page.
- 2. Meteorological Data - PPC
- a. Select Desired Met Data (Primary or Backup)
- 1) Primary is preferred to backup.
- 2) Do NOT select if any of the 3 parameters indicates "UNREL"
- 3) If both met towers have "UNREL" data, perform a long hand calculation using Attachment 10.1.
- 3. DCF Determination
- a. This carries over from the Atmospheric Steam Release page (do not edit). It is based on the PDN input for SG Narrow Range (NR) water level
- 4. Dose Calculations, Total Effective Dose Equivalent(TEDE)
- a. Total Effective Dose Equivalent (TEDE)
- 1) Verify the projected release duration (default 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) a) Enter 0.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> for a "puff" release under 15 minutes.
- 2) Enter this calculated TEDE rate in block 10 of the ENF if off-site dose rates are not available from FMTs or PICs
- 3) Compare the release duration "Total TEDE" against dose values in EALs RG1.2 and RS.1.2 for classification.
- b. Thyroid Committed Dose Equivalent (CDE)
- 1) Compare the release duration "Total CDE" against dose values in EALs RG1.2 and RS.1.2 for classification.
- 5. Print the Atmosphere Steam Release page and the Dose Calculations page.
- 6. Enter the Assessors name at the top of each page.
- 7. Submit the calculation to the SM for approval. Signature on each page.
EP_R-2u3r28.DOC 03B 0419.0958
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJC-C1
Title:
MANUAL START DIESEL GENERATOR 1-2 (2-1)
Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(ref: LJC-085 r17)
Note: This JPM is intended to be simulated in either U-1 or U-2 Control Room.
References:
U-1 EOP E-0, Reactor Trip or Safety Injection, Rev. 39 U-2 EOP E-0, Reactor Trip or Safety Injection, Rev. 30 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2, 3, 4 Job Designation: RO/SRO Rev Comments/TIPs: Made generic for U-1 or U-2 DCPP Task # / Rating: 589600 3.7 Gen KA # / Rating: 064.A4.06 3.9 / 3.9 AUTHOR: JOHN F. BUCKLEY DATE: 04/26/2011 REV. 1
JPM TITLE: MANUAL START DIESEL GENERATOR 1-2 (2-1) JPM NUMBER: NRCLJC-C1 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Provide a copy of U-1 (U-2) EOP E-0, App E (applicable page with step 16 on it allowed) to the student. Clearly state unit and DG to start.
Note: Clearly state the Unit and DG to be started during the initial conditions and cue, below.
Initial Conditions: Given:
- Unit 1 (2) has had a Safety Injection.
- Diesel Generator 1-2 (2-1) did not start.
Initiating Cue: You are the Unit 1 (2) Control Operator and have been directed by the Shift Foreman to start Diesel Generator 1-2 (2-1) from the Control Room, in accordance with EOP E-0, Appendix E, Step 16a RNO.
Isochronous operation is desired.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Diesel Generator 1-2 (2-1) started and in the isochronous mode of operation.
NRCLJC-C1 rev 1.doc PAGE 2 OF 7 REV. 1
JPM TITLE: MANUAL START DIESEL GENERATOR 1-2 (2-1) JPM NUMBER: NRCLJC-C1 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References EOP E-0, Appendix E.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Place diesel generator 1-2 (2-1) in **********************************
MANUAL. Cue: Switch position is AS SEEN.
2.1 Places Mode Selector Switch in MANUAL. **
Cue: Switch position is MANUAL.
DG 1-2 (2-1) Trouble and DG 1-2 (2-1) on Local Control alarms are ON (PK13-20, PK17-03).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-C1 rev 1.doc PAGE 3 OF 7 REV. 1
JPM TITLE: MANUAL START DIESEL GENERATOR 1-2 (2-1) JPM NUMBER: NRCLJC-C1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. Start diesel generator 1-2 (2-1). **********************************
Cue: Switch position is AS SEEN.
3.1 Takes the Man Mode Stop/Start to START. **
Cue: DG 1-2 (2-1) Cranking and DG 1-2 (2-1) Strt-Turbo Air Press alarms are ON (PK17-02, PK17-09) 3.2 Verifies that D/G 1-2 (2-1) is running.
Cue: (if/when checked) DG is at 900 rpm, 120 vac, and 60 Hz. The white power available light for DG 1-2 (2-1) is ON.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-C1 rev 1.doc PAGE 4 OF 7 REV. 1
JPM TITLE: MANUAL START DIESEL GENERATOR 1-2 (2-1) JPM NUMBER: NRCLJC-C1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. Place D/G in ISOC mode. **********************************
Cue: Switch position is AS SEEN.
4.1 Places Mode Selector Switch to AUTO. **
Cue: Switch position is AUTO.
PK17-03 is OUT.
Cue: (not required, and only if D/G Shutdown Rly & Alarm Reset PB is pushed) PK13-20 and PK17-09 are OUT .
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-C1 rev 1.doc PAGE 5 OF 7 REV. 1
JPM TITLE: MANUAL START DIESEL GENERATOR 1-2 (2-1) JPM NUMBER: NRCLJC-C1 ATTACHMENT 1, SIMULATOR SETUP This is a simulate JPM. Simulator setup is N/A.
NRCLJC-C1 rev 1.doc PAGE 6 OF 7 REV. 1
JPM NUMBER: NRCLJC-C1 EXAMINEE CUE SHEET Initial Conditions: Given:
- Unit 1 (2) has had a Safety Injection.
- Diesel Generator 1-2 (2-1) did not start.
Initiating Cue: You are the Unit 1 (2) Control Operator and have been directed by the Shift Foreman to start Diesel Generator 1-2 (2-1) from the Control Room, in accordance with EOP E-0, Appendix E, Step 16a RNO.
Isochronous operation is desired.
NRCLJC-C1 rev 1.doc PAGE 7 OF 7 REV. 1
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJC-C2
Title:
RESPOND TO SATURATED CORE CONDITIONS Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(new JPM)
Note: This simulate task may be performed in U-1 or U-2.
References:
U-1 EOP FR-C.3,, Response to Saturated Core Conditions, Rev 10A U-2 EOP FR-C.3,, Response to Saturated Core Conditions, Rev 5A Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 5 Job Designation: RO/SRO Rev Comments/TIPs: Rev 1 - changed out C2 for a new task (per NRC, previous task too long and complex to cue) (no rev bars, due to new task)
DCPP Task # / Rating: 321200 (RO) / 832400 (SRO) 3.3 / 3.2 Gen KA # / Rating: E07.EA1.1 3.6 / 3.6 AUTHOR: JOHN F. BUCKLEY DATE: 04/26/2011 REV. 1
JPM TITLE: RESPOND TO SATURATED CORE CONDITIONS JPM NUMBER: NRCLJC-C2 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Provide a copy of U-1 (U-2) EOP FR-C.3, to the student.
Note: Clearly state the Unit to be performed on during the initial conditions and cue, below.
Initial Conditions: Given:
- Unit 1(2) has experienced a Safety Injection.
- RCS pressure 1800 psig and dropping slowly
- RCS temperature above 600 °F, and rising slowly
- RCS Subcooled margin (SCM) at 5 °F, and dropping.
- The SFM has been informed of and has confirmed a valid YELLOW PATH on CORE COOLING, and had decided to transition to EOP FR-C.3 to deal with saturated RCS conditions.
Initiating Cue: The SFM directs you to perform EOP FR-C.3, Response to Saturated Core Conditions.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: EOP FR-C.3 has been completed, and the Rx Vessel Head Vents have been closed.
NRCLJC-C2 rev 1.doc PAGE 2 OF 8 REV. 1
JPM TITLE: RESPOND TO SATURATED CORE CONDITIONS JPM NUMBER: NRCLJC-C2 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References EOP FR-C.3.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Checks applicability of **********************************
EOP ECA-3.2.. Cue: EOP E-1 was the procedure in effect.
2.1 Determines that ECA-3.2 was not procedure in effect, and continues to next procedure step.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 3. Checks RHR system - NOT in Note: The RHR in service noted in service. this step refers to normal RHR cooling lineup, not an ECCS injection lineup (ie; it is not in service). 8980 is the ECCS suction valve for RHR, and 8702/8702 are the RHR cooling suction valves.
3.1 Determines that the RHR system is not lined up for service (is in normal ECCS lineup), and proceeds to next step Cue: (if valve 8980 is checked, to confirm RHR aligned for ECCS injection) Valve is AS-SEEN (open). (if 8701/8702 checked)
Valves are AS-SEEN.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-C2 rev 1.doc PAGE 3 OF 8 REV. 1
JPM TITLE: RESPOND TO SATURATED CORE CONDITIONS JPM NUMBER: NRCLJC-C2 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. Verifies ECCS Flows. 4.1 Verifies Charging Injection flow >
100 gpm.
Cue: (when checked) FI-917 is reading 220 gpm, and stable.
4.2 Checks RCS wide range pressure
< 1650 psig (above SI pp discharge).
Cue: (when checked, on any of several meters, the PPC, or chart recorder) RCS pressure is 1790 psig, and dropping slowly.
4.3 Determines that RCS pressure is above SI Pp discharge, and proceeds to next step.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-C2 rev 1.doc PAGE 4 OF 8 REV. 1
JPM TITLE: RESPOND TO SATURATED CORE CONDITIONS JPM NUMBER: NRCLJC-C2 INSTRUCTOR WORKSHEET Step Expected Operator Actions
Cue: (when checked) Block valves are AS-SEEN.
5.2 Determines PZR PORV status (closed).
Cue: (when checked) PORVs are AS-SEEN.
5.3 Determines PORV block valve status (all open).
Cue: (when checked) PORV block valves are AS-SEEN.
5.4 Determines Rx Vessel Head Vent Status.
Cue: (when checked) All head vent valves are RED light ON, GREEN light OFF, with the control switches in OPEN.
(continued on next page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-C2 rev 1.doc PAGE 5 OF 8 REV. 1
JPM TITLE: RESPOND TO SATURATED CORE CONDITIONS JPM NUMBER: NRCLJC-C2 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 5. (continued) Note: The following valve manipulations may be performed in any order.
Cue: (for each valve, as operated) The switch is in CLOSE, with the GREEN light ON, and RED light OFF.
5.5 Closes 8078A by placing its control switch in CLOSE. **
5.6 Closes 8078B by placing its control switch in CLOSE. **
5.7 Closes 8078C by placing its control switch in CLOSE. **
5.8 Closes 8078D by placing its control switch in CLOSE. **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 6. Return to procedure and step in 6.1 Leaves EOP FR-C.3.
effect.
Cue: Other operators will continue with EOP E-1, and monitoring of the CSFSTs.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-C2 rev 1.doc PAGE 6 OF 8 REV. 1
JPM TITLE: RESPOND TO SATURATED CORE CONDITIONS JPM NUMBER: NRCLJC-C2 ATTACHMENT 1, SIMULATOR SETUP This is a Control Room simulated task, so the simulator is not used.
NRCLJC-C2 rev 1.doc PAGE 7 OF 8 REV. 1
JPM NUMBER: NRCLJC-C2 EXAMINEE CUE SHEET Initial Conditions: Given:
- Unit 1(2) has experienced a Safety Injection.
- RCS pressure 1800 psig and dropping slowly
- RCS temperature above 600 °F, and rising slowly
- RCS Subcooled margin (SCM) at 5 °F, and dropping.
- The SFM has been informed of and has confirmed a valid YELLOW PATH on CORE COOLING, and had decided to transition to EOP FR-C.3 to deal with saturated RCS conditions.
Initiating Cue: The SFM directs you to perform EOP FR-C.3, Response to Saturated Core Conditions.
NRCLJC-C2 rev 1.doc PAGE 8 OF 8 REV. 1
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJC-S1
Title:
RESPOND TO LOW ACCUMULATOR LEVEL Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(ref: LJC-016 r25A)
References:
AR PK02-10, ACCUM LEVEL HI-LOW, Rev. 17A OP B-3B:I, Accumulators - Fill and Pressurize, Rev. 27 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 30 minutes Critical Steps: 6, 7, 8, 9, 10, 11 Job Designation: RO/SRO Rev Comments/TIPs:
DCPP Task # / Rating: 48400 3.1 Gen KA # / Rating: GEN.2.4.50 4.2 / 4.0 AUTHOR: JOHN F. BUCKLEY DATE: 04/26/2011 REV. 1
JPM TITLE: RESPOND TO LOW ACCUMULATOR LEVEL JPM NUMBER: NRCLJC-S1 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab.
Initial Conditions: Unit 1 is at 100% power. Annunciator PK02-10 ACCUM LEVEL HI-LO has just been received.
Initiating Cue: You are directed to restore Accumulator 1-3 to normal parameters.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Accumulator 1-3 level is restored, associated alarms are cleared and the SI system alignment is returned to normal.
NRCLJC-S1 rev 1.doc PAGE 2 OF 8 REV. 1
JPM TITLE: RESPOND TO LOW ACCUMULATOR LEVEL JPM NUMBER: NRCLJC-S1 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References AR PK02-10.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Confirm abnormal condition. **********************************
Cue: The SFM is addressing all Technical Specification requirements at this time.
2.1 Checks LI-954 and LI-955 to verify alarm is not due to an instrument failure.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 3. Verify fill and drain paths isolated. 3.1 Verifies the following valves closed:
- a. 9357A
- b. 9357B
- c. 8876C (may check all)
- d. 8878C (may check all) 3.2 Calls auxiliary watch to close or check closed 9352C.
Cue: 9352C is closed (or all if asked)
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S1 rev 1.doc PAGE 3 OF 8 REV. 1
JPM TITLE: RESPOND TO LOW ACCUMULATOR LEVEL JPM NUMBER: NRCLJC-S1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. Obtain the correct procedure. 4.1 References OP B-3B:I, Step 6.2, and reviews applicable P&Ls.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 5. Verify valves open. 5.1 Reads CAUTION 5.2 Checks RCS Pressure > 1700 psig.
5.3 Verifies Open the following valves:
- 8974A
- 8974B
- 8976
- 8923A Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 6. Start SI pump 11 and allow it to 6.1 Reads Cautions prior to performing run on recirculation. next step.
6.2 Starts SI pump 11. **
6.3 Checks for proper operation of the pump (normal press/amps).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 7. Open SI pump 11 discharge test 7.1 Opens 8883. **
line and accumulator fill valve, SI-1-8883.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S1 rev 1.doc PAGE 4 OF 8 REV. 1
JPM TITLE: RESPOND TO LOW ACCUMULATOR LEVEL JPM NUMBER: NRCLJC-S1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 8. Open accumulator test header 8.1 Opens 8871. **
isolation valve, SI-1-8871.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 9. Open accumulator fill valve, 9.1 Reads CAUTION SI-1-8878C, to increase accumulator level. 9.2 Opens 8878C. **
9.3 Monitors accumulator level increase.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 10. Secure filling the accumulator at 10.1 Closes 8878C when accumulator approximately 67 % level. level reaches approx. 67%. ** (hi/lo level alarms off).
10.2 Verifies SI Pump Running for > 15 minutes.
Cue: SI pump 11 has run for 15 minutes.
10.3 Shut down SI pump 11. **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S1 rev 1.doc PAGE 5 OF 8 REV. 1
JPM TITLE: RESPOND TO LOW ACCUMULATOR LEVEL JPM NUMBER: NRCLJC-S1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 11. Depressurize the fill and drain 11.1 Reads CAUTION header.
11.2 Open, then Close 8961 as necessary to depressurize the fill and drain header. (to < 100 psig) **
Cue: The SFM is addressing all Technical Specification requirements at this time.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 12. Restore system alignment 12.1 Closes 8871.
12.2 Closes 8883.
Note: Operator may refer to OP O-3.
12.3 Notifies the Chemistry Section for a boron sample.
Cue: Chemistry is notified 12.4 Verifies annunciator PK02-05 and PK02-10 windows are OUT.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S1 rev 1.doc PAGE 6 OF 8 REV. 1
JPM TITLE: RESPOND TO LOW ACCUMULATOR LEVEL JPM NUMBER: NRCLJC-S1 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).
Go to RUN.
Enter drill file 1016, or manually insert the following:
Command Description
- 1. mal sis1c act,100,0,0,d,80 Lowers level in accumulator 13
- 2. frz when xv1d049m.lt.59 Freezes simulator when accumulator 13 level is less than 59%.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRCLJC-S1 rev 1.doc PAGE 7 OF 8 REV. 1
JPM NUMBER: NRCLJC-S1 EXAMINEE CUE SHEET Initial Conditions: Unit 1 is at 100% power. Annunciator PK02-10 ACCUM LEVEL HI-LO has just been received.
Initiating Cue: You are directed to restore Accumulator 1-3 to normal parameters.
NRCLJC-S1 rev 1.doc PAGE 8 OF 8 REV. 1
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJC-S2
Title:
ESTABLISH STEADY STATE CONDITIONS AFTER A ROD MISALIGNMENT Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(ref: LJC-022 r26)
References:
OP AP-12B, Control Rod Misalignment, Rev. OTSC for Rev 11B14 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes Critical Steps: 2, 3 Job Designation: RO/SRO Rev Comments/TIPs:
DCPP Task # / Rating: 80200 4.0 Gen KA # / Rating: 001.A2.03 3.5 / 4.2 AUTHOR: JOHN F. BUCKLEY DATE: 04/26/2011 REV.13
JPM TITLE: ESTABLISH STEADY STATE CONDITIONS JPM NUMBER: NRCLJC-S2 AFTER A ROD MISALIGNMENT INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab.
Initial Conditions: Given:
- The plant is at approximately 75% power ramping down to 50% at 5 MW/minute.
- The rods are in AUTO
- A boration in progress.
Initiating Cue: PK03-25 has alarmed. You are directed by the Shift Foreman to take actions to stabilize the plant per the appropriate plant procedures.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: The plant has been stabilized and Tavg matched to Tref (+/-1.5°F) in accordance with plant procedures.
NRCLJC-S2 rev 1.doc PAGE 2 OF 6 REV.1
JPM TITLE: ESTABLISH STEADY STATE CONDITIONS JPM NUMBER: NRCLJC-S2 AFTER A ROD MISALIGNMENT INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Obtain the correct procedure. 1.1 References OP AP-12B.
(Note: OP AP-12B may be 1.2 Determines that rod K2 is entered directly or from ARP misaligned.
PK03-25)
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Place Rod Control in MANUAL. 2.1 Turns the ROD BANK/MODE SELECT switch to the MAN position. **
2.2 Reads NOTE.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCLJC-S2 rev 1.doc PAGE 3 OF 6 REV.1
JPM TITLE: ESTABLISH STEADY STATE CONDITIONS JPM NUMBER: NRCLJC-S2 AFTER A ROD MISALIGNMENT INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. ESTABLISH Steady State Plant 3.1 Presses the HOLD button on the Conditions: Triconex DEH Turbine Controller
- a. Stop any turbine load panel. **
changes 3.2 Determines that a boration is in
- b. Stop any RCS Boration in progress and presses the STOP progress button on the makeup
- c. Match TAVG-TREF by controller. **
either 3.3 Verifies red START light is on
- Turbine load changes and boration has stopped.
- Boration/dilution Note: Operator may return makeup control to AUTO.
3.4 Matches T AVG -T REF .
- Raises turbine load to lower T avg and/or
- Borates to lower T avg Note: this substep is not a critical step as written, since T ave is already within 1.5°F of T ref . If excessive time is taken to place the turbine on hold, and 1.5°F deviation is exceeded, then action must be taken and this substep becomes critical (operator may also choose to allow existing boration to hit RCS and adjust Tave)
Cue: Once the above actions are completed, tell the operator that other operators will complete the procedure.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
NRCLJC-S2 rev 1.doc PAGE 4 OF 6 REV.1
JPM TITLE: ESTABLISH STEADY STATE CONDITIONS JPM NUMBER: NRCLJC-S2 AFTER A ROD MISALIGNMENT INSTRUCTOR WORKSHEET Initialize the simulator to the IC-511 (75%, MOL).
Update RODCONFIG and DELTAI (drill 72) on PPC.
Go to RUN RUN Drill File 1022 (or manually insert the following)
Command Description mal rod4a act,1,k2,0,d,0 Sticks rod K2 cih mcrfns(52) = mcrfpa(14) + 15 Sets K2 rod > 12 steps higher than the rest of bank With the simulator running, complete the following:
- Place MW feedback IN
- Set 5 MW/min load ramp rate
- Set 550 MW in TARGET window and press GO/Enable to start ramp.
- STOP auto makeup, select BORATE, and set 100 gallons or boric acid into the makeup controller at 5 gal/min; position the makeup MODESELECTOR (43/MU) switch to BORATE, then START the boration.start the boration.
- Go to FRZ Note: due to AP-12B now only requiring turbine or boration adjustments if > 1.5°F deviation, action will only be taken by the examinee during that step if excessive time lapses between taking the rods to manual and stopping the turbine ramp. This setup will normally leave the deviation @ 1.0°F to 1.5°F, since rods were in auto during the setup.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRCLJC-S2 rev 1.doc PAGE 5 OF 6 REV.1
JPM NUMBER: NRCLJC-S2 EXAMINEE CUE SHEET Initial Conditions: Given:
- The plant is at approximately 75% power ramping down to 50% at 5 MW/minute.
- The rods are in AUTO
- A boration in progress.
Initiating Cue: PK03-25 has alarmed. You are directed by the Shift Foreman to take actions to stabilize the plant per the appropriate plant procedures.
NRCLJC-S2 rev 1.doc PAGE 6 OF 6 REV.1
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJC-S3
Title:
RESPOND TO A LOSS OF CCW TO THE LETDOWN HEAT EXCHANGER Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(ref: LJC-126, r17)
OP AP-11, Malfunction of Component Cooling Water System, Rev 25
References:
OP B-1A:IV, Excess Ltdn Place in Service/Remove from Service, Rev. 18.
Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 3, 4, 5, 6, 8, 9 Job Designation: RO/SRO Rev Comments/TIPs:
DCPP Task # / Rating: 129400 4.0 Gen KA # / Rating: 004.A4.06 3.6 / 3.1 AUTHOR: JOHN F. BUCKLEY DATE: 04/26/2011 REV. 1
JPM TITLE: RESPOND TO A LOSS OF CCW TO THE JPM NUMBER: NRCLJC-S3 LETDOWN HEAT EXCHANGER INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Provide a copy of the reference procedure (partial procedure allowed), if the task is being done in the plant or lab.
Initial Conditions: Given:
- Unit 1 is operating at 100% power.
- TCV-130 has failed closed with TCV-130 in AUTO.
Initiating Cue: The Shift Foreman directs you to perform the actions necessary to address the failure of TCV-130.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Excess Letdown in service and normal letdown secured.
NRCLJC-S3 REV 1.DOC PAGE 2 OF 9 REV. 1
JPM TITLE: RESPOND TO A LOSS OF CCW TO THE JPM NUMBER: NRCLJC-S3 LETDOWN HEAT EXCHANGER INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Check TCV-130 controlling 1.1 May confirm diagnoses of TCV-130 letdown temperature. failure by observing high letdown temperature on TI-130 with TCV-130 controller output at 100%.
Note: Operator may shift the TCV-130 controller to MANUAL and attempt to raise CCW flow, but the controllers output is already at 100%. This step may be done prior to use of OP AP-11, or as part of step 1 of section D.
Note: The operator may chose to isolate letdown prior to OP AP-11 entry (for safety concerns). This is a valid concern and allowed by OP1.DC10.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Obtains the correct procedure. 2.1 Refers to OP AP-11, Section D, after concluding that CCW has been lost to the letdown HX..
Note: Operator may also refer to AR PK04-21 (optional) (it will also direct the operator to section D of OP AP-11).
2.2 Confirms that TCV-130 will not open to cool the letdown HX (see above note).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S3 REV 1.DOC PAGE 3 OF 9 REV.1
JPM TITLE: RESPOND TO A LOSS OF CCW TO THE JPM NUMBER: NRCLJC-S3 LETDOWN HEAT EXCHANGER INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. Isolates letdown. 3.1 Observes that 8149A and 8149B are already CLOSED.
3.2 CLOSES 8149C. **
3.3 CLOSES LCV-459 and LCV-460**
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 4. Isolate normal charging 4.1 Reduces charging flow to minimum while maintaining 8 to 13 GPM seal injection flow to each RCP
("minimum" is 8-13 gpm to the RCP seals). **
4.2 CLOSES 8146.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 5. Place Excess Letdown Heat 5.1 References OP B-1A:IV Exchanger in service. 5.2 Notifies RP Foreman to implement SPG-3 due to possible changing radiological conditions.
Cue: RP has been notified to check rad postings.
5.3 Reads Note prior to step 6.1.2.
Cue: Flushing is required. The RCDT has ample room for the flush.
5.4 Places 8143 to Divert (RCDT) position. **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S3 REV 1.DOC PAGE 4 OF 9 REV.1
JPM TITLE: RESPOND TO A LOSS OF CCW TO THE JPM NUMBER: NRCLJC-S3 LETDOWN HEAT EXCHANGER INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 6. ESTABLISH CCW 6.1 OPENS FCV-361. **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 7. CHECK pressure control valve 7.1 CHECK HCV-123 CLOSED (demand is zero).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 8. OPEN isolation valves 8.1 OPENS 8166. **
8.2 OPENS 8167. **
Cue: The ABW will monitor RCDT level.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S3 REV 1.DOC PAGE 5 OF 9 REV.1
JPM TITLE: RESPOND TO A LOSS OF CCW TO THE JPM NUMBER: NRCLJC-S3 LETDOWN HEAT EXCHANGER INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 9. ESTABLISH excess letdown 9.1 Reads CAUTIONs and NOTEs prior flow. to Step 6.1.7.
9.2 SLOWLY OPENS Excess Letdown Press Control valve HCV-123. **
9.3 Observes rise in excess letdown temperature (TI-122).
9.4 Reads NOTEs prior to and following Step 6.1.8.
9.5 ADJUST HCV-123 to maintain letdown temperature (TI-122) less than 190°F.
Cue: (one or two minutes after HCV-123 first opened) The Aux Bldg Watch reports that > 40 gallons have been flushed to the RCDT.
Cue: The SFM directs you to maximize excess letdown flow, as allowed by the procedure. The BOPCO will monitor the containment sumps for Excess Ltdn HX leakage.
9.6 Raises demand on HCV-123 to maximize excess letdown flow (should be full open). **
(continued on next page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S3 REV 1.DOC PAGE 6 OF 9 REV.1
JPM TITLE: RESPOND TO A LOSS OF CCW TO THE JPM NUMBER: NRCLJC-S3 LETDOWN HEAT EXCHANGER INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 9. (continued) 9.7 Places 8143 in Normal position. **
Cue: (once examinee is done throttling HCV-123 open) The SFM will have another operator complete OP B-1A:IV and OP AP-11. The CO will control Pzr Level.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time:
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S3 REV 1.DOC PAGE 7 OF 9 REV.1
JPM TITLE: RESPOND TO A LOSS OF CCW TO THE LETDOWN JPM NUMBER: NRCLJC-S3 HEAT EXCHANGER ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).
Enter drill file 1126 or manually insert the following Command Description
- 1. CNV CVC7 2,0,0,0,d,0 TCV-130 fails closed
- 2. RUN 45 Run simulator for 45 seconds to allow alarms to actuate On status board update Excess Letdown boron concentration to 2200 ppm boron.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRCLJC-S3 REV 1.DOC PAGE 8 OF 9 REV.1
JPM NUMBER: NRCLJC-S3 EXAMINEE CUE SHEET Initial Conditions: Given:
- Unit 1 is operating at 100% power.
- TCV-130 has failed closed with TCV-130 in AUTO.
Initiating Cue: The Shift Foreman directs you to perform the actions necessary to address the failure of TCV-130.
NRCLJC-S3 REV 1.DOC PAGE 9 OF 9 REV.1
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJC-S4
Title:
TRANSFER TO COLD LEG RECIRCULATION Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat _____ Unsat _____ Total Time: _______ TCOA Time: ______
Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(ref: LJC-027A, r0)
References:
EOP E-1.3, Transfer to Cold Leg Recirculation, Rev. 29 OP1.ID2, TCOAs, Rev 3 (& TCOA database); TCOA item 8 Alternate Path: Yes X No Time Critical: Yes X No (TCOA is time critical)
Time Allotment: 12 minutes.
Critical Steps: 1, 3, 4, 5, 8, 10 Job Designation: RO/SRO Rev Comments/TIPs:
DCPP Task # / Rating: 331200, 43200, 324800, 323600, 324600 3.5 / 4.5 / 4.0 / 4.0 / 4.0 (all RO)
Gen KA # / Rating: 011.EA1.11 4.2 / 4.2 AUTHOR: JOHN F. BUCKLEY DATE: 04/26/2011 REV. 1
JPM TITLE: TRANSFER TO COLD LEG RECIRCULATION JPM NUMBER: NRCLJC-S4 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Provide a copy of the reference procedure if the task is being done in the plant or lab. If performing on the simulator, provide the student with the "cart" EOP E-1.3.
Initial Conditions: Unit 1 experienced a LBLOCA and RWST level has decreased to 33%.
Initiating Cue: Given:
- The USFM directs you to perform EOP E-1.3 to align RHR for cold leg recirculation and to provide suction to the SI pumps and CCPs. RHR PP 1-2 did not stop @ 33%, and could not be stopped from the Control Room.
- Step 1, App EE of EOP E-1.3, has been completed (using time compression); you are to start at step 2 of E-1.3.
- This is a time critical JPM.
- You may take a couple of minutes to preview the procedure before the task begins. Time begins when the simulator is placed in RUN.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: RHR has been aligned to the suction of the SI pumps and CCPs for cold leg recirculation up through step 11.
Time Critical This JPM was evaluated against TCOA # 8 (Operator must transfer to Operator Action cold leg recirculation within 10 minutes after RWST reaches low level (TCOA): set point [case 2 - one RHR pp (1-2) does not stop from control room for up to 5 min after the RWST reaches 33%]).
This TCOA:
- is applicable to this JPM; the appropriate steps will be designated as critical, and the TCOA will be designated as time critical
- has a start time when the simulator is placed in RUN (RWST @
33%); the finish time is when one train of RHR is aligned for cold leg recirc (step 11e, when 8804A is OPEN); the time limit is 10 minutes).
NRCLJC-S4 rev 1.doc PAGE 2 OF 9 REV. 1
JPM TITLE: TRANSFER TO COLD LEG RECIRCULATION JPM NUMBER: NRCLJC-S4 INSTRUCTOR WORKSHEET Start Time: (also start time for TCOA)
Step Expected Operator Actions
1.2 Dispatches a Nuclear Operator to locally open the breaker for RHR PP 1-2. **
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Verify RHR PP 1-1 stopped. 2.1 Observes that RHR PP 1-1 is not running (green light ON and/or no amps).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 3. Close 8700A, RHR pump 1 3.1 Closes 8700A. **
normal suction valve.
3.2 Observes green light (only) ON for 8700A.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 4. Close 8716A and B, RHR pump 4.1 Closes 8716A and B. **
discharge crosstie valves.
4.2 Observes green lights (only) ON for 8716A and 8716B.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S4 rev 1.doc PAGE 3 OF 9 REV. 1
JPM TITLE: TRANSFER TO COLD LEG RECIRCULATION JPM NUMBER: NRCLJC-S4 INSTRUCTOR WORKSHEET Step Expected Operator Actions
5.2 Closes 8974A and 8974B. **
5.3 Observes green lights (only) ON for 8974A and 8974B.
5.4 Closes 8105 and 8106. **
5.5 Observes green lights (only) ON for 8105 and 8106.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 6. Checks Containment Recirc Sump 6.1 Observes Containment Recirc Sump Level. Level > 92' on LI-940 & 941.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 7. Verify RHR PP 1-2 Alignment. 7.1 Observes that RHR PP 1-2 is running (red light ON and/or amps indicated).
7.2 Continues in procedure to step to crosstie SI and CCP suctions.
Note: Trying to place the 1-2 RHR PP in recirc while it is still running constitutes a failure. Also, if the 1-2 RHR PP has been stopped locally, 8700B is still OPEN, and this would still require going to the RNO, since the A/ER step is only a "Check" (if the examinee aligns the 1-2 RHR PP for recirc, it would not be IAW the procedure).
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S4 rev 1.doc PAGE 4 OF 9 REV. 1
JPM TITLE: TRANSFER TO COLD LEG RECIRCULATION JPM NUMBER: NRCLJC-S4 INSTRUCTOR WORKSHEET Step Expected Operator Actions
8.2 Observes red lights (only) ON for 8807A and 8807B.
8.3 Observes both ECCS CCPs are running (red lights ON)..
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 9. Verify RHR PP 1-1 Alignment. 9.1 Observes that RHR PP 1-1 is not running (green light ON and/or no amps).
9.2 Observes green light (only) ON for 8700A.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S4 rev 1.doc PAGE 5 OF 9 REV. 1
JPM TITLE: TRANSFER TO COLD LEG RECIRCULATION JPM NUMBER: NRCLJC-S4 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 10. Places RHR PP 1-1 in Cold Leg 10.1 Opens 8982A. **
Recirc Lineup.
10.2 Observes red light (only) ON for 8982A.
10.3 Verifies RHR HX 1-1 in service per App EE.
Cue: App EE has been completed. Both RHR HXs are in service per the appendix.
10.3 Starts RHR pump 1. **
10.4 Opens 8804A. **
Note the time 8804A indicated full OPEN (TCOA stop time):
10.5 Observes red light (only) ON for 8804A.
10.6 Observes RCS Pressure is < 1500 psig (VB-2, any PPC).
10.7 Observes both SI PPs are running (red lights ON)..
10.8 Observes RHR pump 1 motor current less than 57 amps, and stable.
Note: Throttling HCV-637 is not required.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S4 rev 1.doc PAGE 6 OF 9 REV. 1
JPM TITLE: TRANSFER TO COLD LEG RECIRCULATION JPM NUMBER: NRCLJC-S4 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 11. Check at least one RHR PP **********************************
running in Cold Leg Recirc Cue: The SFM has assigned other Lineup. operators to complete this procedure.
Stop Time: (for entire task)
Total Time: (for entire task; enter total time on the cover page)
TCOA Start Time:
TCOA Stop Time:
TCOA Total Time: (enter TCOA time on front page)
TCOA: SAT UNSAT (TCOA time must be < 10 minutes)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJC-S4 rev 1.doc PAGE 7 OF 9 REV. 1
JPM TITLE: TRANSFER TO COLD LEG RECIRCULATION JPM NUMBER: NRCLJC-S4 ATTACHMENT 1 - SIMULATOR SETUP Select JPM IC 751.
This SNAP allows entry into EOP E-1.3 at Step 2. RWST level is 33%. RHR PP 1-2 is still running. Step 1 (App EE has been completed by other operators, using time compression).
Inform the examiner that the simulator setup is complete.
NOTE: This JPM is time critical. Going to RUN too soon may affect the examinees ability to successfully complete this JPM. Do NOT go to run until the examiner or examinee indicates that they have begun.
Go to RUN when the examinee states they are ready to perform the task.
When an operator is dispatched to open the RHR pump 2 breaker, wait 3 minutes (or 5 minutes after start of task, whichever is longer), then clear GLB PMP RHR2 NRCLJC-S4 rev 1.doc PAGE 8 OF 9 REV. 1
JPM NUMBER: NRCLJC-S4 EXAMINEE CUE SHEET Initial Conditions: Unit 1 experienced a LBLOCA and RWST level has decreased to 33%.
Initiating Cue: Given:
- The USFM directs you to perform EOP E-1.3 to align RHR for cold leg recirculation and to provide suction to the SI pumps and CCPs. RHR PP 1-2 did not stop @ 33%, and could not be stopped from the Control Room.
- Step 1, App EE of EOP E-1.3, has been completed (using time compression); you are to start at step 2 of E-1.3.
- This is a time critical JPM.
- You may take a couple of minutes to preview the procedure before the task begins. Time begins when the simulator is placed in RUN.
NRCLJC-S4 rev 1.doc PAGE 9 OF 9 REV. 1
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJC-S5
Title:
VERIFY RE-18 IS OPERABLE Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
References:
OP G-1:II Discharge of Liquid Radwaste Rev. 36 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 2 Job Designation: RO/SRO Rev Comments/TIPs:
DCPP Task # / Rating: 274964 (SRO), N53650 (NO, 3.0) 3.8 (SRO)
Gen KA # / Rating: 073.A4.03 3.1 / 3.2 AUTHOR: GARY HUTCHISON DATE: 04/26/2011 REV. 1
JPM TITLE: VERIFY RE-18 IS OPERABLE JPM NUMBER: NRCLJC-S5 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Marked up of OP G-1:II section 12 and Discharge Permit for PWR 0-2.
Initial Conditions: Given:
- A Discharge Permit is issued for Process Waste Receiver 0-2.
- Recorder RR-102 is Out of Service.
- Instrument Cal expiration date is 10/3/2011.
Initiating Cue: The Shift Foreman directs you to verify RE-18 is operable by performing OP G-1:II step 12.13.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: RE-18 is source checked with the Operation Selector switch returned to OPERATE.
NRCLJC-S5 REV 1.DOC PAGE 2 OF 6 REV. 1
JPM TITLE: VERIFY RE-18 IS OPERABLE JPM NUMBER: NRCLJC-S5 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Channel Check RE-18 1.1 Verifies the instrument calibration has NOT expired.
1.2 Check Power On light is lit.
1.3 Check Operation Selector switch in "Operate."
1.4 Check Range Selector switch in "Wide."
1.5 Check Low Alarm (red) light is NOT lit.
1.6 Determines RR-102 is inoperable and must use PPC 1.7 Sets up PPC point R0001A for trend on the PPC.
Note: This substep is cued due to so many different ways to accomplish it on the PPC, and the ease of the subtask.
Cue: U2 CO will trend R0001A continuously with an F8 trend.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCLJC-S5 REV 1.DOC PAGE 3 OF 6 REV. 1
JPM TITLE: VERIFY RE-18 IS OPERABLE JPM NUMBER: NRCLJC-S5 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 2. Perform a source check on RE-18 2.1 Verbalizes that PK 11-23, "RADIATION MON SYS IN TEST." will alarm.
2.2 Places Operation Selector switch in the "CHECK SOURCE" position. **
Note: The source check reading will be 4 x 104 cpm.
2.3 Reads the source count rate. **
2.4 Return Operation Selector switch to "OPERATE." **
2.5 Record the source count rate on Part 3 of the discharge permit Cue: Another operator will continue in OP G-1:II, and with CAP AP-5, Att 11.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCLJC-S5 REV 1.DOC PAGE 4 OF 6 REV. 1
JPM TITLE: VERIFY RE-18 IS OPERABLE JPM NUMBER: NRCLJC-S5 ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRCLJC-S5 REV 1.DOC PAGE 5 OF 6 REV. 1
JPM NUMBER: NRCLJC-S5 EXAMINEE CUE SHEET Initial Conditions: Given:
- A Discharge Permit is issued for Process Waste Receiver 0-2.
- Recorder RR-102 is Out of Service.
- Instrument Cal expiration date is 10/3/2011.
Initiating Cue: The Shift Foreman directs you to verify RE-18 is operable by performing OP G-1:II step 12.13.
NRCLJC-S5 REV 1.DOC PAGE 6 OF 6 REV. 1
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJC-S6
Title:
RESPOND TO TRAVELLING SCREEN PROBLEM Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
References:
OP AP-7, Degraded Condenser, rev 38 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes Critical Steps: 1, 2 Job Designation: RO/SRO Rev Comments/TIPs:
DCPP Task # / Rating: 509200 3.7 Gen KA # / Rating: 051.AA2.02 3.9 / 4.1 AUTHOR: JOHN F. BUCKLEY DATE: 04/26/2011 REV. 1
JPM TITLE: RESPOND TO TRAVELLING SCREEN JPM NUMBER: NRCLJC-S6 PROBLEM INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: Provide a copy of OP AP-7 to the student during the reading of the initial conditions and cue. The examinee should be allowed a couple of minutes to review the procedure prior to accepting the watch (complex situation that would normally involve an extensive turnover).
Initial Conditions: Given:
- A high swell warning has been in effect for the last several hours.
All OP O-28 actions have been taken (manning, screens in high speed, etc). Ocean conditions are slowly degrading.
- All screen equipment is available and performing as designed, but D/Ps on the 1-1 CWP are remaining higher than 8.
- The crew is currently ramping U-1 down in power @ 10 mw/min.
- Several procedures are currently in use. OP AP-7, section C is in use, and step 1a was just completed.
- Due to the complex cue and plant conditions, you may have a minute or two to familiarize yourself with current plant conditions and procedures, before beginning the task.
Initiating Cue: The SFM directs you to continue in OP AP-7, section C, starting at step 1b.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: The reactor and CWP 1-1 are tripped, and subsequent actions performed, per OP AP-7, section C, step 1b.
NRCLJC-S6 REV 1.DOC PAGE 2 OF 6 REV. 1
JPM TITLE: RESPOND TO TRAVELLING SCREEN JPM NUMBER: NRCLJC-S6 PROBLEM INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
Note: Depending on how rapidly the screen Ps reach 70 (and how fast the examinee proceeds),
they may carry out the step 1b actions immediately, or loop back and perform the step after the next two steps in the procedure.
1.2 Observes the CWP 1-1 screen Ps are > 70.
1.3 Proceeds to the RNO section that deals with only one CWP in operation, with power > 25%.
1.4 Trips the reactor, and trips CWP 1-1. **
Note: The examinee may perform part or all of the E-0 immediate actions prior to tripping CWP 1-1.
Cue: (once reactor is tripped) Other operators will proceed with E-0 and E-0.1 actions. Continue with AP-7 actions.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCLJC-S6 REV 1.DOC PAGE 3 OF 6 REV. 1
JPM TITLE: RESPOND TO TRAVELLING SCREEN JPM NUMBER: NRCLJC-S6 PROBLEM INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 2. Aligns secondary systems. 2.1 Closes all MSIVs. **
Note: The examinee may inform the SFM of MSIV and 10%er operations prior to performing them.
2.2 Adjusts all 10% steam dumps controllers to maintain S/G pressure LESS THAN OR EQUAL TO 1005 PSIG (8.38 turns). **
2.3 Opens FCV-230 to bypass the polishers.
Cue: The Work Control Lead (WCL) will continue with AP-7 actions.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes a Critical Step.
NRCLJC-S6 REV 1.DOC PAGE 4 OF 6 REV. 1
JPM TITLE: RESPOND TO TRAVELLING SCREEN JPM NUMBER: NRCLJC-S6 PROBLEM ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-512 (50%, MOL).
On Triconex, take the programmed ramp OOS for the 1-2 CWP.
Set up a ramp to 200 mw at 10 mw/min, and start the ramp.
Enter drill file 6908 or manually insert the following:
Command Description mal cws3a act 99,150,0,c,xv4o185g Ramps Traveling Screen blockage over 2 minutes ser 0451 act,1,0,0,d,0 PK13-01 in alarm ovr xv4i186o act,1,0,0,d,5 Stops 1-2 CWP loa cws8 act,2,0,0,d,0 Turns on Screen wash pumps loa cws32 act,2,0,0,d,0 run 120 runs 2 minutes Ensure auto reclose and SCW lamicoids on the 1-1 CWP.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
NRCLJC-S6 REV 1.DOC PAGE 5 OF 6 REV. 1
JPM NUMBER: NRCLJC-S6 EXAMINEE CUE SHEET Initial Conditions: Given:
U-1 was operating at 50%, due to the 1-2 CWP being OOS for corrective maintenance.
- A high swell warning has been in effect for the last several hours.
All OP O-28 actions have been taken (manning, screens in high speed, etc). Ocean conditions are slowly degrading.
- All screen equipment is available and performing as designed, but D/Ps on the 1-1 CWP are remaining higher than 8.
- The crew is currently ramping U-1 down in power @ 10 mw/min.
- Several procedures are currently in use. OP AP-7, section C is in use, and step 1a was just completed.
- Due to the complex cue and plant conditions, you may have a minute or two to familiarize yourself with current plant conditions and procedures, before beginning the task.
Initiating Cue: The SFM directs you to continue in OP AP-7, section C, starting at step 1b.
NRCLJC-S6 REV 1.DOC PAGE 6 OF 6 REV. 1
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJP-P1
Title:
TRANSFER THE TSC TO VITAL POWER Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(ref: LJP-058, r27)
References:
EOP ECA-2.1, Uncontrolled Depressurization of All Steam Generators, Appendix J, Rev. 24A Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 1, 4, 5, 6 Job Designation: RO/SRO Rev Comments/TIPs:
DCPP Task # / Rating: 896600 2.8 Gen KA # / Rating: 062.A2.11 3.7 / 4.1 AUTHOR: JOHN F. BUCKLEY DATE: 04/27/2011 REV. 0
JPM TITLE: TRANSFER THE TSC TO VITAL POWER JPM NUMBER: NRCLJP-P1 INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.
Required Materials: Copy of ECA-2.1, Appendix J.
Initial Conditions: Given:
- Unit 1 experienced a steam break and uncontrolled depressurization of all steam generators.
- Offsite power was lost to both units.
- Diesel generator 13 is supplying 4kV bus F and is the only diesel capable of carrying the electrical load.
Initiating Cue: The Unit 1 Shift Foreman directs you to place the TSC on vital power, per ECA-2.1, Appendix J, commencing with Step 3.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: TSC power is aligned to Unit 1 vital power.
NRCLJP-P1 REV 0.DOC PAGE 2 OF 6 REV. 0
JPM TITLE: TRANSFER THE TSC TO VITAL POWER JPM NUMBER: NRCLJP-P1 INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
1.1 Places breaker 52-22J-40 (TSC XFER SW - normal power) in the OFF position.**
Cue: An audible "clunk" is heard, and the breaker is in the down position with the word OFF showing on the lower breaker handle.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Open breaker 52-2F-47. 2.1 Notes that breaker 52-2F-47 (TSC 480V POWER TO EPTSC - U2 vital supply to TSC) is in the OFF position.
Cue: The breaker is in the down position with the word OFF showing on the lower breaker handle.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJP-P1 REV 0.DOC PAGE 3 OF 6 REV. 0
JPM TITLE: TRANSFER THE TSC TO VITAL POWER JPM NUMBER: NRCLJP-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. Open breaker 52-1F-67. 3.1 Notes that breaker 52-1F-67 (TSC XFER SW - U1 vital supply to TSC) is in the OFF position.
Cue: The breaker is in the down position with the word OFF showing on the lower breaker handle.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 4. Switch EPTSN to VITAL power. Note: Switch is on west wall of 2F 480VAC switchgear room.
4.1 Places switch EPTSN in the VITAL SUPPLY (may be labeled "backup")
position.**
Cue: The sealed component change form needs will be addressed by another operator.
Cue: The switch is in the VITAL (backup) position.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJP-P1 REV 0.DOC PAGE 4 OF 6 REV. 0
JPM TITLE: TRANSFER THE TSC TO VITAL POWER JPM NUMBER: NRCLJP-P1 INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 5. Switch EPTSC to the UNIT 1 Note: Switch is also on west wall of 2F position. 480VAC switchgear room, next to EPTSN switch.
5.1 Breaks the seal.
Note: U2 is the normal position.
5.2 Places switch EPTSC in the UNIT 1 (52-1F-67) (may be labeled "backup") position.**
Cue: The switch is in the U-1 (52-1F-67)
(backup) position.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Cue: An audible "clunk" is heard, and the breaker is in the up position with the word ON showing on the upper breaker handle.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJP-P1 REV 0.DOC PAGE 5 OF 6 REV. 0
JPM NUMBER: NRCLJP-P1 EXAMINEE CUE SHEET Initial Conditions: Given:
- Unit 1 experienced a steam break and uncontrolled depressurization of all steam generators.
- Offsite power was lost to both units.
- Diesel generator 13 is supplying 4kV bus F and is the only diesel capable of carrying the electrical load.
Initiating Cue: The Unit 1 Shift Foreman directs you to place the TSC on vital power, per ECA-2.1, Appendix J, commencing with Step 3.
NRCLJP-P1 REV 0.DOC PAGE 6 OF 6 REV. 0
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJP-P2
Title:
CLOSE STEAM GENERATOR BLOWDOWN ISOLATION VALVES OUTSIDE CONTAINMENT Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: (Note: Any Unsat step requires a numbered comment; use back as needed.)
(ref: LJP-096, r17 retired)
Note: This is a U-1 JPM.
References:
OP AP-8A, C/R Inaccessibility - Establishing Hot Standby, Rev. 27A Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 25 minutes Critical Steps: 2, 3 Job Designation: RO/SRO Rev Comments/TIPs:
DCPP Task # / Rating: 386600 (ret) 3.5 Gen KA # / Rating: 013.A4.01 4.5 / 4.8 AUTHOR: GARY HUTCHISON DATE: 04/27/2011 REV.0
JPM TITLE: CLOSE STEAM GENERATOR BLOWDOWN JPM NUMBER: NRCLJP-P2 ISOLATION VALVES OUTSIDE CONTAINMENT INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.
Required Materials:
- Copy of OP AP-8A, Step 27.
- Adjustable crescent wrench Initial Conditions: Given:
- Units 1 and 2 are in MODE 3
- Control has been established from the Hot Shutdown Panels following a Control Room Evacuation.
Initiating Cue: You are directed by the Unit 1 Shift Foreman to verify closed the Unit 1 steam generator blowdown isolation valves outside containment (isolation and sample), in accordance with OP AP-8A, Step 27.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: The U-1 SGBD isolation valves (isolation and sample) have been closed per OP AP-8A, step 27.
Time Critical This JPM was evaluated against TCOA # 58, "De-energize DC power or Operator Action isolate air and vent SG Blowdown valves to isolate the path for each SG (TCOA): within 60 minutes".
This TCOA:
- is applicable to this JPM (not exactly the design bases case, but functionally the same from the point of view of this task), but since the JPM is only part of the whole TCOA task/event, the TCOA related steps will be critical, but the partial TCOA will not be time critical. (no partial TCOA task time validations exist).
NRCLJP-P2 REV 0.DOC PAGE 2 OF 7 REV.0
JPM TITLE: CLOSE STEAM GENERATOR BLOWDOWN JPM NUMBER: NRCLJP-P2 ISOLATION VALVES OUTSIDE CONTAINMENT INSTRUCTOR WORKSHEET Start Time:
Step Expected Operator Actions
- 1. Verify steam generator blowdown **********************************
isolation (O.C.) are closed. Cue: (for all of the valves) Valve (Penetration area GE, 100 elev.) position is AS-SEEN.
1.1 Checks the position of steam generator blowdown sample isolation valves FCV-244, 246, 248, and 250; determines valves are open.
Note: The position of both the SGBD isolation and sample isolation valves can be determined by looking at the metal plate attached to the valve stem (moves with the valve, and can clearly be seen pressing on either the open or closed limit switches); closed is towards the piping, open is away from the piping.
1.2 Checks position of steam generator blowdown isolation valves FCV-151, 154, 157 and 160; determines valves are open.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJP-P2 REV 0.DOC PAGE 3 OF 7 REV.0
JPM TITLE: CLOSE STEAM GENERATOR BLOWDOWN JPM NUMBER: NRCLJP-P2 ISOLATION VALVES OUTSIDE CONTAINMENT INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 2. Close the air supply valves to the 2.1 Locates air supply valves in steam generator blowdown PM-123. (Penetration area GE, 100 isolation valves. elev, just NW of SGBD isolation valves)
Cue: (for all air valves in PM-123)
Initial position is AS-SEEN.
2.2 Closes air supply valves:
- Closes AIR-I-1-1295.**
- Closes AIR-I-1-1301.**
Cue: (for each valve) The handle is 90 degrees (perpendicular) to tubing Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJP-P2 REV 0.DOC PAGE 4 OF 7 REV.0
JPM TITLE: CLOSE STEAM GENERATOR BLOWDOWN JPM NUMBER: NRCLJP-P2 ISOLATION VALVES OUTSIDE CONTAINMENT INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. Vent the air supply header to the 3.1 Removes vent caps from steam generator blowdown AIR-I-1-1300 and AIR-I-1-1306. **
isolation valves.
Cue: A crescent wrench was provided at HSDP when task was assigned.
Cue: (for each cap) The pipe cap rotated CCW and is now off the pipe.
3.2 Opens air supply header vent valves:
- Opens AIR-I-1-1300.**
- Opens AIR-I-1-1306.**
Cue: The sound of air noise from the pipe was initially heard, but is now quiet again.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJP-P2 REV 0.DOC PAGE 5 OF 7 REV.0
JPM TITLE: CLOSE STEAM GENERATOR BLOWDOWN JPM NUMBER: NRCLJP-P2 ISOLATION VALVES OUTSIDE CONTAINMENT INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 4. Check steam generator blowdown 4.1 Checks closed FCV-244, 246, 248, isolation valves closed. and 250; determines valves are closed.
Cue: (for each valve) The plate attached to the valve stem moved towards the valve, and is now pressing on the limit switch closest to the piping.
4.2 Checks closed FCV-151, 154, 157, and 160; determines valves have closed.
Cue: (for each valve) The plate attached to the valve stem moved towards the valve, and is now pressing on the limit switch closest to the piping.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJP-P2 REV 0.DOC PAGE 6 OF 7 REV.0
JPM NUMBER: NRCLJP-P2 EXAMINEE CUE SHEET Initial Conditions: Given:
- Units 1 and 2 are in MODE 3
- Control has been established from the Hot Shutdown Panels following a Control Room Evacuation.
Initiating Cue: You are directed by the Unit 1 Shift Foreman to verify closed the Unit 1 steam generator blowdown isolation valves outside containment (isolation and sample), in accordance with OP AP-8A, Step 27.
NRCLJP-P2 REV 0.DOC PAGE 7 OF 7 REV.0
NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCLJP-P3
Title:
LOCAL VERIFICATION OF SI AND CONTAINMENT ISOLATION PHASE A Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate Results: Sat Unsat Total Time: minutes Comments: This JPM can be performed on Unit 1 or Unit 2.
(Note: Any Unsat step requires a numbered comment; use back as needed.)
References:
System Lesson Guide B-6A, Reactor Protection System, page 2.2-7 System Lesson Guide G-1, Liquid Radwaste System, page 2.3-5, 6 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 20 minutes Critical Steps: 1, 2, 3, 4 Job Designation: RO/SRO Rev Comments/TIPs:
DCPP Task # / Rating: 331600, 197200 3.3 / 4.3 Gen KA # / Rating: 011.EA1.05 4.3 / 3.9 AUTHOR: GARY HUTCHISON DATE: 04/27/2011 REV.0
JPM TITLE: LOCAL VERIFICATION OF SI AND JPM NUMBER: NRCLJP-P3 CONTAINMENT ISOLATION PHASE A INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.
Required Materials: None Note: Clearly state the Unit to be performed on during the initial conditions and cue, below.
Initial Conditions: Given:
- U-1 (U-2) reactor has tripped and a Safety Injection/Phase A isolation have occurred.
- The following lights on Monitor Light Box B and C do not indicate the complete actuation of Phase A and SI:
- Charging pump Suction from RWST - 8805B (Should be OPEN)
- Charging pump Suction from VCT- LCV-112C (Should be CLOSED)
- RCDT Pump Discharge Outside Containment - FCV-254 (Should be CLOSED)
- Containment sumps discharge Outside Containment - FCV-501 (Should be CLOSED)
Initiating Cue: The SFM directs you to enter the plant on U-1 (U-2) and locally verify the correct position of 8805B and LCV-112C and verify the correct position of FCV-254 and FCV-501 at the Liquid Radwaste Isolation Panel. The breakers for the valves 8805B and LCV-112C have been opened.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: 8805B will be CLOSED and will need to be repositioned OPEN (Alternate Path). LCV-112C will be OPEN and will need to be repositioned Closed (Alternate Path). FCV-254 and FCV-501 will be OPEN and will need to be repositioned CLOSED (Alternate Path).
NRCLJP-P3 REV 0.DOC PAGE 2 OF 5 REV.0
JPM TITLE: LOCAL VERIFICATION OF SI AND JPM NUMBER: NRCLJP-P3 CONTAINMENT ISOLATION PHASE A INSTRUCTOR WORKSHEET Start Time: Note: Steps may be performed in ANY order.
Step Expected Operator Actions
- 1. Locally verify proper actuation of Note: Location is U-1 (U-2) 85 Aux 8805B. Bldg Cont Pen Area Cue: Valve position is AS SEEN.
1.1 Opens Charging pump Suction from RWST - 8805B. **
Cue: Valve position indicator is UP.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 2. Locally verify proper actuation of Note: Location is 85 Aux Bldg outside FCV-254. Aux Control board.
Cue: Valve position is AS SEEN.
2.1 Takes control switch for RCDT Pump Discharge - FCV-254 to CLOSE. **
Cue: Red light OFF, green light ON.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJP-P3 REV 0.DOC PAGE 3 OF 5 REV. 0
JPM TITLE: LOCAL VERIFICATION OF SI AND JPM NUMBER: NRCLJP-P3 CONTAINMENT ISOLATION PHASE A INSTRUCTOR WORKSHEET Step Expected Operator Actions
- 3. Locally verify proper actuation of Note: Location is 85 Aux Bldg outside FCV-501. Aux Control board.
Cue: Valve position is AS SEEN.
3.1 Takes control switch for Containment sumps discharge -
FCV-501 to CLOSE. **
Cue: Red light OFF, green light ON.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
- 4. Locally verify proper actuation of Note: Location is U-1 (U-2) 100 Aux LCV-112C. Bldg Blender Room.
Cue: Valve position is AS SEEN.
4.1 Closes Charging pump Suction from VCT - LCV-112C. **
Cue: Valve position indicator is DOWN.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes an entry required on the JPM cover sheet.
- Denotes Critical Step and Sub Steps.
NRCLJP-P3 REV 0.DOC PAGE 4 OF 5 REV. 0
JPM NUMBER: NRCLJP-P3 EXAMINEE CUE SHEET Initial Conditions: Given:
- U-1 (U-2) reactor has tripped and a Safety Injection/Phase A isolation have occurred.
- The following lights on Monitor Light Box B and C do not indicate the complete actuation of Phase A and SI:
- Charging pump Suction from RWST - 8805B (Should be OPEN)
- Charging pump Suction from VCT- LCV-112C (Should be CLOSED)
- RCDT Pump Discharge Outside Containment - FCV-254 (Should be CLOSED)
- Containment sumps discharge Outside Containment - FCV-501 (Should be CLOSED)
Initiating Cue: The SFM directs you to enter the plant on U-1 (U-2) and locally verify the correct position of 8805B and LCV-112C and verify the correct position of FCV-254 and FCV-501 at the Liquid Radwaste Isolation Panel. The breakers for the valves 8805B and LCV-112C have been opened.
NRCLJP-P3 REV 0.DOC PAGE 5 OF 5 REV. 0
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: 1 Op-Test No.: L091-NRC Examiners: Operators:
Initial Conditions: 100% Reactor power, MOL, Boron at 774 ppm Turnover: TDAFW pp cleared, H 2 delivery in progress, maintain 100% power Event Malf Event Event No No. Type* Description 1 xmt pzr15 I (ALL) PT-455 Pzr Pressure channel fails high (interlock fails) (TS) (CT) 2 pmp cnd10 C (SRO) # 2 Htr Drain Pump trip (automatic programmed ramp @ 40 mw/min)
R (ATC) 3 xmt cvc31 C, N (ALL) Charging pump 13 high stator temperature; swaps charging pumps (ECG) 4 loa cnd1 M (ALL) Loss of condenser vacuum 5 loa afw6/7 C, M (ALL) AFW pumps cavitate due to suction line break and eventually trip (or are stopped)
LOSHS - must establish heat sink from condensate system (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 1. Total malfunctions (5-8) 5
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 2
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2 L091 NRC Sim Exam 01 Rev 1.doc Page 1 of 13 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 1 Event No.: 1 Page 1 of 6 Event
Description:
PT-455 Pzr Pressure channel fails high (CT) (TS)
Time Position Applicants Actions or Behavior ATC Identifies pressurizer pressure failing BOP Identifies PORV PCV-455C open from failure, and manually closes (prior to ESF/SI actuation) (critical task) **
SRO Enter OP AP-5 Malfunction of Eagle Protection or Control Channel ATC May place Master Pzr Pressure Controller HC-455K in manual BOP Determines if Eagle-21 failure - PK06-01 and PK06 OFF ATC Determines PT-455 not selected as control or backup ATC Determines PT-455 not selected as a Recorder input BOP Checks steam dumps not actuated SRO Notifies I&C, directs OOS tags placed (PI-455)
SRO Recognizes TS 3.3.2.L P-11 ESF (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
SRO Recognizes TS 3.4.11.B1 & B2 (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
SRO Recognizes TS 3.3.1.E & M OTT, Pressure High/Low Trips SRO Recognizes TS 3.3.2.D Low Press S/I ESF SRO May implement TS 3.4.1.A (2 hr) if pressure drops low enough (2175 psig)
BOP Closes Block Valve 8000B for Inoperable PORV (1 hr TS)
SRO/BOP Directs WCL to remove power to 8000B (1 hr TS)
ATC Returns HC-455K to Auto (if placed in manual)
- Critical Task L091 NRC Sim Exam 01 Rev 1.doc Page 2 of 13 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 1 Event No.: 2 Page 2 of 6 Event
Description:
- 2 Htr Drain Pump trip Time Position Applicants Actions or Behavior BOP Identifies #2 Htr Drain PP tripped on Overcurrent (blue light)
SRO May refer to ARP PK10-14 for OC trip; directs to OP AP-15, section C (may go directly to OP AP-25)
ATC/BOP Notes programmed ramp in progress, from turbine indications and/or PK12-12 (DEH)
SRO Implement OP AP-15, section C, for #2 Htr Drain Pp trip BOP Verifies adequate MFP suction pressure ATC/BOP Verifies programmed ramp is in progress for Htr Drain Pp trip SRO Transitions to OP AP-25, Rapid Load Reduction, to stabilize the plant (if not initially selected)
ATC Verifies programmed ramp operating properly ATC Verifies control rods inserting properly in AUTO ATC Energizes all Pzr backup heaters ATC Takes manual control of Pzr level to prevent flashing of letdown BOP Verifies DFWCS controlling S/G levels ATC Uses reactivity handbook to determine boric acid required, and borates RCS SRO Provides oversight during the ramp BOP Verifies MFP suction pressure, and stby CB Pp set running ATC Verifies proper operation of steam dumps ATC Checks pressurizer pressure and level at or returning to program ALL Notifies maintenance of pump failure L091 NRC Sim Exam 01 Rev 1.doc Page 3 of 13 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 1 Event No.: 3 Page 3 of 6 Event
Description:
Charging pump 13 high stator temperature; swaps charging pumps (ECG)
Time Position Applicants Actions or Behavior ATC Recognizes high temperature/alarm on CCP 1-3 SRO Refers to AR PK04-16 ATC/BOP Confirms high temperature using PPC BOP Dispatches operators to check pump conditions (pump, motor, vents, breaker)
Cue: If requested to investigate 1-3 CCP: The pump motor casing is hot to the touch, and there is a slight acrid smell in the room. The breaker conditions are normal.
Note: Crew may stop CCP 1-3 prior to procedure guidance (to protect equipment, and followup with procedure).
SRO Determines that the high temperature conditions are real, and directs swapping CCPs (may have pump stopped, which would create need to restore letdown)
SRO Implements OP B-1A:V to swap CCPs (sec 6.1)
SRO Directs Maintenance to investigate ATC Places FCV-128 in MANUAL BOP Starts a standby CCP, and secures 1-3 CCP once stable ATC Returns level to program, and maintains RCP seal flows normal ATC Returns FCV-128/level control to AUTO once at program (if time permits)
SRO Refers to ECG 8.1.A (1 hr)
L091 NRC Sim Exam 01 Rev 1.doc Page 4 of 13 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 1 Event No.: 4 Page 4 of 6 Event
Description:
Loss of condenser vacuum Time Position Applicants Actions or Behavior BOP Observes degrading condenser vacuum (rising pressure) (PK10-11)
SRO Implements OP AP-7, section A (as time permits)
BOP Makes plant announcement concerning loss of vacuum ATC May trip turbine and/or reactor manually prior to automatic trips BOP/ATC May ramp down due to degrading vacuum prior to trip ALL Observes turbine and reactor trip SRO Enters EOP E-0 for reactor trip ALL Performs E-0 immediate actions:
- Verifies reactor trip
- Verifies turbine trip
- Checks vital 4kv busses
- Checks if SI actuated SRO/BOP Throttles AFW to minimize cooldown; notes no AFW flow (may note here or in E-0.1, as S/G levels are still on scale, and pumps may not have started yet)
ALL Transitions from E-0 to E-0.1; implements CSFSTs ALL Performs E-0.1 actions:
- Stabilizes Tave (may set 10% dumps to 1005 psig)
- Verifies feedwater isolation
- Verifies adequate AFW, or adequate S/G levels (may note AFW pp cavitation at this point, if pumps tried to start, or are started manually)
- Checks control rods inserted
- Checks pressurizer level control SRO Once AFW pumps start and cavitate (levels still > LOSHS transition point), may send operators to locally check MDAFPs (cue on next page)
SRO Once heat sink requirements no longer met (RED PATH on HEAT SINK), crew transitions to EOP FR-H.1 L091 NRC Sim Exam 01 Rev 1.doc Page 5 of 13 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 1 Event No.: 5 Page 5 of 6 Event
Description:
AFW pumps cavitate due to suction line break, causing a loss of secondary heat sink (LOSHS)
Time Position Applicants Actions or Behavior SRO/BOP Notes AFW pumps cavitating; may stop pumps (possibly uses interlocks, per OP1.DC10, 5.15.3.f.10) prior to pumps tripping ALL Observes S/G levels < 15% NR during EOP E-0.1, or while evaluating CSFSTs SRO Enters EOP FR-H.1 (LOSHS) due to loss of AFW and low S/G levels SRO May perform procedure transition brief done for FR-H.1 entry ATC Need for secondary heat sink verified ATC ECCS CCP verified available BOP Verifies adequate CST level SRO Operator(s) dispatched to locally check lineups/investigate AFW Pps Cue: Report from Nuclear operator: AFW common suction for U-1 has pipe break and significant water on floor.
Cue: Report from maintenance/SM (if asked to bring back TDAFP): The RTS for the TDAFP is being expedited. RTS is estimated to be 90 minutes.
ATC Stops all RCPs BOP 10% steam dumps set to control pressure @ 1005 psig (if not earlier during EOP E-0.1)
ALL Performs initial feed alignment steps (step 7):
- Checks condensate booster pp set running
- Checks MFIVs open
- Notes condenser not available, and proceeds to step 9 L091 NRC Sim Exam 01 Rev 1.doc Page 6 of 13 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 1 Event No.: 5 Page 6 of 6 Event
Description:
Establish feed flow to S/Gs from the condensate system following a LOSHS (cont)
(CT)
Time Position Applicants Actions or Behavior ALL Block Safety Injection signals
- Maintains RCS pressure below P-11 (1500-1865 psig)
SRO/BOP Verifies MFIVs open BOP Resets FWI (as needed)
ATC Throttles open MFRVs or MFRV bypasses BOP Bypasses feedwater heaters and condensate demineralizers (FCV-55 and FCV-230)
BOP Closes all MSIVs BOP Depressurizes two S/Gs (any two) using the 10% steam dumps, at maximum rate, down to condensate injection pressure (< 490 psig), where pressure is stabilized ATC Maximizes normal charging during S/G depressurization ALL Verifies feedwater flow to at least one S/G, with WR S/G level rising prior to bleed and feed criteria being met (WOG CT FR-H.1-A) (critical task) **
Terminate the scenario once feedwater flow from the condensate system is established, and S/G level is rising in at least one S/G.
- Critical Task L091 NRC Sim Exam 01 Rev 1.doc Page 7 of 13 Rev 1
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES
- 1. Pressurizer pressure transmitter PT-455 fails high, causing its PORV (PCV-455C) to open (opens, with interlock channel failing as well). The crew takes actions to close the PORV and block valve (prior to ESF/SI actuation) (CT), and address the Tech Specs (TS) associated with the failure.
- 2. #2 Heater Drain Pp trips on overcurrent, causing a runback to 770 MWe @ 40 mw/min. The crew will respond to the ramp, borate as needed, and stabilize the plant.
- 3. 1-3 CCP stator temperature will rise above the alarm setpoint. After investigation, the crew will swap CCPs in order to secure the 1-3 CCP. (ECG)
- 4. A rapid loss of vacuum occurs. The crew may trip the turbine manually and/or ramp the unit prior to the automatic turbine/reactor trip. E-0 and E-0.1 actions are performed as S/G levels drop below 15%.
- 5. Both MDAFPs are noted to cavitate following trip; the crew may stop the pumps (and possibly defeat with interlock devices) prior to the pumps tripping a minute or so later. With low S/G levels, this will cause a RED PATH on the Heat Sink CSFST, and transition to EOP FR-H.1. AFW status will be investigated (suction pipe break in MDAFP room), but will not be returned to service.
The condensate system is aligned for feeding, and S/Gs are depressurized in order to feed from the condensate system (prior to bleed/feed criteria being met, that is, 3 WR S/G levels
< 18%) (CT).
The scenario is terminated when at least one S/G is being fed from the condensate system with rising level in at least one S/G.
L091 NRC Sim Exam 01 Rev 1.doc Page 8 of 13 Rev 1
ATTACHMENT 1 - SIMULATOR SETUP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator INIT 510 100% power, Mol, CB = 774 per Checklist
- Integrators: BA - 00, and PW - 15
- Tags: TDAFP Setup Drill 81 Reset normal engineering values Setup Drill 40 Clears TDAFP (PMT, so FCV-37/38 not included)
Setup Boards - CC1 Place Htr Grp 1-4 in ON CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary. TDAFP Primary integrator = 15 gal, Boron = 00 gal.
Record PPC MAX (BOL = 100.1, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP C B near 774 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o Trend TAVG, ALM/MODE-1, Trend CHARGING, Sim Large on big screen o RONCONFIG is updated.
o PENs running.
o R2BCONFIG blowdown flows at 90 gpm.
o Operational mode correct for current conditions. 1 o Delta-I target slope matches Delta-I curve (DELTAICONFIG)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
Run the clear recorders program to clear digital charts All printer are on, with adequate paper/ink/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
1 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, go to APMC. Follow menu to manually override to correct mode.
L091 NRC Sim Exam 01 Rev 1.doc Page 9 of 13 Rev 1
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X Once crew has DRILL 6901 in AUTO Scenario malfunctions are inputted once the crew taken the watch takes the watch 0 min loa ppl322 act,1,0,0,d,0 Defeats PC474B interlock so that PCV-455C does not close at the interlock setpoint 2 min xmt pzr15 3,2642,5,120,d,0 PT-455 Pzr Pressure transmitter fails high X When requested DRILL 12 in AUTO Removes power from 8000B (PCV-455C block valve)
On Htr 2 Drain Pp xmt mfw110 6,215,0,0,c, Bias PI-156 to > 200 psig following Htr 2 Drain Pp trip trip xv3o220b,0 Following PT-455 pmp cnd10 6,2.26,5,1800,c, Htr 2 Drain Pp 1-1 trips on OC failure, per lead xv2o205r,0 examiner Following Htr xmt cvc31 3,320,150,1800,c, Rising stator temperature on the 1-3 CCP, will cause Drain Pp failure, xv3o220b, 0 the crew to swap pumps per lead examiner X Cue: If requested to investigate 1-3 CCP: The pump motor casing is hot to the touch, and there is a slight acrid smell in the room. The breaker conditions are normal.
Once CCP 1-3 loa cnd1 act,0.0025,120,1800, Rapid loss of vacuum to the main condenser (opens event is c,xv2o266g vac bkr) complete, per lead examiner On trip tc jpplp4, loa cnd1 act,0.5,1,0 Opens vac breaker on trip to ensure MFPs are NOT available following trip 1 min after trip loa afw6 act,0,0,60,c, Closes MDAFP 1-2 suction from CST fnispr.lt.5,0 1 min after trip loa afw7 act,0,0,60,c, Closes MDAFP 1-3 suction from CST fnispr.lt.5,0 2 min after trip pmp afw1 4,0,0,120,c, MDAFPs 1-2 and 1-3 trip due to loss of suction fnispr.lt.5,0 pmp afw2 4,0,0,150,c, fnispr.lt.5,0 X Cue: Report from Nuclear operator: AFW common suction for U-1 has pipe break and significant water on floor.
X Cue: Report from maintenance/SM (if asked to bring back TDAFP): The RTS for the TDAFP is being expedited. RTS is estimated to be 90 minutes.
X After Rx Trip PA DRILL 32 in AUTO NO Action on reactor trip L091 NRC Sim Exam 01 Rev 1.doc Page 10 of 13 Rev 1
DRILL FILE TEXT
- NRC L091 Exam Scenario 1 (6901)
- jfb1 04/25/11
- init 510
- drill 40 to clear TDAFW pp
- defeat pc-474b interlock loa ppl322 act,1,0,0,d,0 #krps474b
- pt-455 fails high in 2 min xmt pzr15 3,2642,5,120,d,0 #pxmtpzr(1)
- bias pi-156 above 200 psig when drn pp trips xmt mfw110 6,215,0,0,c,xv3o220b,0 #pcfw156
- PMP CND10 HEATER 2 DRAIN TANK PP 11 pmp cnd10 6,2.26,5,1800,c,xv2o205r,0 #ohdp11
- XMT CVC31 CHG PP 1-3 STATOR TEMP, T0668A #txmtchgs(3) xmt cvc31 3,320,150,1800,c,xv3o220b,0 #txmtchgs(3)
- loa CND1 CND-506 VACUUM BREAKER FOR MAIN CONDENSER #rcdv506 loa cnd1 act,0.0025,120,1800,c,xv2o266g,0 #rcdv506
- open vac bkr on trip to remove mfps due to low vac tc jpplp4, loa cnd1 act, 0.5,1,0
- Both MDAFPs trip approx 1 minute after losing suction pmp afw1 4,0,0,120,c,fnispr.lt.5,0 #oafp12 pmp afw2 4,0,0,150,c,fnispr.lt.5,0 #oafp13 L091 NRC Sim Exam 01 Rev 1.doc Page 11 of 13 Rev 1
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 111 Days Operating Mode: 1 Gross Generation: 1191 MWe Power Level: 100 % Net Generation: 1148 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): 307 SCF / 326 SCFD 5 day ave NEW EMERGENT WORK:
- None SHUTDOWN TECH SPECS / ECGS:
- TS 3.7.5.B TDAFP, OOS for bearing replacement, estimated RTS is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; pump has been OOS for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- None TURNOVER ITEMS:
- H 2 delivery is in progress PRIORITY ITEMS FOR NEXT SHIFT:
- Maintain 100% power.
OPERABILITY ITEMS:
- None ANNUNCIATORS IN ALARM:
- PK09-18 is in, due to the TDAFP being cleared.
L091 NRC Sim Exam 01 Rev 1.doc Page 12 of 13 Rev 1
Shift Foreman Turnover TURNOVER ITEMS:
- U maintain 100% - no one in containment
- U-2 is at 100%
REACTIVITY MANAGEMENT:
- Time in core life: MOL.
- Power History: Steady State, previously at 100% for 47 days. Currently power is at 100%.
- Boron concentration is 774 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 231 steps on CBD.
- Diluting the RCS approximately 15 gallons every 1 1/2 hrs.
- The last dilution was completed 15 min ago.
- Rod motion: none planned, as needed to maintain I on target CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
- None OTHER ABNORMAL PLANT STATUS
- See Plant Abnormal Status Board L091 NRC Sim Exam 01 Rev 1.doc Page 13 of 13 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: 2 Op-Test No.: L091-NRC Examiners: Operators:
Initial Conditions: 100% power, MOL, 774 ppm boron, Cond/Bstr pump set 13 cleared, H 2 delivery in progress Turnover: Ramp to 25% power based on ODM decision due to high swell warning (copy of OP O-28 provided to crew with turnover)
Event Malf Event Event No No. Type* Description 1 R (ATC) Ramp at 15 MW/min 2 xmt rcs15 I (SRO, Loop 1 Tcold channel fails high (TS)
ATC) 3 mal rcs3c C (ALL) 40 gpm RCS leak on Loop 3 (TS) 4 cnh pzr3 I (ATC, Pzr Spray valve controller loop 1 fails high in auto SRO) 5 mal rcs3c M (ALL) 3000 gpm LOCA on Loop 3 6 mal ppl3a/b I (ATC) Safety Injection fails to Actuate in Auto; manually actuate prior to exit from EOP E-0 (CT) 7 ramp asisrwst M (ALL) Crack Drains RWST to approximately 36% over 10 minutes due to explosion by tank area - requires makeup to RWST (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 1. Total malfunctions (5-8) 6
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 2
- 5. EOPs entered/requiring substantive actions (1-2) 2
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 3 L091 NRC Sim Exam 02 Rev 1.doc Page 1 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 2 Event No.: 1 Page 1 of 7 Event
Description:
Ramp down to 25% power @ 15 mw/min due to high swell warning Time Position Applicants Actions or Behavior SRO Enters OP AP-25, Rapid Load Reduction BOP Ramp is started:
- Sets ramp rate to 15 mw/min
- Pushes GO ATC Verifies that control rods are inserting properly in AUTO ATC Verifies ON all pressurizer backup heaters ATC Maintains charging flow adequate to prevent letdown flashing BOP Verifies DFWCS in AUTO and controlling S/G levels ATC RCS is borated per reactivity handbook for approx 70% load reduction SRO SFM provides reactivity oversight BOP MFP suction is verified adequate ATC Verifies proper operation of steam dumps ATC Checks pressurizer pressure and level trending to program L091 NRC Sim Exam 02 Rev 1.doc Page 2 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 2 Event No.: 2 Page 2 of 7 Event
Description:
Loop 1 T C channel fails high (TS)
Time Position Applicants Actions or Behavior BOP/ATC Diagnoses that loop 1 Tave has failed high, using VB-2 indications (PPC may also be used)
BOP/ATC May place ramp on hold while stabilizing the plant (and re-initiates ramp later)
ATC May stop boration, if in progress.
ATC (if rods in auto) Observes inward rod motion (auct Tave failed high); places rod control in MANUAL ATC Notes increase in charging flow and possible high charging flow demand alarm (due to auct Tave failed high); may place charging flow in MANUAL prior to entering OP AP-5 SRO Determines that a protection/control channel has failed, and enters OP AP-5 (may stop ramp and/or boration).
ATC Reports that rod control and pressurizer level control have been affected by the failure; takes manual control of rods (if not already done), and places charging in manual BOP Determines that the failure is Eagle-21 related (PK06 ON)
ATC Determines which Protection Set is affected (from Ronan or Viewer/board indications); set I SRO Directs WCL/watchstander to open all Prot Set I doors (racks 1-4) and monitor per Att 4.2 SRO Determines which instruments are in the affected racks (2 & 4) using Att 4.1 SRO Directs WCL/watchstander to monitor unaffected instrument racks each 4 hrs SRO Determines affected bistables and fills out Bistable Trip Authorization Sheet (Att 4.1) (may do now or in later step)
- TC-411C Loop 1 OTT Trip
- TC-411G Loop 1 OPT Trip
- (S/G TTD bistables are an option, but not required)
ATC Deselects Loop 1 Tave and Delta-T as Tave inputs (goes to loop out on switches) (may move up due to/if ramp still in progress)
ATC Verifies loop 1 is not selected on the VB-1 delta-T recorder BOP Checks steam dumps not actuated SRO Notifies I&C to investigate ALL Directs OOS stickers for affected instruments (Att 4.1)
SRO Determines affected Tech Specs and ECGs
- 3.3.1.E OTT and OPT trips
- 3.3.1.X and 3.3.2.M S/G TTD circuitry (reset to zero, or trip bistables)
ATC May return rod control and pressurizer level control to AUTO (if time permits)
L091 NRC Sim Exam 02 Rev 1.doc Page 3 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 2 Event No.: 3 Page 3 of 7 Event
Description:
40 gpm RCS leak on loop 3 (TS)
Time Position Applicants Actions or Behavior ALL Notes indications of RCS leakage (increase in net charging, higher charging flow, lowering pressurizer level, containment sump alarms, containment environment, etc)
SRO Enters OP AP-1 for RCS leakage (may enter ARP PK11-21 first); may stop ramp during diagnostics and stabilization (and continues ramp at SFM discretion)
ATC Observes increase in charging flow and/or drop in pressurizer level ATC Maintains pressurizer level (may raise charging in auto or manual); adjusts seal flows BOP May start an additional charging pump as pressurizer level drops BOP May isolate letdown as pressurizer level drops ATC Verifies RCS pressure is normal and stable ATC Verifies that CVCS makeup can keep up with leak (makeup in auto, at programmed band)
ALL Identify the source of the leak:
- Rules out seal table leak
- Uses S/G radiation monitors to rule out S/G tube leakage
- Observes that pressurizer safeties and PORVs show no signs of leakage
- Notes no indications (indicator or alarm) of reactor vessel flange leakage
- Observes that RCP seal leakage is normal
- Notes that there is no indication or RCS valve packing leakage (alarm)
- Observes several containment environmental and radiation indications of RCS leakage into containment SRO Considers making a containment entry to locate leak SRO May isolate charging and letdown to eliminate as possible source of leakage ALL If isolated, charging and/or letdown may be placed back in service (as time permits)
ATC Estimates leak size (STP R-10C, and/or available indications)
SRO Evaluates leak size vs Tech Specs (TS 3.4.13)
L091 NRC Sim Exam 02 Rev 1.doc Page 4 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 2 Event No.: 4 Page 4 of 7 Event
Description:
Loop 1 pressurizer spray controller fails high in AUTO Time Position Applicants Actions or Behavior ALL Observes RCS pressure dropping, and/or notes low pressure alarm ATC Observes green light out on loop 1 spray valve (open), with lowering RCS pressure, and determines that the controller (PCV-455A) has failed to operate properly in auto ATC Takes PCV-455A to manual and closed; observes that valve closes and RCS pressure stops dropping (this action may occur prior to or during OP AP-13 use)
SRO Enters OP AP-13 for malfunction of reactor pressure control system BOP Stop any load changes in progress BOP Checks pressurizer PORVs and safeties closed ATC Checks pressurizer spray valves closed - closed PCV-455A in manual if not already done BOP Verifies pressurizer aux spray not in service ATC Verifies proper pressurizer heater operation BOP Observes that no pressurizer pressure channels have failed ATC Returns RCS pressure to normal SRO Evaluates TS 3.4.1.A (only if pressure dropped to below 2175 psig)
L091 NRC Sim Exam 02 Rev 1.doc Page 5 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 2 Event No.: 5&6 Page 5 of 7 Event
Description:
3000 gpm LOCA on loop 3, and Safety Injection failure (auto fails) (CT)
Time Position Applicants Actions or Behavior ATC Observes rapid drop is pressurizer pressure and level ATC May initiate a manual SI prior to reaching the SI setpoint ATC Initiates manual SI (prior to exit from EOP E-0; WOG CT E-0-D) (critical task) **
SRO Crew enters EOP E-0 ALL Immediate actions are performed:
- Verify reactor trip
- Verify turbine trip
- Check vital 4KV bus status
- Announce trip/SI on PA system, and checks main generator - tripped
- Verify Phase A and containment vent isolation complete
- Checks containment spray, Phase B, and main steam isolation - not required
- Checks excess letdown - not in service; turns on aux bldg vent charcoal filter preheater
- Checks secondary systems (MFPs tripped, only one CB Pp set running, condenser status, and opens MFP recircs
- Verifies proper operation of Aux Bldg and Control Rm vent systems; verifies containment iodine fans secured
- Verifies DGs running normally; verifies vital batteries supplied by chargers
- Verifies MSRs reset, and throttles RCP seal injection flows to normal ATC Checks RCS temperature - stable ATC Checks Pzr safeties and PORVs - closed ATC Checks RCP trip criteria - stops all RCPs < 5 minutes after RCS pressure drops below 1300 psig in the RCS (WOG CT E-1-C) (critical task) (note: this may occur in EOP E-0 or E-1) **
ATC/BOP Checks for faulted and ruptured S/Gs ALL Checks for RCS intact - notes containment parameters are elevated - places 2nd CCW HX in service, and transitions to EOP E-1 ALL Implements CSFSTs
- Critical Task L091 NRC Sim Exam 02 Rev 1.doc Page 6 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 2 Event No.: 7 Page 6 of 7 Event
Description:
RWST leak causes rapid drop to 36% level (CT)
Time Position Applicants Actions or Behavior SRO Performs procedure transition brief for EOP E-1 SRO Checks RCP Trip criteria (may have been performed earlier) - Verifies all RCPs are stopped, within 5 min of dropping below 1300 psig in the RCS (critical task if performed at this point) **
ATC/BOP Observes from indication, explosion sound, and/or alarm that RWST level is dropping at rate in excess of RCS leak; may have security investigate.
Cue: (from RP) An RP Tech has reported that the U-1 RWST is leaking rapidly from damage; the leak appears to be about 1/3 or so the way up the tank, and most of the 115 tank area is wet.
ALL Check for faulted and ruptured S/Gs BOP Check and maintain S/G levels 20-65%
ATC Check Pzr PORVs/blocks - closed and available, unless needed open ATC Check containment spray status (not on)
ALL Check ECCS termination criteria (not met)
ATC Check if RHR pumps should be stopped BOP Check if DGs should be stopped (stopped and returned to auto)
ALL RWST low alarm noted @ 33%; RHR pumps automatically stop ATC Foldout Page (FOP) noted on RWST low level; crew transitions to EOP E-1.3 BOP Appendix EE is performed:
- All (6) series contactor switches on VB-2 are cut in
- SI, Phase A, and Phase B signals are reset
- Dispatches operators to rack in breakers for ECCS normal suction valves ATC Verifies RHR Pp 1-2 stopped , and then closes 8700B ATC Verifies RHR Pp 1-1 stopped , and then closes 8700A ATC Closes 8716A/B (RHR discharge crossties)
ATC Isolates ECCS recirc paths (closes 8974 A/B, and 8105 / 8106)
ATC Checks containment recirc sump level (not adequate for cold leg recirc); transitions to EOP ECA-1.1, Loss of Emergency Coolant Recirc Capability
- Critical Task L091 NRC Sim Exam 02 Rev 1.doc Page 7 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 2 Event No.: 7 Page 7 of 7 Event
Description:
RWST leak causes rapid drop to 36% level - makeup to RWST (cont) (CT)
Time Position Applicants Actions or Behavior ALL Determines loss of ECR not caused by sump blockage ALL Restores recirc equipment (not possible due to low sump level)
ATC Resets SI, and verifies CFCUs running in slow speed ATC Checks RWST level (not empty)
ATC Determines containment spray requirements (not on)
ATC Adds makeup to the RWST (WOG CT ECA-1.1-B) (critical task): **
- Implements App M of procedure
- Reads notes prior to steps, and selects section A for makeup
- Directs field operators to perform the section A steps (all in field); may direct entire procedure section to field, as desired (since all performance is in the field, directing the performance satisfies the CT).
- Note: flow can be confirmed by RWST level rise and/or sim console flow monitoring BOP Checks and maintains S/G levels 20-65%
Terminate scenario once the control room directs App M to be performed in the field.
- Critical Task L091 NRC Sim Exam 02 Rev 1.doc Page 8 of 14 Rev 1
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES
- 1. Plant is ramped at 15 mw/min to approx 25% power. OP AP-25 is used for guidance.
- 2. Loop 1 Tc fails high, affecting both rod control (rods move in) and Pzr level control (charging increases due to ref level signal going up). OP AP-5 is used to defeat the affected temperature channel and address Tech Specs. (TS)
- 3. A 40 gpm RCS leak develops. OP AP-1 is used to determine the leak location. RCS leakage Tech Specs are evaluated. (TS)
- 4. Loop 1 Pzr spray valve (PCV-455A) fails open (in auto). Manual control is used to close the valve. Actions are verified using OP AP-13.
- 5. A 3000 gpm LOCA occurs. EOP E-0 is implemented. The RCPs must be tripped when the trip criteria are met (within 5 min of dropping below 1300 psig in the RCS) (CT). A LOCA into containment is diagnosed, and EOP E-1 is used for subsequent actions.
- 6. A manual SI is needed (auto failure; must be actuated prior to exit from E-0) (CT) following the LOCA.
- 7. The RWST is faulted, and drains quickly down to 36% (just above the low level RHR Pp trip). The crew transitions to E-1.3 to establish a cold leg recirc lineup, but then transitions to ECA-1.1 (due to low recirc sump level) and makes up to the RWST (CT).
The scenario is terminated once the field operators have been directed to make up to the RWST using App M.
L091 NRC Sim Exam 02 Rev 1.doc Page 9 of 14 Rev 1
ATTACHMENT 1 - SIMULATOR SETUP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator IC-510 100% power, Mol, CB = 774 per Checklist
- Integrators: BA - 00, and PW - 20
- Tags: CB Pp set 1-3 Setup Drill 81 Reset normal engineering values Setup ser 0949 act,0,0,0,d,0 CB Pp set 1-3 OOS, alarm and knife switch dsc cnd12 act,0,0,0,d,0 Control Boards Place CB Pp set 1-3 in manual Setup loa cws8 2 Starts screen wash pps loa cws32 2 Setup Boards - CC1 Place Htr Grp 1-4 in ON Prior to turnover Provide OP O-28 to the crew prior to their arrival on the simulator.
CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary. CB Pp Set 1-3 Primary integrator = 20 gal, Boron = 00 gal.
Record PPC MAX (BOL = 100.1, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP C B near 774 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o Trend TAVG, ALM/MODE-1, Trend CHARGING, Sim Large on big screen o RONCONFIG is updated.
o PENs running.
o R2BCONFIG blowdown flows at 90 gpm.
o Operational mode correct for current conditions. 1 o Delta-I target slope matches Delta-I curve (DELTAICONFIG)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
Run the clear recorders program to clear digital charts All printer are on, with adequate paper/ink/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
1 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, go to APMC. Follow menu to manually override to correct mode.
L091 NRC Sim Exam 02 Rev 1.doc Page 10 of 14 Rev 1
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X Once crew has DRILL 6902 in AUTO Scenario malfunctions are inputted once the crew taken the watch takes the watch 0 min Control Boards Crew ramps the unit down @ 15 mw/min due to the storm conditions Once ramp is in xmt rcs15 3,679,5,1800,d,0 Loop 3 T C fails high progress, per lead examiner Once TC failure mal rcs3c act 0.04,120,1800,c, 40 gpm RCS leak on loop 3 has completed, txmt410b(1).gt.670,0 per lead examiner Once RCS leak cnh pzr3 6,1,15,1800,c, Loop 1 spray valve controller (PCV-455A) fails to has been jmrcs3c,0 100% (manual available) responded to, per lead examiner Once spray valve bst aux10 1,0,0,1800,c, Sets up increase in RCS leak (next event) has been xc2i013m,0 responded to, per lead examiner Once spray valve tc jistbst10, mal rcs3c Raises RCS leak rate to SBLOCA of 3000 gpm on has been act,3,5,0,d,0 loop 3 responded to, per lead examiner On trip/SI mal ppl3a act 1,0,0,d,0 Auto SI fails to actuate (CT) mal ppl3b act 1,0,0,d,0 X After Rx Trip PA DRILL 32 in AUTO NO Action on reactor trip 2 min after trip[/SI audio explode1.wav,30,1,0,c, Explosion, causing the RWST to drain to approx 36%
fnispr.lt.5,0 level over the following 10 minutes ramp asisrwst=1.605e6,600, 30,c,fnispr.lt.5,0 X Cue: (on transition to EOP E-1) RP reports that workers have reported an explosion on the 115 tank area, and also reports that the RWST on U-1 has an approx 4 foot rip a little over a third of the way up the tank.
X When requested DRILL 92 in MANUAL (do first Racks out power (breakers) for valves 8980 and in E-1.3 TWO actions ONLY) 8976 L091 NRC Sim Exam 02 Rev 1.doc Page 11 of 14 Rev 1
DRILL FILE TEXT
- NRC L091 Exam Scenario 2 (6902)
- jfb1, 04/25/11
- init 510
- clear cnd/bstr set 13
- XMT RCS15 RCS LP1 NR T-COLD: TQM-410B, TQM-410B1 #txmt410b(1) xmt rcs15 3,679,5,1800,d,0 #txmt410b(1)
- 40 gpm leak
- mal RCS3C SMALL LOCA IN BOTTOM OF COLD LEG 3 mal rcs3c act 0.04,120,1800,c,txmt410b(1).gt.670,0
- Spray valve pcv-455A failure (man works)
- CNH PZR3 PZR SPRAY CONT LOOP 1 #xcnh455g cnh pzr3 6,1,15,1800,c,jmrcs3c,0 #xcnh455g
- BST AUX10 INSTRUCTOR BISTABLE 10 #jistbst10 bst aux10 1,0,0,1800,c,xc2i013m,0 #jistbst10
- when bistable aux10 trips, loca increases to 3000 gpm tc jistbst10, mal rcs3c act,3,5,0,d,0
- si fails to actuate
- mal PPL3A SAFETY INJECTION ACTUATION FAILURE (TRAIN A) mal ppl3a act 1,0,0,d,0
- mal PPL3B SAFETY INJECTION ACTUATION FAILURE (TRAIN B) mal ppl3b act 1,0,0,d,0
- drain rwst to 36% in 10 minutes audio explode1.wav,30,1,0,c,fnispr.lt.5 ramp asisrwst=1.605e6,600,30,c,fnispr.lt.5 L091 NRC Sim Exam 02 Rev 1.doc Page 12 of 14 Rev 1
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 117 Days Operating Mode: 1 Gross Generation: 1191 MWe Power Level: 100 % Net Generation: 1148 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): 327 SCF / 306 SCFD 5 day ave NEW EMERGENT WORK:
- None SHUTDOWN TECH SPECS / ECGS:
- None ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- None TURNOVER ITEMS:
- A high swell warning is in effect. All OP O-28 guidelines are being followed. Screens are currently in manual (low speed).
- Due to an unexpected increase in the swell warning rating from 7.1 to 9.6, an ODM meeting was convened, and the decision is to take both units promptly to 25% @ 15mw/min (higher if the condenser or screens degrade).
- Condensate/booster pump set 1-3 is cleared due to high vibrations. It is not expected back for several days.
PRIORITY ITEMS FOR NEXT SHIFT:
- Ramp the unit to 25% at 15 mw/min following shift turnover.
- Continue with OP O-28 briefings.
- Be prepared to remove a condenser half from service once at 25% power (as needed) for cleaning.
OPERABILITY ITEMS:
- None L091 NRC Sim Exam 02 Rev 1.doc Page 13 of 14 Rev 1
ANNUNCIATORS IN ALARM:
- No unexpected alarms Shift Foreman Turnover TURNOVER ITEMS:
- Both units are at 100%, but will be ramping to 25% following shift brief.
- No one in containment REACTIVITY MANAGEMENT:
- Time in core life: MOL.
- Power History: Steady State, previously at 100% for 53 days. Currently power is at 100%.
- Boron concentration is 774 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 231 steps on CBD.
- Diluting the RCS approximately 20 gallons every 2 hrs.
- The last dilution was completed 5 min ago.
- Ramp Plan - use reactivity handbook for 70% load reduction.
CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
- None OTHER ABNORMAL PLANT STATUS
- See Plant Abnormal Status Board L091 NRC Sim Exam 02 Rev 1.doc Page 14 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: 3 Op-Test No.: L091-NRC Examiners: Operators:
Initial Conditions: 100% power, MOL, 774 ppm boron, Cond/Bstr pump set 1-3 cleared Turnover: Maintain 100% power Event Malf Event Event No No. Type* Description 1 R (ATC) Large Steam leak from MSR 1-1A Drain Line, 25 mw/min ramp per SM ***
2 mal eps4c C (ALL) 4 KV Bus F differential (TS) 3 pmp cnd5 C (SRO, Cond/Bstr pp 1-2 overcurrent trip at 60% power BOP) 4 cnh pzr4 C (SRO, Pzr Press Controller becomes unstable, requiring manual pressure control ATC) (TS, PCV-474) 5 xmt rms15 I (SRO) RM-15 fails high (ECG) 6 cnh mss3 I (BOP, S/G 1-2 10% dump fails open, and is closed by backup (prior to causing an SRO) overpower condition) (CT) 7 mal mss3 M (ALL) Steam line break outside containment **
8 vlv mss7-10 C (SRO, MSIVs fail open - must control AFW flow to limit C/D in ECA-2.1 (CT)
BOP)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 1. Total malfunctions (5-8) 7
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 4
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 2
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 2
L091 NRC Sim Exam 03 Rev 1.doc Page 1 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 3 Event No.: 1 Page 1 of 8 Event
Description:
Large Steam leak from MSR 1-1A Drain Line, 25 mw/min ramp per SM Time Position Applicants Actions or Behavior Cue: (from SM, during walkdown) There is a significant steam leak on the 1-1A MSR drain line.
Cue: The Shift Manager directs that U-1 be ramped down @ 25 mw/min until the leak can be isolated, or the unit taken off-line.
SRO Enters OP AP-25, Rapid Load Reduction BOP Ramp is started:
- Load target is entered into DEH
- Sets ramp rate to 25 mw/min
- Pushes GO ATC Verifies that control rods are inserting properly in AUTO ATC Verifies ON all pressurizer backup heaters ATC Maintains charging flow adequate to prevent letdown flashing BOP Verifies DFWCS in AUTO and controlling S/G levels ATC RCS is borated per reactivity handbook for estimated load reduction SRO SFM provides reactivity oversight BOP MFP suction is verified adequate ATC Verifies proper operation of steam dumps ATC Checks pressurizer pressure and level trending to program Cue: (from SM, if AP-25 point reached where staying at power question is asked)
Stabilize at 15% power, and remove the MSRs from service. An ODM meeting will be convened to evaluate further actions.
L091 NRC Sim Exam 03 Rev 1.doc Page 2 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 3 Event No.: 2 Page 2 of 8 Event
Description:
4 KV Bus F differential (TS)
Time Position Applicants Actions or Behavior ALL Observes multiple alarms and loss of power to various equipment on bus F BOP Diagnoses differential trip on bus F due to alarms (PK18-16 and/or PK18-17), blue diff light on bus F, and loss of power available white light on bus F.
ATC Observes DRPI has lost power; rod control is placed in MANUAL (immediate) per AP-27 and/or PK03-21 (may occur before or after procedure entry)
BOP May place ramp (momentarily) on hold; re-initiates per SFM SRO Enters OP AP-27 for loss of vital 4KV bus (may enter PK18-16 and/or PK18-17 first)
BOP Checks vital 4KV busses energized (only bus F off)
ATC Checks DRPI energized (off) - places rod control in manual (TS 3.1.7.B, immediate)
SRO Uses PK03-21 and OP A-3:I to place DRPI on backup power (field operator)
BOP Confirms bus F is tripped on differential ATC/BOP Checks alternate pumps running on 4KV busses BOP Checks 480 vac vital busses - only bus 1F de-energized BOP Implements Attachment 4.1 for bus 1F:
- Verifies DRPI is being placed on backup (above), or directs DRPI be placed on backup
- Places PCV-474 in CLOSE, and refers SFM to TS 3.4.11
- Assigns field actions of appendix:
o Battery charger 121 placed on the 1-1 battery (2 hr TS) o C/R vent pwr panel E-2 placed on backup o Verifies other equipment not aligned to bus 1F, and redundant equip running
- Verifies 480 vac loads running: starts PW Pp 1-2, and verified 3 CFCUs in service
- Verifies other equipment status (as time permits)
SRO Evaluates Tech Specs and ECGs:
- TS 3.1.7 - DRPI (immediate)
- TS 3.4.11.C - PORV block valve (1 hr)
operating (2 hrs)
- ECG 23.6 - Vital 480 vac swgr class 1 ventilation SRO/BOP Check unloaded DGs (shuts down DG 1-3); calls maintenance on bus fault SRO Checks OPERABILITY of ESF equipment L091 NRC Sim Exam 03 Rev 1.doc Page 3 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 3 Event No.: 3 Page 3 of 8 Event
Description:
Cond/Bstr pp 1-2 overcurrent trip at 60% power Time Position Applicants Actions or Behavior BOP Observes Cond/Booster Pp set 1-2 tripped from PK10-06 alarming and/or blue light on pump BOP Determines that there is only one Cond/Booster Pp Set running, and monitors MFP suction pressure and the DFWCS SRO Enters PK10-06, which directs crew to OP AP-15 (section D); Enters OP AP-15, sec D (may remain in AP-25, since the same important actions are taken)
BOP Verifies all available condensate/booster Pp sets running (only 1-1 is available)
BOP Checks MFP suction pressure, > 260 psig (it is not)
BOP Checks MFP suction pressure > 190 psig (yes)
BOP Verifies FCV-31 open, and LCV-12 closed (fully opens FCV-31, if suction still < 260 psig)
BOP Opens TCV-23 fully and FCV-55 (if suction pressure remains < 260 psig)
ATC/BOP Continues ramp (raises ramp rate to 40 mw/min) to raise suction pressure to > 260 psig ATC Verifies rod control in AUTO, heaters on, and DFWCS controlling (continued from AP-25 actions)
SRO Once MFP suction pressure is > 260 psig, continues ramp due to steam leak (may reduce ramp rate) (note that ramp may be continued through event, as it mitigates the event)
L091 NRC Sim Exam 03 Rev 1.doc Page 4 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 3 Event No.: 4 Page 4 of 8 Event
Description:
HC-455K becomes unstable in AUTO (manual control required) (TS)
Time Position Applicants Actions or Behavior SRO/ATC Erratic HC-455K output is observed; may also note low pressure alarms with pressure normal, as well as intermittent spray valve openings ALL Crew diagnoses that HC-455K (pressurizer pressure controller) is not controlling properly in AUTO (due to above indications continuing over time)
SRO/ATC Places HC-455K in MAN, and controls pressure in manual on HC-455K (manual control of heaters and sprays is equally acceptable in this failure); this may occur before or after entering OP AP-13)
SRO Implements OP AP-13 for pressure control malfunction SRO/BOP Stops load reduction (temporarily)
ATC/BOP Observes Pzr PORVS and safeties closed BOP/ATC Checks normal and auxiliary spray closed (may go to MAN on HC-455K any time before or during this procedure, depending on conditions and when diagnosis made)
ATC Observes erratic operation of Pzr heaters; places HC-455K in manual (may temporarily operate heaters in manual, as well); controls Pzr pressure manually BOP Verifies Pzr pressure control channels OPERABLE ATC Controls Pzr pressure in MANUAL (on HC-455K, or operates Pzr heaters and sprays in manual; either option is acceptable)
SRO Notes AUTO function (from HC-455K) for Pzr PORV PCV-474 is no longer working.
Declares PCV-474 INOPERABLE per TS 3.4.11.B. (1 hr)
SRO/BOP Notes PCV-474 block valve (8000A) needs to be closed (no power), per TS 3.4.11.B BOP Resumes ramp once stable L091 NRC Sim Exam 03 Rev 1.doc Page 5 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 3 Event No.: 5 Page 5 of 8 Event
Description:
RM-15 fails high (ECG)
Time Position Applicants Actions or Behavior ATC/SRO Observes PK11-06 and PK11-07 alarming BOP RM-15 and RM-15R are checked; only RM-15 is upscale SRO Chemistry is notified to check for S/G tube leakage SRO I&C is notified to investigate RM-15 BOP Dispatches an operator to verify that RM-15 is not selected on device 43-SJAE in the cable spreading room Cue: (if requested to check RM-15 selector [SPDS feed]) The selector is switched to RM-15 (can also see by looking at SPDS displays).
BOP Determines that the sample pp is still running on RM-15 SRO Evaluates ECG 2.1.B for RM-15 failure L091 NRC Sim Exam 03 Rev 1.doc Page 6 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 3 Event No.: 6 Page 6 of 8 Event
Description:
S/G 1-2 10% dump fails open, closed by backup air (CT)
Time Position Applicants Actions or Behavior BOP Observes red light on for PCV-20, and S/G pressure below the 10% steam dump setpoint SRO Directs PCV-20 closed BOP Attempts to place PCV-20 in manual and close; valve doesnt close SRO Directs that backup air be used to close PCV-20 BOP Cuts in backup air and closes PCV-20; valve closes (closed to prevent overpower or trip/ESF actuation) (critical task) **
SRO Refers to PK09-09 for backup air operation SRO May evaluate TS 3.7.4 (valve remains OPERABLE)
- Critical Task L091 NRC Sim Exam 03 Rev 1.doc Page 7 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 3 Event No.: 7 Page 7 of 8 Event
Description:
Steam line break outside containment Time Position Applicants Actions or Behavior ALL Increased steam flow and noise is noted, as well as dropping S/G pressures and Tavg ALL Crew responds to trip/SI by going to EOP E-0; may initiate manual SI/trip prior to automatic actuation SRO Crew enters EOP E-0 ALL Immediate actions are performed:
- Verify reactor trip
- Verify turbine trip
- Check vital 4KV bus status
- Check if SI actuated
- Announce trip/SI on PA system
- Check main generator - tripped
- Verify Phase A and containment vent isolation complete
- Checks containment spray and Phase B
- Checks main steam isolation - attempts to close MSIVs (if not done above)
- Checks excess letdown - not in service; turns on aux bldg vent charcoal filter preheater
- Checks secondary systems (MFPs tripped, only one CB Pp set running, condenser status, and opens MFP recircs
- Verifies proper operation of Aux Bldg and Control Rm vent systems; verifies containment iodine fans secured
- Verifies DGs running normally; verifies vital batteries supplied by chargers
- Verifies MSRs reset, and throttles RCP seal injection flows to normal ATC Checks RCS temperature - throttles AFW to minimum needed for heat sink ATC Checks Pzr safeties and PORVs - closed ATC Checks RCP trip criteria - stops all RCPs when criteria (< 1300 psig) is reached ATC/BOP Checks for faulted S/Gs - transitions out of EOP E-0 to E-2 ALL Implements CSFSTs L091 NRC Sim Exam 03 Rev 1.doc Page 8 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 3 Event No.: 8 Page 8 of 8 Event
Description:
MSIVs fail open - must control AFW flow to limit C/D (CT)
Time Position Applicants Actions or Behavior SRO Enters EOP E-2 for multiple faulted S/Gs SRO Directs implementation of App L to locally close all MSIVs Note: When requested to locally close the MSIVs per App L, do not reply on task progress (the scenario will end before there would have been any success on this path).
SRO/BOP Determines that NO S/Gs are intact SRO Transitions to EOP ECA-2.1, Uncontrolled Depressurization of All S/Gs SRO/BOP Confirms that all S/Gs are faulted ALL Check secondary pressure boundary, and isolate all S/Gs:
- Verifies MFIVs closed
- Verifies all B/D isolation valves (IC, OC, and sample) closed
- Verifies all 10% steam dumps closed
- Isolates steam to TDAFP (FCV-37/38) (one MDAFP is still available); FCV-38 must be isolated locally (bus failure)
Note: With a RED PATH on HEAT SINK, the crew may transition to EOP FR-H.1 (performs step 1 and then returns to ECA-2.1). The crew may also chose to stay in ECA-2.1 (allowed, but not required, by WOG EOP background)
ALL Controls feedwater flow to minimize RCS cooldown:
- Determines that RCS cooldown is > 100 F in the last hour
- Throttles AFW to 25 gpm to S/Gs 1 & 2 prior to a MAGENTA PATH on RCS INTEGRITY (MDAFP 1-3 is not available) (WOG CT ECA-2.1-A) (critical task) **
- Checks RCS temperature - stable or decreasing (uses AFW and steam dumps to control if temperature is rising)
Terminate scenario once AFW flow has been throttled to approx 25 gpm for S/Gs 1 & 2
- Critical Task L091 NRC Sim Exam 03 Rev 1.doc Page 9 of 16 Rev 1
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES
- 1. A steam leak on the MSRs prompts the crew (per shift manager direction) to ramp the unit down at 25 mw/min.
- 2. A bus differential trip occurs on 4KV Bus F. Actions to place alternate equipment in service will be per OP AP-27 (including placing DRPI on backup power). (TS)
- 3. At 60-75% power (still ramping), the 1-2 Condensate/booster Pp Set trips. With the 1-3 pump cleared, this will impact MFP suction pressure. Actions to maintain MFP suction pressure will be taken per OP AP-15, section D (keep ramping, and ensure condensate flowpaths to MFPs open) (the crew may use the same guidance in OP AP-25).
- 4. HC-455K (Pzr press controller) becomes unstable, requiring manual control of pressure.
OP AP-13 is used to stabilize the plant and respond to the failure. With AUTO control not available, Pzr PORV PCV-474 is declared INOPERABLE (TS 3.4.11.B). (TS)
- 5. RM-15 fails high. The rad monitor is compared to the redundant channel, and actions are taken for a failed RM-15, including consulting ECG 2.1. (ECG)
- 6. S/G 1-2 10% steam dump (PCV-20) fails open. Closing using the controller fails, but cutting in backup air is successful in closing the valve (CT). TS 3.7.4 may be evaluated (valve is OPERABLE).
- 7. The steam leak outside containment degrades into a major steam break. A reactor trip and safety injection occur, and the crew takes normal EOP action for an SI. Transition from E-0 is to E-2 due to multiple faulted S/Gs.
- 8. With all of the MSIVs failing to close, the crew takes action to locally close the MSIVs, and then transition to ECA-2.1, where AFW will be throttled to 25 gpm (to S/Gs 1 and 2; MDAFP 1-3 is not available due to earlier bus loss) (CT) to control the cooldown.
The scenario is terminated once the S/G AFW flowrates are throttled to approx 25 gpm per lead (leads 1 and 2).
L091 NRC Sim Exam 03 Rev 1.doc Page 10 of 16 Rev 1
ATTACHMENT 1 - SIMULATOR SETUP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator IC-510 100% power, Mol, CB = 774 per Checklist
- Integrators: BA - 00, and PW - 15
- Tags: CB Pp set 1-3 Setup Drill 81 Reset normal engineering values Setup ser 0949 act,0,0,0,d,0 CB Pp set 1-3 OOS, alarm and knife switch dsc cnd12 act,0,0,0,d,0 Control Boards Place CB Pp set 1-3 in manual Setup Boards - CC1 Place 1-4 Htr Grp in ON CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary. CB Pp Set 1-3 Primary integrator = 15 gal, Boron = 00 gal.
Record PPC MAX (BOL = 100.1, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP C B near 774 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o Trend TAVG, ALM/MODE-1, Trend CHARGING, Sim Large on big screen o RONCONFIG is updated.
o PENs running.
o R2BCONFIG blowdown flows at 90 gpm.
o Operational mode correct for current conditions. 1 o Delta-I target slope matches Delta-I curve (DELTAICONFIG)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
Run the clear recorders program to clear digital charts All printer are on, with adequate paper/ink/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
1 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, go to APMC. Follow menu to manually override to correct mode.
L091 NRC Sim Exam 03 Rev 1.doc Page 11 of 16 Rev 1
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X Once crew has DRILL 6903 in AUTO Scenario malfunctions are inputted once the crew taken the watch takes the watch X Cue: (from SM, during walkdown) There is a significant steam leak on the 1-1A MSR drain line.
X Cue: (immediately following 1st cue) The Shift Manager directs that U-1 be ramped down @ 25 mw/min until the leak can be isolated, or the unit taken off-line.
X 0 min, per SM Control Boards Ramps unit due to steam leak on 1-1A MSR Once ramp is in mal eps4c act 2,0,1800,d,0 4KV Bus F differential trip progress ( 95%),
per lead examiner X When requested DRILL 11 in AUTO Racks out breaker for 8000A (PCV-474 block valve) to remove power from 8000A X When requested loa eps1 act,1,0,60,d,0 Transfers DRPI power to backup source to transfer DRPI to backup X When requested DRILL 46 in AUTO Transfers 1-1 battery to the 121 charger to do attachment loa ven18 act,1,0,120,d,0 Transfers C/R vent pwr E2 to backup source for 480 vac bus 1F tasks X Cues: As the AP-27 actions (above) are competed, report each of them as completed to the Control Room Approx 60% - pmp cnd5 6,2.96,5,0,c, OC trip on the 1-2 CB Pp set (can be activated as 75% power, per fnispr.lt.60,0 long as power is < 75%)
lead examiner xmt mfw110 3,245,60,0,c, xv3o224b,0 MFP suction pressure indication biased to stay above 200 psig (but below 260 psig); (can clear once FCV-31, FCV-55, and TCV-23 manipulations have been taken)
X Cue: (from SM, if AP-25 point reached where the staying at power question is asked) Stabilize at 15% power, and remove the MSRs from service. An ODM meeting will be convened to evaluate further actions.
Following CB Pp cnh pzr4 4,80,0,900,c, HC-455K becomes unstable in AUTO, requiring actions, per lead xv3o224b,0 manual control (gain set to 80 times normal) examiner (conditional on CB Pp set OC light)
Once HC-455K xmt rms15 3,0.2,5,1800,c, RM-15 fails high (conditional on CB Pp set blue light) failure actions xv3o224b, 0 taken, per lead examiner X Cue: (if requested to check RM-15 selector [SPDS feed]) The selector is switched to RM-15 (can also see by looking at SPDS displays).
(continued on next page)
L091 NRC Sim Exam 03 Rev 1.doc Page 12 of 16 Rev 1
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION (cont)
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION Once RM-15 cnh mss3 2,1,30,1800,c, PCV-20 (1-2 S/G 10%er) fails open (only B/U air failure completed, rrmsr15.gt.0.02,0 works) per lead examiner N/A (0 min) vlv mss7 2,1,0,0,d,0 MSIVs set up to fail open on next event vlv mss8 2,1,0,0,d,0 vlv mss9 2,1,0,0,d,0 vlv mss10 2,1,0,0,d,0 Once PCV-20 mal mss4 act 1e+07,120,1800, Steamline break OC on lead 1-4 failure response c,xv3i346c,0 completed, per lead examiner X After Rx Trip PA DRILL 32 in AUTO NO Action on reactor trip X Note: When requested to locally close the MSIVs per App L, do not reply on task progress (the scenario will end before there would have been any success on this path).
L091 NRC Sim Exam 03 Rev 1.doc Page 13 of 16 Rev 1
DRILL FILE TEXT
- NRC L091 Exam Scenario 3 (6903)
- glh1, 04/25/11
- init 510
- cnd/bstr set 13 cleared
- Bus F differential mal eps4c act 2,0,1800,d,0
- PMP CND5 CONDENSATE BOOSTER PP 12 #ocbp12 pmp cnd5 6,2.96,5,0,c,fnispr.lt.60,0 #ocbp12 xmt mfw110 3,245,60,0,c,xv3o224b,0 #pcfw156
- hc-455k becomes unstable (high gain) cnh pzr4 4,80,0,900,c,xv3o224b,0 #xcnhpzrp
- rm-15 fails high xmt rms15 3,0.2,5,1800,c,xv3o224b,0 #rrmsr15
- pcv-20 controller fails to 100%
cnh mss3 2,1,30,1800,c,rrmsr15.gt.0.02,0 #xcnh526e
- mal MSS4 STEAMLINE BREAK OUTSIDE CONTAINMENT (DOWNSTEAM OF MSIV) mal mss4 act 1e+07,120,1800,c,xv3i346c,0
- MSIVs fail to close vlv MSS7 2,1,0,0,d,0 #RMSF041 vlv MSS8 2,1,0,0,d,0 #RMSF042 vlv MSS9 2,1,0,0,d,0 #RMSF043 vlv MSS10 2,1,0,0,d,0 #RMSF044 L091 NRC Sim Exam 03 Rev 1.doc Page 14 of 16 Rev 1
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 101 Days Operating Mode: 1 Gross Generation: 1191 MWe Power Level: 100 % Net Generation: 1148 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): 317 SCF / 326 SCFD 5 day ave NEW EMERGENT WORK:
- None SHUTDOWN TECH SPECS / ECGS:
- None ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- None TURNOVER ITEMS:
- CB Pp Set 1-3 is cleared due to high vibrations. RTS estimate is approximately 3 shifts.
PRIORITY ITEMS FOR NEXT SHIFT:
- Maintain current power level.
OPERABILITY ITEMS:
- None ANNUNCIATORS IN ALARM:
- None L091 NRC Sim Exam 03 Rev 1.doc Page 15 of 16 Rev 1
Shift Foreman Turnover TURNOVER ITEMS:
- U maintain 100% - no one in containment
- U-2 is at 100%
REACTIVITY MANAGEMENT:
- Time in core life: MOL.
- Power History: Steady State, previously at 100% for 27 days. Currently power is at 100%.
- Boron concentration is 774 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 231 steps on CBD.
- Diluting the RCS approximately 15 gallons every 1.5 hrs.
- The last dilution was completed 15 min ago.
- Rod motion: none planned, as needed to maintain I on target CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
- None OTHER ABNORMAL PLANT STATUS
- See Plant Abnormal Status Board L091 NRC Sim Exam 03 Rev 1.doc Page 16 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: 4 Op-Test No.: L091-NRC Examiners: Operators:
Initial Conditions: 8% power, MOL, 1181 ppm boron Turnover: Increase power to 15% using rods per OP L-3 Event Malf Event Event No No. Type* Description 1 R (ATC) Pull rods to increase power 2 mal nis3a I (SRO, Intermediate Range detector NI-35 fails low (TS) @ 9.5% power; blocks PR ATC) low and IR trips at 10% power 3 xmt rms11 I (SRO) RM-12 fails high (TS) 4 N (BOP) Places CFCU drain collection in service (CFCU to low speed) 5 cnh pzr1 I (SRO, Pzr level master controller (HC-459D) fails low, requiring manual charging ATC) flow control 6 mal mss3c M (ALL) S/G 1-3 steam line break OC - isolate faulted S/G (prior to E-2 exit) (CT) 7 pmp cvc1/2 C (BOP) Both CCPs must be manually started on SI (prior to E-0 exit) (CT) 8 mal rcs4c M (ALL) S/G 1-3 SGTR (600 gpm) - concurrent with steam break; crew will transition to ECA-3.1, and either C/D the RCS or determine that the C/D rates have already been exceeded (and not start a C/D) (CT) **
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 1. Total malfunctions (5-8) 6
- 2. Malfunctions after EOP entry (1-2) 2
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 2
- 5. EOPs entered/requiring substantive actions (1-2) 2
- 6. EOP contingencies requiring substantive actions (0-2) 1
- 7. Critical tasks (2-3) 3
L091 NRC Sim Exam 04 Rev 1.doc Page 1 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 4 Event No.: 1 Page 1 of 7 Event
Description:
Raise power to 15%
Time Position Applicants Actions or Behavior ATC Power is raised to 15% using control rods
- Power raised using 1 step rod pulls
- Steam dumps are adjusted (only if needed) to ensure steam pressure does not lift 10%
steam dumps SRO Provides reactivity oversight L091 NRC Sim Exam 04 Rev 1.doc Page 2 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 4 Event No.: 2 Page 2 of 7 Event
Description:
Intermediate Range detector NI-35 fails low (TS) @ 9.5%, block IR and PR low power trips @ 10% power (P-10)
Time Position Applicants Actions or Behavior ATC Determines that NI-35 has failed low from meter and recorder indications SRO Implements OP AP-5 for NI-35 failure ATC Determines that no additional controls need to be placed in manual due to the failure SRO/BOP Determines that the failure is not Eagle-21 related (PK06-01 and PK06-03 are OFF)
ATC Determines that NI-35 cannot be deselected for control or recorder input BOP Verifies steam dumps are not actuated SRO Notifies I&C to investigate NI-35 failure ATC Places OOS stickers on failed channel indications SRO Determines Tech Spec actions using Att 4.1 (pg 18 for NIs):
- TS 3.3.1.F (24 hrs to go < P-6 or > P-10)
- TS 3.3.1.G (not applicable unless both chan failed)
- TS 3.3.1.S (not applicable > P-6)
- (SFM discretion) may have IR trip bypassed from NI-35 (not TS action)
Cue: (from SM, once TS 3.3.1.F determined) Continue the power ramp and go > P-10, as previously planned.
SRO/ATC Continues to raise power to 15%
SRO/ATC Once power is raised to greater than 10% (P-10 permissive ON, PK08-05):
- BLOCK both trains of the Intermediate Range High Flux Reactor Trip and Rod Stop, and verifies proper alarm response
- BLOCK both trains of the Power Range Low Setpoint Reactor Trip. And verifies proper alarm response L091 NRC Sim Exam 04 Rev 1.doc Page 3 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 4 Event No.: 3&4 Page 3 of 7 Event
Description:
RM-12 failure (TS) ; places CFCU in slow speed (collection monitoring system to service)
Time Position Applicants Actions or Behavior ALL Crew recognizes PK11-21 in alarm (high proc rad alarm)
ALL Implements ARP PK11-21 (may use PK11-22) (input 1066, proc monitor hi rad)
- Checks annunciator printout (or A&E viewer / Ronan display) to determine alarm input
- Uses PPC or walkdown of rad monitors to determine that RM-12 has failed
- Goes to section 2.4, and implements procedure to place CFCU collection monitoring system in service
- Evaluates TS 3.4.15
- TS 3.4.15.C (applicable until CFCU drain collection aligned)
- May notify shift CARP tech per OP O-3 BOP/ATC Places collection monitoring system in service (OP H-2:I, section 6.5)
- Transfers one running CFCU to slow speed per section 6.3.2
- Places drain collection selector to CFCU transferred to slow speed, and verifies that the appropriate drain valve closed light comes on L091 NRC Sim Exam 04 Rev 1.doc Page 4 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 4 Event No.: 5 Page 4 of 7 Event
Description:
HC-459D (Pzr level master controller) fails low Time Position Applicants Actions or Behavior ALL Observes some or all of the following:
- Charging flow dropping
- HC-459D and/or FCV-128 output dropping
- All four RCP seal injection alarms come in (PK05-01 through 04)
ALL Crew determines that a low charging flow is not called for, and takes manual control of FCV-128 (may try to control HC-459D in manual, but will not be successful)
ATC Takes manual control of FCV-128 (may try to control HC-459D in manual, but will not be successful), and restores charging flow to normal (maintains pzr level) (note: this may be done prior to procedure entry to stabilize the plant and prevent harm to the letdown system)
SRO Enters OP AP-17 (loss of charging), section B (charging sys equip malfunctions)
SRO/ATC Stops power rise BOP Checks letdown flow normal (may note rising temperature due to low charging)
BOP/ATC Verifies charging pumps suction is normal/stable ATC Observes (now or earlier) that charging flow is NOT as expected ATC Checks HC-459D and FCV-128 controllers, notes that both are abnormally low ATC Places FCV-128 controller in MANUAL, and restores charging flow (and maintains normal pzr level) (may have been done earlier) (may try HC-459D in manual, but will be unsuccessful)
SRO Maintenance is notified of the HC-459D failure.
L091 NRC Sim Exam 04 Rev 1.doc Page 5 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 4 Event No.: 6&7 Page 5 of 7 Event
Description:
S/G 1-3 steamline break OC - isolate faulted S/G, AND start both ECCS CCPs on Safety Injection (CT)
Time Position Applicants Actions or Behavior ALL Steam break diagnosed from increased steam flows, S/G alarms, and increased noise levels ALL Crew enters EOP E-0 on trip/SI actuation - a manual trip/SI may be performed if time allows ALL Immediate actions are performed:
- Verify reactor trip
- Verify turbine trip
- Check vital 4KV bus status
- Announce trip/SI on PA system, and checks main generator - tripped
- Verify Phase A and containment vent isolation complete
- Starts both ECCS CCPs (prior to exit from E-0; at least one pump required for critical task) (critical task) (may have been performed earlier) **
- Verify feedwater isolation complete
- Checks containment spray and Phase B
- Checks main steam isolation status and AFW status
- Checks excess letdown isolated, and turns on aux bldg vent charcoal filter preheater
- Checks secondary systems (MFPs tripped, only one CB Pp set running, condenser status, and opens MFP recircs
- Verifies proper operation of Aux Bldg and Control Rm vent systems; verifies containment iodine fans secured
- Verifies DGs running normally; verifies vital batteries supplied by chargers
- Verifies MSRs reset, and throttles RCP seal injection flows to normal ATC Checks RCS temperature - throttles AFW to minimum needed for heat sink ATC Checks Pzr safeties and PORVs - closed ATC Checks RCP trip criteria, and trips RCPs ATC/BOP Checks for faulted S/Gs - transitions out of EOP E-0 to E-2 with 1-3 S/G faulted ALL Implements CSFSTs
- Critical Task L091 NRC Sim Exam 04 Rev 1.doc Page 6 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 4 Event No.: 6 Page 6 of 7 Event
Description:
S/G 1-3 steamline break OC - isolate faulted S/G (CT) (cont)
Time Position Applicants Actions or Behavior SRO Enter EOP E-2 for 1-3 faulted S/G Cue: (from workers leaving area) There is a large amount of steam in the U-1 115 penetration area.
BOP Verifies ALL MSIVs and bypasses are closed BOP Checks for any intact S/G BOP Identifies 1-3 S/G as faulted BOP Isolates 1-3 faulted S/G (see BOLD substeps below, completed prior to exit from EOP E-2) (critical task): **
- Verifies MFIV closed
- Verifies S/G 1-3 10% steam dump closed
- Closes FCV-38 to isolate steam from 1-3 S/G to TDAFP BOP Verifies AFW flow to at least one intact S/G BOP Checks CST level > 10%
BOP Removes WR T hot input to SCMM for loop 3
- Critical Task L091 NRC Sim Exam 04 Rev 1.doc Page 7 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 4 Event No.: 8 Page 7 of 7 Event
Description:
SGTR (600 gpm) on 1-3 S/G (concurrent with steam break) (CT)
Time Position Applicants Actions or Behavior Cue: (from RP) The SPING near the U-1 115 Pen area is in alarm.
ALL (EOP E-2) Checks for SGTR (may identify here, or in E-1.1); transitions to EOP E-3 if diagnoses made (on rising level and/or SPING reports)
ALL Checks ECCS termination criteria (most likely satisfied); transitions to EOP E-1.1, SI Termination ALL May perform E-1.1 actions, until Foldout Page (FOP) criteria noted for EOP E-3 transition ATC/BOP Observes lowering Pzr level, and rising level and pressure in the 1-3 S/G; FOP criteria met for SGTR; transitions to EOP E-3 ATC Checks if RCPs should be stopped SRO Identifies 1-3 S/G as ruptured; samples S/Gs for activity BOP Isolate ruptured S/G using App FF:
- Sets 1-3 S/G 10% steam dump controller to 8.67 turns (1040 psig)
- Verifies 1-3 S/G 10% steam dump closed
- Verifies 1-3 S/G MSIV and bypass valves closed
- Verifies FCV-38 closed
- Verifies SGBD valves (OC and sample) for 1-3 S/G closed
- Checks ruptured S/G isolated from intact S/Gs - notifies SFM
- Verifies WR T hot input to SCMM disabled for loop 3
- Directs S/G sampling ATC Maintains feedflow isolated to the 1-3 S/G ATC Checks ruptured S/G pressure > 225 psig SRO Transitions to EOP ECA-3.1 for a faulted/ruptured S/G ATC/BOP Verifies SI and Phase A/B reset; establishes instrument air to containment ALL Verifies busses are on S/U power; places pzr htrs in OFF, checks cont spray status SRO/BOP Maintains AFW secured to faulted/ruptured S/G (1-3)
ATC/BOP Checks RHR pumps; Checks aux bldg rad monitors, Check/maintain intact S/G levels BOP Initiates RCS cooldown at < 100 °F/hr, OR the decision is made NOT to start a cooldown, because the cooldown rate is already greater than 100°F in last hour (as indicated by RCS WR T c < 450°F) (critical task) **
Terminate the scenario once the cooldown (or decision not to cooldown) is made in EOP ECA-3.1
- Critical Task L091 NRC Sim Exam 04 Rev 1.doc Page 8 of 14 Rev 1
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES
- 1. Raise power to 8% per OP L-3. Turbine is already at 1800 rpm per OP C-3:II.
- 2. NI-35 fails low @ 9.5% power. OP AP-5 is used for recovery, and Tech Specs are evaluated. Power is raised above P-10 to satisfy the TS on the failed instrument (SM cue).
IR and PR low power trips are blocked at 10% (P-10). (TS)
- 3. RM-12 fails high. ARPs PK-11-21 and/or 11-22 are used to respond. Tech Specs are evaluated, and it is determined that the CFCU collection monitoring systems needs to be placed in service. (TS)
- 4. The CFCU collection monitoring system is placed in service per OP H-2:I and TS 3.4.15.
- 5. HC-459D (Pzr level master controller) fails low, causing charging flow to drop. The crew will restore charging, using FCV-128 in manual control (letdown may be isolated and returned to service due to the low flow conditions, but is not a required task for the scenario). OP AP-17, section B, is used to respond to the failure.
- 6. A steam break (OC) occurs on the 1-3 S/G, causing a reactor trip and SI. EOPs E-0 and E-2 are used to isolate the faulted S/G (CT).
- 8. Concurrent with the steam break on 1-3 S/G, a 600 gpm SGTR occurs on the 1-3 S/G, requiring the crew to verify isolation in EOP E-3, and then transition to EOP ECA-3.1 to respond to the faulted/ruptured S/G. The crew must start a cooldown , OR determine that the previous cooldown precludes the start of additional cooldown (ie; RCS WR T c is <
450°F (CT).
The scenario is terminated once the cooldown is started in ECA-3.1, OR the decision is made NOT to start a cooldown (based on the previous amount of cooldown).
L091 NRC Sim Exam 04 Rev 1.doc Page 9 of 14 Rev 1
ATTACHMENT 1 - SIMULATOR SETUP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator Load snap31 and IC_31 from exam 8% power, Mol, CB = 1181, turbine rolling at per Checklist flash drive 1800 rpm INIT 31
- Integrators: BA - 00, and PW - 100
- Tags: none Setup Drill 81 Reset normal engineering values Setup Boards - CC1 Place Htr Grp 1-4 in ON CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary. NONE Primary integrator = 100 gal, Boron = 00 gal.
Record PPC MAX (BOL = 100.1, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP C B near 1181 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o Trend TAVG, ALM/MODE-1, Trend CHARGING, Sim Large on big screen o RONCONFIG is updated.
o PENs running.
o R2BCONFIG blowdown flows at 90 gpm.
o Operational mode correct for current conditions. 1 o Delta-I target slope matches Delta-I curve (DELTAICONFIG)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
Run the clear recorders program to clear digital charts All printer are on, with adequate paper/ink/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
1 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, go to APMC. Follow menu to manually override to correct mode.
L091 NRC Sim Exam 04 Rev 1.doc Page 10 of 14 Rev 1
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X Once crew has DRILL 6904 in AUTO Scenario malfunctions are inputted once the crew taken the watch takes the watch 9.5%, per lead mal nis3a act -11,20,0,c, Intermediate Range detector NI-35 fails low @ 9.5%
examiner fnispr.gt.9.5,0 X Cue: (from SM, once TS 3.3.1.F determined) Continue the power ramp to 15%, and go > P-10, as previously planned.
Following IR/PR xmt rms11 3,1e+06,30,60,c, RM-12 fails high blocks at P-10, xc1i070b,0 per lead examiner Once CFCU cnh pzr1 2,0,60,1800,c, HC-459D fails low collection xc1i070b,0 monitoring system placed in service, per lead examiner Once charging mal mss3c act 4.05e+06,30, S/G 1-3 steam break OC has been 1800,c,xc2i016m,0 returned to normal, per lead examiner Upon SI pmp cvc1 1,0,0,0,d,0 Both ECCS CCPs must be manually started pmp cvc2 1,0,0,0,d,0 X Cue: (from RP, report 2 min after trip) Workers in the area reported a large amount of steam in the U-1 115 penetration area prior to leaving the area a couple of minutes ago.
On trip/SI mal rcs4c act 600 gpm SGTR on the 1-3 S/G (1-3 is ruptured and 600,60,0,c,jpplp4,0 faulted)
X After Rx Trip PA DRILL 32 in AUTO NO Action on reactor trip X Cue: (just after EOP E-2 entry) The SPING near the U-1 115 Pen area is in alarm.
When S/G activity DRILL 17 in AUTO Opens sample valves locally for all S/Gs samples requested (and sample lineup made)
L091 NRC Sim Exam 04 Rev 1.doc Page 11 of 14 Rev 1
DRILL FILE TEXT
- NRC L091 Exam Scenario 4 (6904)
- jfb1, 04/26/11
- init 31 (load IC_31 and snap31 first)
- (8%, turbine rolling at 1800 rpm, ready for rod pull to 15%)
- mal NIS3A INTERMEDIATE RANGE CHANNEL 35 FAILURE - AMPS mal nis3a act -11,20,0,c,fnispr.gt.9.5,0
- RM-12 fails high (after P-10 blocks)
XMT RMS11 3,1e+06,30,60,c,xc1i070b,0 #rrmsr12
- HC-459D fails low (conditional on P-10 blocks) cnh pzr1 2,0,60,1800,c,xc1i070b,0 #xcnhpzrl
- mal MSS3C STEAMLINE BREAK OUTSIDE CONTAINMENT (S/G #3)
- (conditional on going to manual on fcv-128) mal mss3c act 4.05e+06,30,1800,c,xc2i016m,0
- PMP CVC1 CHARGING PP 11 (CENT.) #ocvp11 pmp cvc1 1,0,0,0,d,0 #ocvp11
- PMP CVC2 CHARGING PP 12 (CENT.) #ocvp12 pmp cvc2 1,0,0,0,d,0 #ocvp12
- mal RCS4C SG 1-3 TUBE RUPTURE AT TOP OF TUBE mal rcs4c act 600,60,0,c,jpplp4,0 L091 NRC Sim Exam 04 Rev 1.doc Page 12 of 14 Rev 1
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 0 Days Operating Mode: 1 Gross Generation: 0 MWe Power Level: 8 % Net Generation: 0 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): n/a SCF / 305 SCFD 5 day ave NEW EMERGENT WORK:
- None SHUTDOWN TECH SPECS / ECGS:
- None ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- None TURNOVER ITEMS:
- OP L-3 is complete to step 6.39, ready to proceed to 15% power.
- OP C-3:II is complete, with turbine rolling at 1800 rpm PRIORITY ITEMS FOR NEXT SHIFT:
- Raise power to 15%
- Parallel the unit, and proceed to 28% power hold point OPERABILITY ITEMS:
- None ANNUNCIATORS IN ALARM:
- Alarms are consistent with normal operation at 8% power L091 NRC Sim Exam 04 Rev 1.doc Page 13 of 14 Rev 1
Shift Foreman Turnover TURNOVER ITEMS:
- U raise power to 15%, parallel to grid, and raise power to 28%
- No one is in containment
- U-2 is at 100%
REACTIVITY MANAGEMENT:
- Time in core life: MOL.
- Power History: tripped 4 days ago, previously at 100% for 43 days. Currently power is at 8%.
- Boron concentration is 1181 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 105 steps on CBD.
- Reactivity Plan: use rods to raise power to 15%. Once paralleled, dilution of 2000 gallons will be needed the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> while raising power to 28%; use rods to maintain I on target band. Another ramp plan will be available for raising power from 30% - 100%.
CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
- None OTHER ABNORMAL PLANT STATUS
- See the Plant Abnormal Status Board L091 NRC Sim Exam 04 Rev 1.doc Page 14 of 14 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: 5 Op-Test No.: L091-NRC Examiners: Operators:
Initial Conditions: 100% power MOL, 774 ppm boron, H 2 delivery in progress Turnover: RCP 1-2 elevated vibration - SM directs ramp offline (shutdown) at 10 mw/min Event Malf Event Type* Event No No. Description 1 R (ATC) Ramps unit offline at 10 mw/min 2 xmt mfw70 I (SRO) S/G 11 FW flow channel FT-511 fails low 3 xmt tur2 I (SRO, ATC) PT-505 fails low (TS) 4 mal cvc42 I (SRO, ATC) LT-461 failure (TS) 5 N (ALL) Return normal letdown to service 6 cnv mfw69 I (SRO, BOP) FT-510 fails low, causes FCV-510 to go to manual 7 mal sei1 M (ALL) Seismic event, causing DBA LOCA - must align cold leg recirc within 10 mal rcs1 minutes of reaching 33% RWST level (CT) (TCOA) **
8 vlv sis1/2 C (BOP) Charging Injection valve 8803A or B must be manually opened (prior to E-0 exit) (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 1. Total malfunctions (5-8) 6
- 2. Malfunctions after EOP entry (1-2) 1
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 2
- 6. EOP contingencies requiring substantive actions (0-2) 0
- 7. Critical tasks (2-3) 2
- This DBA LBLOCA was evaluated against TCOA #8, and is similar to the TCOA bases event, so TCOA time limits will be applied to the scenario (operators have 10 min to align to cold leg recirculation, as timed from the RWST reaching 33% [alarm comes in] and finishing the alignment [8804A open, which is the last significant action in the lineup]).
L091 NRC Sim Exam 05 Rev 1.doc Page 1 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 5 Event No.: 1 Page 1 of 9 Event
Description:
Ramps unit down at 10 mw/min Time Position Applicants Actions or Behavior SRO Enters OP AP-25, Rapid Load Reduction BOP Ramp is started:
- Load target is entered into DEH
- Sets ramp rate to 10 mw/min
- Pushes GO ATC Verifies that control rods are inserting properly in AUTO ATC Verifies ON all pressurizer backup heaters ATC Maintains charging flow adequate to prevent letdown flashing BOP Verifies DFWCS in AUTO and controlling S/G levels ATC RCS is borated per reactivity handbook SRO SFM provides reactivity oversight BOP MFP suction is verified adequate ATC Verifies proper operation of steam dumps ATC Checks pressurizer pressure and level trending to program L091 NRC Sim Exam 05 Rev 1.doc Page 2 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 5 Event No.: 2 Page 2 of 9 Event
Description:
FT-511 (1-1 S/G feed flow) fails low Time Position Applicants Actions or Behavior SRO/ATC Crew responds to DFWCS alarm, PK09-15 and/or PK09-01 ATC Checks that all MFRVs and MFRV Bypasses are still in AUTO ATC/BOP Uses board indications and DFWCS alarm screen to diagnose FT-511 failure SRO SFM may have ramp put on hold during failure.
SRO OP AP-5 is entered for the flow transmitter failure ATC DFWCS is left in auto, since the remaining channel was selected by the arbitration signal BOP Determines that the failure is not Eagle-21 related ATC Determines that the failed channel cannot be deselected (done automatically)
ATC Determines that the failed channel cannot be deselected for recorder (done automatically)
BOP Checks steam dumps not actuated SRO Notifies I&C to investigate the FT-511 failure BOP Places OOS stickers on affected indications (Att 4.1)
ALL May evaluate power indications (calorimetric and official power indication) vs Ops Policy C-1 SRO Evaluates affected Tech Specs using Att 4.1:
- FT-511 is not Tech Spec related ALL Ramp is continued (if placed on hold during diagnostics), per SFM L091 NRC Sim Exam 05 Rev 1.doc Page 3 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 5 Event No.: 3 Page 3 of 9 Event
Description:
PT-505 (turbine impulse pressure) fails low (TS)
Time Position Applicants Actions or Behavior ALL Observes control rods are driving inward, and steam dump modulate and trip open lights are lit on VB-3, as well as C-5 alarm (PK08-11)
ALL Comparisons with the reactor and turbine load show no need for rod motion and/or PT-505 failure (low) is seen on VB-3, the PPC, or the Triconex turbine HMI ATC Control rods are taken to manual SRO OP AP-5 is entered for the PT-505 failure ATC Control rods are verified in manual (T ref signal failed low)
BOP Determines that the failure is not Eagle-21 related ATC Determines that the failed channel cannot be deselected ATC Determines that the failed channel cannot be deselected for recording BOP Checks steam dumps not actuated (modulate and trip open signals present - SFM may use the STP referenced in Att 4.1 to place steam dumps in pressure mode)
SRO Notifies I&C to investigate the PT-505 failure BOP Places OOS stickers on affected indications (Att 4.1)
SRO Evaluates affected Tech Specs using Att 4.1:
- TS 3.3.1.T PC-505 (P-13) (1 hr)
ALL Ramp is continued (if placed on hold during diagnostics)
L091 NRC Sim Exam 05 Rev 1.doc Page 4 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 5 Event No.: 4 Page 4 of 9 Event
Description:
Pzr level channel LT-461 fails low (TS)
Time Position Applicants Actions or Behavior ALL Diagnoses LT-461 failed low by comparison with other channels, loss of letdown flow, and/or rise in charging flow and related alarms BOP Observes that letdown has isolated SRO Enters OP AP-5 for Pzr Level channel failure ATC Level control is placed in MANUAL, if not already done. Operator may reduce charging to minimum (RCP seals only).
BOP Determines that the failure is not Eagle-21 related (PK06-01 and PK06-03 are OFF)
ATC Verifies that level controller is in manual, and swaps controlling channels off of LT-461 (LT459/460 position)
ATC Verifies that the channel selected for recording is not LT-461 BOP Verifies steam dumps are not actuated SRO Notifies I&C of the LT-461 failure ATC Places OOS stickers on failed channel indications (uses Att 4.1)
SRO Determines Tech Spec actions using Att 4.1:
- TS 3.3.1.M (trip bistables w/i 72 hrs)
ATC Level is controlled in manual, pending return of letdown SRO Makes decision to place letdown back in service L091 NRC Sim Exam 05 Rev 1.doc Page 5 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 5 Event No.: 5 Page 5 of 9 Event
Description:
Restores Normal Letdown Time Position Applicants Actions or Behavior BOP Reviews Precautions and Limitations of OP B-1A:XII SRO Performs reactivity brief for returning letdown.
BOP Manually adjust Letdown temperature control, TCV-130, to 35-40% demand.
BOP Check open letdown isolation valve 8152.
BOP Place letdown back pressure control valve, PCV-135 in manual and open 60%.
BOP Open letdown isolation valves LCV-459 and LCV-460.
ATC Increase normal charging to 87 gpm and adjust RCP seal injection flow to between 8 GPM and 13 GPM per RCP using HCV-142.
BOP Open orifice isolation valve 8149C.
BOP Adjust PCV-135 to control at 350 psig, and place in Auto.
ATC Adjust charging flow and when pressurizer level is on reference, return to auto.
BOP Adjust TCV-130 to maintain normal letdown temperature and return to Auto L091 NRC Sim Exam 05 Rev 1.doc Page 6 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 5 Event No.: 6 Page 6 of 9 Event
Description:
FT-510 (1-1 S/G feed flow) fails low, causes FCV-510 to fail to manual Time Position Applicants Actions or Behavior SRO/ATC Observes DFWCS alarm (PK09-15); PK09-10 (Failed to Manual) alarms also comes in ATC/BOP Checks that all DFWCS controls are in auto; notes FCV-510/1510 have failed to manual BOP Takes manual control of 1-1 S/G level and maintains level on setpoint SRO OP AP-5 is entered for the flow transmitter failure ATC DFWCS is controlled in manual for the 1-1 S/G (loss of both feed flow signals)
BOP Determines that the failure is not Eagle-21 related ATC Determines that the failed channel cannot be deselected (both channels failed)
ATC Determines that the failed channel cannot be deselected for recorder (both channels failed)
BOP Checks steam dumps not actuated SRO Notifies I&C to investigate the FT-510 failure, as well as FT-511 BOP Places OOS stickers on affected indications (Att 4.1)
SRO Evaluates affected Tech Specs using Att 4.1:
- FT-510 is not Tech Spec related ALL Ramp may be continued (if placed on hold during diagnostics)
L091 NRC Sim Exam 05 Rev 1.doc Page 7 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 5 Event No.: 7&8 Page 7 of 9 Event
Description:
Seismic Event, and DBA LOCA (TCOA to align to CL recirc w/I 10 min) (CT), and Charging Injection valve 8803A or B must be opened manually (CT)
Time Position Applicants Actions or Behavior ALL Seismic event is felt and heard in the control room ALL Observes trip/Safety Injection due to rapidly dropping Pzr level and pressure SRO Crew enters EOP E-0 ALL Immediate actions are performed:
- Verify reactor trip
- Verify turbine trip
- Check vital 4KV bus status
- Announce trip/SI on PA system
- Check main generator - tripped
- Verify Phase A and containment vent isolation complete
- Opens charging injection valves 8803 A/B (one required for critical task; must be done prior to E-0 exit) (critical task) (may have been performed earlier) **
- Verify feedwater isolation complete, and verifies containment spray and Phase B
- Checks main steam isolation status and AFW status
- Checks excess letdown, and turns on aux building vent charcoal filter preheater
- Verifies proper operation of Aux Bldg and Control Rm vent systems; verifies containment iodine fans secured
- Verifies DGs running normally; verifies vital batteries supplied by chargers
- Verifies MSRs reset, and throttles RCP seal injection flows to normal ATC Checks RCS temperature - throttles AFW to minimum needed for heat sink ATC Checks Pzr safeties and PORVs - closed ATC Checks RCP trip criteria - stops all RCPs ATC/BOP Checks for faulted and ruptured S/Gs ATC Observes that containment is not normal; places 2nd CCW HX in service, transitions to E-1 ALL Implements CSFSTs
- Critical Task L091 NRC Sim Exam 05 Rev 1.doc Page 8 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 5 Event No.: 7 Page 8 of 9 Event
Description:
Seismic Event, and DBA LOCA (TCOA to align to CL recirc w/I 10 min) (CT) (cont)
Time Position Applicants Actions or Behavior SRO Performs procedure transition brief for EOP E-1 ALL Performs E-1 checks until 33% is reached in RWST:
- Checks RCPs tripped
- Checks for faulted/ruptured S/Gs
- Maintains S/G levels
- Checks PORVs available
- Verifies containment spray in service
- Checks ECCS termination criteria
- Maintains RHR pumps running, and aligns cooling
- Secures unloaded DGs
- Verifies recirc capability, checks aux bldg rad levels
- Determines that post LOCA cooldown procedure is not appropriate (stays in E-1)
ALL Observes 33% in RWST; RHR pumps are verified OFF (per E-1 step or FOP); this is time 0 for TCOA to complete transition to cold leg recirc in 10 minutes.
Record time: _______________
SRO Crew transitions to EOP E-1.3; aligns for CL Recirc (all BOLD substeps part of CT), per the following steps (critical task and TCOA; end point on next page) **
BOP App EE assigned/performed:
- All (6) series contactor switches are cut in
- Resets SI and both trains of CI Phase A and Phase B
- Verifies two ASW/CCW HXs in service
- Dispatches operators to rack in breakers for 8980 and 8976.
ATC Verifies RHR Pp 1-2 stopped and closes 8700B ATC Verifies RHR Pp 1-1 stopped and closes 8700A ATC Closes RHR crosstie valves 8716 A/B ATC Isolates ECCS Pp recirc paths by closing 8974 A/B, and closing 8105 / 8106 ATC Verifies recirc sump level > 92 ft ATC Opens recirc suction valve 8982B, and then starts RHR Pp 1-2 (verifies flows, amps)
ATC Opens crosstie 8804B, and verifies SI Pps running and RHR Pp amps w/i limits
- Critical Task L091 NRC Sim Exam 05 Rev 1.doc Page 9 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 5 Event No.: 7 Page 9 of 9 Event
Description:
Seismic Event, and DBA LOCA (TCOA to align to CL recirc w/I 10 min) (CT) (cont)
Time Position Applicants Actions or Behavior ATC Opens crossties 8807 A/B, and verifies both ECCS CCPs running ATC Opens recirc suction valve 8982A, and then starts RHR Pp 1-1 (verifies flows, amps)
ATC Opens crosstie 8804A (TCOA completion time ___________), and verifies SI Pps running and RHR Pp amps w/i limits (TCOA total time must be < 10 minutes) (CT) **
ATC Observes that both RHR trains are now in cold leg recirc lineup ATC Closes normal ECCS pump suction valves: 8805 A/B, 8976, and 8980 Terminate the scenario any time after valve 8804A has been opened (completion of CT and TCOA to be on CL Recirc)
- Critical Task L091 NRC Sim Exam 05 Rev 1.doc Page 10 of 16 Rev 1
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES
- 1. The unit is ramped down @ 10 mw/min due to RCP 1-2 high vibrations. OP AP-25 is used for the rapid load reduction.
- 2. S/G 1-1 feed flow transmitter FT-511 fails low; DFWCS remains in automatic; the crew takes actions per OP AP-5 for the channel failure.
- 3. Turbine impulse pressure transmitter PT-505 fails low. This causes control rods to drive in and other system perturbations. OP AP-5 and Tech Specs are used to respond to the failure. (TS)
- 4. Pzr level transmitter LT-461 fails low. The crew responds per OP AP-5 to transfer the backup channel to an operable channel, and return normal letdown to service. (TS)
- 5. The crew places normal letdown back in service.
- 6. The 2nd feed flow transmitter (FT-510) fails low on the 1-1 S/G, resulting in the FWRV and the bypass valve failing to manual. The crew will respond by maintaining 1-1 S/G level in manual, and respond to the transmitter failure using OP AP-5.
- 7. A seismic event causes a DBA LOCA on the unit. The crew will proceed through the EOPs until the RWST reaches 33%, when transfer to cold leg recirculation will be performed (CT, and a TCOA to swap to recirc within 10 minutes of reaching 33% in the RWST).
- 8. On the safety injection, charging injection valves 8803 A/B must be manually opened (auto failure) (CT).
The scenario is terminated once the transfer to cold leg recirculation is completed (including the CT and TCOA).
L091 NRC Sim Exam 05 Rev 1.doc Page 11 of 16 Rev 1
ATTACHMENT 1 - SIMULATOR SETUP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator IC-510 100% power, Mol, CB = 774 per Checklist
- Integrators: BA - 00, and PW - 20
- Tags: None Setup Drill 81 Reset normal engineering values Setup Drill 79 Limit NI response during LBLOCA Setup Boards - CC1 Place Htr Grp 1-4 in ON CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary.
Primary integrator = 20 gal, Boron = 00 gal.
Record PPC MAX (BOL = 100.1, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP C B near 774 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o Trend TAVG, ALM/MODE-1, Trend CHARGING, Sim Large on big screen o RONCONFIG is updated.
o PENs running.
o R2BCONFIG blowdown flows at 90 gpm.
o Operational mode correct for current conditions. 1 o Delta-I target slope matches Delta-I curve (DELTAICONFIG)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
Run the clear recorders program to clear digital charts All printer are on, with adequate paper/ink/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
1 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, go to APMC. Follow menu to manually override to correct mode.
L091 NRC Sim Exam 05 Rev 1.doc Page 12 of 16 Rev 1
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X Once crew has DRILL 6905 in AUTO Scenario malfunctions are inputted once the crew taken the watch takes the watch X 0 min, per SM Control Boards Crew ramps unit down @ 10 mw/min X For turnover, and Cue: Use vibration summary on 2nd page of crew turnover to give readings any any time RCP time crew comes over to get update from vibration monitor (use same vibrations response if engineering called about any changes). (Note: vibration data checked for all other RCPs is AS-SEEN on monitor.)
Once ramp is in xmt mfw70 3,-152,30,1800,d,0 FT-511 (1-1 S/G feed flow transmitter) fails low (set progress, per up for coming event) lead examiner Once FT-511 xmt tur2 2,0,0,1800,c, PT-505 (turbine 1st stage pressure) fails low (TS) failure completed, fqm511(1).lt.100,0 per lead examiner Once PT-505 xmt pzr42 2,0,0,1800,c, LT-461 (Pzr level transmitter, selected for backup failure completed, pxmt1(1).lt.10,0 ctrl) fails low (causes letdown isolation) per lead examiner Once letdown is xmt mfw69 3,-152,30,1800,c, FT-511 (2nd feed flow transmitter on 1-1 S/G) fails low service, per lead lqm461.lt.10,0 (causes loop 1 DFWCS to fail to manual) examiner Once 1-1 S/G mal sei1 act, 0.25,5,0,c, DBA LBLOCA on loop 3, preceded by an earthquake level is stabilized fqm510(1).lt.100,0 in manual, per mal rcs1 act 3,1,1800,c, lead examiner jmlsei1,0 On trip/SI vlv sis1 2,0,0,0,d,xv2i243o 8803 A/B fail to open on trip/SI (manual available) vlv sis2 2,0,0,0,d,xv2i244o X After Rx Trip PA DRILL 32 in AUTO NO Action on reactor trip st X When requested DRILL 92 in MANUAL (do 1 Racks out breakers for valves 8980 and 8976 (from two actions ONLY) EOP E-1.3)
L091 NRC Sim Exam 05 Rev 1.doc Page 13 of 16 Rev 1
DRILL FILE TEXT
- NRC L091 Exam Scenario 5
- jfb1, 04/26/11
- init 510
- XMT MFW70 S/G 1-1 FEEDWATER FLOW #fqm511(1) xmt mfw70 3,-152,30,1800,d,0 #fqm511(1)
- XMT TUR2 TURB 1ST STAGE PRESS: PM-505F, PQM-505 #pxmtst1(1) xmt tur2 2,0,0,1800,c,fqm511(1).lt.100,0 #pxmtst1(1)
- XMT PZR42 PZR LEVEL #lqm461 xmt pzr42 2,0,0,1800,c,pxmtst1(1).lt.10,0 #lqm461
- XMT MFW69 S/G 1-1 FEEDWATER FLOW #fqm510(1) xmt mfw69 3,-152,30,1800,c,lqm461.lt.10,0 #fqm510(1)
- seismic mal sei1 act,0.25,5,0,c,fqm510(1).lt.100,0
- VLV SIS2 BORON INJ TK SUPPLY LINE VLV #rsi8803b vlv sis2 2,0,0,0,d,xv2i244o #rsi8803b L091 NRC Sim Exam 05 Rev 1.doc Page 14 of 16 Rev 1
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 134 Days Operating Mode: 1 Gross Generation: 1191 MWe Power Level: 100 % Net Generation: 1148 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): 307 SCF / 326 SCFD 5 day ave NEW EMERGENT WORK:
- None SHUTDOWN TECH SPECS / ECGS:
- None ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- None TURNOVER ITEMS:
- RCP 1-2 vibrations have been rising over the past week, and have reached the ALERT and DANGER levels on some readings in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, but are stable. Engineering has evaluated the pump condition. An ODM meeting was held, and the Shift Manager (SM) directs you to start a ramp to shut down the unit at 10 mw/min immediately following taking the watch. (current pump levels on 2nd page)
- H 2 delivery in progress PRIORITY ITEMS FOR NEXT SHIFT:
- Ramp the plant down, and shut down the unit (to secure RCP 1-2)
OPERABILITY ITEMS:
- None ANNUNCIATORS IN ALARM:
- None L091 NRC Sim Exam 05 Rev 1.doc Page 15 of 16 Rev 1
Shift Foreman Turnover TURNOVER ITEMS:
- U maintain 100% - no one in containment
- U-2 is at 100%
REACTIVITY MANAGEMENT:
- Time in core life: MOL.
- Power History: Steady State, previously at 100% for 123 days. Currently power is at 100%
- Boron concentration is 774 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 231 steps on CBD.
- Diluting the RCS approximately 20 gallons every 2 hrs.
- The last dilution was completed 5 min ago.
- Ramp Plan: Start a ramp immediately after taking the watch to shut down the plant, at 10 mw/min.
Use the intermediate ramp rate guidance from the reactivity handbook, and monitor/adjust as needed.
- Rod motion: as needed to maintain I on target during the ramp / shut down.
CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
- None OTHER ABNORMAL PLANT STATUS
- See Plant Abnormal Status Board RCP 1-2 VIBRATION MONITORING INFORMATION:
- RPM - 1182 and stable
- Motor Shaft (x) - gradual rise over last week to 12-14 mils (ALERT), and oscillating, but stable
- Motor Shaft (y) - gradual rise over last week to 11-13 mils (ALERT), and oscillating, but stable
- Pump Shaft (x) - gradual rise over last week to 20-21 mils (DANGER), and oscillating, but stable
- Pump Shaft (y) - gradual rise over last week to 18-21 mils (ALERT/DANGER), and oscillating, but stable
- Velocity (x) - gradual rise over last week to 0.25-0.28 in (ALERT), and oscillating, but stable
- Velocity (y) - gradual rise over last week to 0.25-0.28 in (ALERT), and oscillating, but stable
- Graphs over the last week: all show gradual rise until reading stabilized approx 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago, and all readings have some oscillations, but are not rising.
L091 NRC Sim Exam 05 Rev 1.doc Page 16 of 16 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: 6 Op-Test No.: L091-NRC Examiners: Operators:
Initial Conditions: 100% Reactor power, MOL, Boron at 774 ppm Turnover: H 2 delivery in progress, RHR pp 1-2 cleared Event Malf Event Event No No. Type* Description 1 ser 0255 C (ARO) Diesel 1-1 day tank low level. (TS) 2 dsc rhr25 C (ALL), RHR pp 1-1 UC fuse blows. Estimate 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to repair, Tech Spec 3.0.3 R (ALL) shut down is required. SM cues to ramp. (TS) 3 cnh cvc8 I (ALL) PCV-135 L/D HX outlet controller fails to 0% demand (I) - must place excess letdown in service ***
4 ovr xc1s C (SRO, Rods outward rod motion (auto and manual); manual reactor trip ATC) 5 mal ppl5a/b C (ALL) ATWS (open 13D & E, trip successful, stays in EOP E-0) (CT) 6 mal rcs4d M (ALL) SGTR on S/G 1-4 (400 gpm) 5 min after reactor trip (CT on isolation, and on cooldown) (completion of RCS depressurization and SI termination at NRC discretion, as they contain (2) additional CTs) 7 8
9 10
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 1. Total malfunctions (5-8) 6
- 2. Malfunctions after EOP entry (1-2) 2
- 3. Abnormal events (2-4) 3
- 4. Major transients (1-2) 2
- 5. EOPs entered/requiring substantive actions (1-2) 1
- 6. EOP contingencies requiring substantive actions (0-2) 0
- 7. Critical tasks (2-3) 3
- placing excess letdown in service similar to audit item, but different cause/path L091 NRC Sim Exam 06 Rev 1.doc Page 1 of 17 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 6 Event No.: 1 Page 1 of 9 Event
Description:
Diesel 11 day tank low level. (TS)
Time Position Applicants Actions or Behavior SRO/ATC Notes PK16-07 (input 255) on DG 1-1 day tank level hi/lo SRO/BOP Dispatches nuclear operator to check DG and DG annunciator status Cue: (using time compression) (after C/R requests status of local alarm and DG status) PK DG11-3-4 is in (low day tank level); 1-1 DG day tank level is 6 and dropping slowly.
Cue: (using time compression) (after C/R requests to follow up on alarm and investigate) The F/O transfer pump is running, and the LCV is open, but the tank is not filling. There is a few drops per minute leak on the day tank. The WCL has arrived on station, and is helping work through the rest of the annunciator response.
Note: (see Vol 9b, figure CMD 1E-21.2b) 6 corresponds to about 238 gallons in the day tank, which is below the 250 gal minimum TS level.
Note: Due to the possible safety hazard, the crew may opt to place the fuel oil LCVs in manual close and/or place the DG in manual to prevent starting (all for safety reasons).
SRO Implements Tech Specs associated with the low day tank level:
- TS 3.8.1.B (one DG INOPERABLE) (1 hr) (partial STP I-1c, power supply check)
SRO My direct IFOs to investigate and evaluate fuel leak/spill (hazmat)
SRO (if time permits) C/R may direct local operators to use OP J-6C:V to attempt to fill the day tank using the portable pump (they may chose not to attempt, due to leak)
L091 NRC Sim Exam 06 Rev 1.doc Page 2 of 17 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 6 Event No.: 2 Page 2 of 9 Event
Description:
RHR pp 11 UC fuse blows. Estimate 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to repair, SM cues to ramp. (TS)
Time Position Applicants Actions or Behavior SRO/ATC Notes PK17-18 (input 219), 4kV Bus-G Bkr DC Cont UV Or Trouble ATC/BOP Crew determines that RHR Pp 1-1 has DC control power problem, diagnosed from loss of ctrl pwr light on board walkdown SRO/BOP Local operators (may also send maintenance) sent to investigate details at the RHR Pp 1-1 breaker Cue: (using time compression) The UC fuses are blown on the 1-1 RHR Pp, and there is a slight burnt smell in and near the breaker cubicle. Maintenance estimates the RTS at about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SRO Declares the 1-1 RHR Pp INOPERABLE (TS)
- TS 3.0.3 (act within 1 hr to ramp to Mode 3)
Cue: (once SFM determines that S/D is required) The SM directs that U-1 ramp the unit immediately to shut down the unit. Plan to separate the unit in about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> from now. (this will require a ramp rate > 5 mw/min, and get the ramp started more quickly, using OP AP-25 vs OP L-4)
SRO Contacts maintenance to investigate failure L091 NRC Sim Exam 06 Rev 1.doc Page 3 of 17 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 6 Event No.: 2 Page 3 of 9 Event
Description:
Ramp down to shut down the unit (TS shut down)
Time Position Applicants Actions or Behavior SRO Enters OP AP-25, Rapid Load Reduction BOP Ramp is started (may do brief before/during ramp):
- Load target is entered into DEH
- Sets ramp rate ( 5 - 10 mw/min)
- Pushes GO ATC Verifies that control rods are inserting properly in AUTO ATC Verifies ON all pressurizer backup heaters ATC Maintains charging flow adequate to prevent letdown flashing BOP Verifies DFWCS in AUTO and controlling S/G levels ATC RCS is borated per reactivity handbook SRO SFM provides reactivity oversight BOP MFP suction is verified adequate ATC Verifies proper operation of steam dumps ATC Checks pressurizer pressure and level trending to program L091 NRC Sim Exam 06 Rev 1.doc Page 4 of 17 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 6 Event No.: 3 Page 4 of 9 Event
Description:
PCV-135 Ltdn HX outlet pressure controller fails to 0% demand Time Position Applicants Actions or Behavior ALL PK04-21 alarms, with input showing that the letdown relief has lifted (below actions from ARP PK04-21; OP AP-18 may also be entered directly, and has similar actions)
ALL Letdown parameters (no flow, high pressure, PCV-135 demand at zero) are used to diagnose that PCV-135 has gone closed, and that the letdown relief is open BOP Manual control of PCV-135 may be attempted (demand wont go above zero)
BOP Letdown is isolated (orifice valve closed; may close LCV-459 and LCV-460) to stop the letdown relief from continuously lifting SRO It is determined that normal letdown cannot be established SRO Maintenance is contacted to investigate the PCV-135 failure ATC Charging flow is controlled to limit pressurizer level rise from reference SRO Decision is made to place excess letdown in service SRO/BOP Ramp may be stopped for initial response/diagnostics; ramp is resumed, if stopped L091 NRC Sim Exam 06 Rev 1.doc Page 5 of 17 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 6 Event No.: 3 Page 5 of 9 Event
Description:
Places excess letdown in service (event 3 cont)
Time Position Applicants Actions or Behavior SRO OP B-1A:IV is used to place excess letdown in service; a brief is held SRO/BOP Radiation Protection is notified to change/check posting requirements for placing excess letdown in service SRO Determines that excess letdown line does not need flushing (recent boron sample shows that excess letdown was in service recently)
Cue: (from Shift Manager) Flushing of the excess letdown line is NOT required.
BOP Opens FCV-361 (CCW cooling)
BOP Verifies HCV-123 is closed BOP Opens 8166 and 8167, excess letdown isolation valves BOP Slowly opens HCV-123 to establish excess letdown flow BOP Monitors containment sumps for leakage (from HX)
ATC Reduce charging to minimum (RCP seals) and use HCV-123 to control Pzr Level L091 NRC Sim Exam 06 Rev 1.doc Page 6 of 17 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 6 Event No.: 4 Page 6 of 9 Event
Description:
Rods outward rod motion (auto and manual) Manual reactor trip Time Position Applicants Actions or Behavior ATC Notes control rods moving out in automatic ATC Determines that Tave-Tref mismatch and turbine/reactor power mismatch do not warrant automatic rod motion ATC Takes control rods to manual; observes that rods are still moving outward SRO May implement OP AP-12A for continuous withdrawal or insertion of control rods SRO/ATC Initiates manual reactor trip L091 NRC Sim Exam 06 Rev 1.doc Page 7 of 17 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 6 Event No.: 5 Page 7 of 9 Event
Description:
ATWS (open 13D & E opened) (CT)
Time Position Applicants Actions or Behavior SRO Crew enters EOP E-0 ALL Immediate actions are performed:
- Verify reactor trip, notes reactor is NOT tripped
- Notes that manual trip already attempted (or may re-try manual reactor trip @ either location)
- Observes that reactor is still critical
- Opens breakers for busses 13D and 13E to de-energize the rod drive MGs; observes that the reactor trips (WOG CT FR-S.1-C), prior to completing FR-S.1 immediate actions (note: FR-S.1 should not be entered) (critical task) **
- Re-closes breakers 13D and 13E once the reactor is tripped
- Dispatches local operator to open reactor trip breakers
- Performs turbine trip
- Checks AFW status, and exits E-0 for E-0.1
- Performs E-0.1 tailboard and E-0.1 actions until SGTR symptoms are noted (lowering Pzr level/press, secondary rad monitor readings and alarms; may use FOP or AP-3 criteria for safety injection)
- Crew re-verifies E-0 immediate actions BOP App E is implemented:
- Announce trip/SI on PA system; checks main generator - tripped
- Verify Phase A and containment vent isolation complete
- Verify feedwater isolation complete, and verifies containment spray and Phase B
- Checks main steam isolation status and AFW status
- Checks excess letdown isolated (closes 8166 & 8167), and turns on aux bldg vent charcoal filter preheater
- Verifies proper operation of Aux Bldg and Control Rm vent systems; verifies containment iodine fans secured
- Verifies (2) DGs running normally; verifies vital batteries supplied by chargers
- Critical Task L091 NRC Sim Exam 06 Rev 1.doc Page 8 of 17 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 6 Event No.: 6 Page 8 of 9 Event
Description:
SGTR on S/G 1-4 (400 gpm) 5 min after reactor trip (CT)
Time Position Applicants Actions or Behavior ATC Checks RCS temperature - throttles AFW to minimum needed for heat sink ATC Checks Pzr safeties and PORVs - closed ATC Checks RCP trip criteria ATC/BOP Checks for faulted S/Gs ATC/BOP Diagnoses 1-4 SGTR (at normal E-0 diagnostics, or when levels are checked later in E-0)
SRO Transition to EOP E-3 is made (from E-0 diags, or E-0 S/G level checks, after diags)
ATC Checks RCP trip criteria BOP Identifies S/G 1-4 as the ruptured S/G (unexpected level rise, sampling, etc)
BOP Isolates S/G 1-4 using App FF (before transition to ECA-3.1 occurs) (WOG CT E-3-A)
(critical task, all below that is BOLD) **
- Sets 1-4 S/G 10% steam dump to 1040 psig, 8.67 turns, and checks valve closed
- Closes 1-4 S/G MSIV and bypass valve
- Verifies SGBD OC closed, and sample isolation closed on 1-4 S/G (sample valve may be open for sampling)
- Verifies S/G 1-4 isolation complete
- Notifies SFM of S/G isolation completion
- Removes WR Thot input from SCMM on PAM3
- Establishes sample lineup for S/G activity samples (or verifies if done earlier)
ATC/BOP Isolates AFW flow to 1-4 S/G (once > 15% NR level)
BOP Check Ruptured S/G pressure greater than 225 psig.
SRO Determines cooldown target temperature BOP Determines Condenser is available ALL Depressurizes RCS to < P-11 (if required; can be done in conjunction with cooldown), and blocks low steamline pressure SI signal ATC Performs RCS cooldown at maximum rate (without getting main steamline isolation; not critical); cooldown is done so that MAGENTA PATH avoided on RCS Integrity, and RCS subcooled margin still exists following cooldown (accomplished by reaching target temperature) (WOG CT E-3-B) (critical task) **
BOP Maintains AFW flow to intact S/Gs.
SRO/BOP Stops cooldown and stabilizes at target temperature (or slightly below)
- Critical Task L091 NRC Sim Exam 06 Rev 1.doc Page 9 of 17 Rev 1
Appendix D (rev 9) Required Operator Actions Form ES-D-1 Op-Test No.: L091-NRC Scenario No.: 6 Event No.: 6 Page 9 of 9 Event
Description:
SGTR on S/G 1-4 (400 gpm) 5 min after reactor trip (cont)
Time Position Applicants Actions or Behavior ATC Checks Pzr PORVs closed and block valves open with power.
ATC/BOP Resets SI, and Phase A; opens FCV-584 BOP Checks ruptured S/G pressure stable or increasing ATC Checks subcooling adequate Note: Continuing the scenario to complete the SGTR response would add (2) additional critical tasks (depressurizing the RCS, and SI termination), and is subject to NRC proposal/ approval if these subsequent steps are done).
Terminate scenario once the cooldown is completed, and temperature stabilized, unless the NRC wants to proceed with the below steps.
ALL Depressurizes RCS to refill Pressurizer (WOG CT E-3-C, must be done prior to water release from S/G) (critical task) **
- Uses normal spray at maximum rate (both sprays full open); note: may shift to one Pzr PORV if spray determined to be ineffective
- Sprays until one of the 3 criteria are satisfied
- Pzr level > 74%, OR,
- SCM < 20 F ATC Checks for rising RCS pressure ALL Checks for ECCS termination criteria, and terminates ECCS flows (WOG CT E-3-D, done so that primary and secondary inventory are stable prior to E-3 exit) (critical task): **
- Observes termination criteria are met
- Stops both SI Pps
- Verifies CCP 1-3 stopped
- Resets vital 4KV auto transfer relays
- Secures charging injection lineup
- Aligns normal charging, and controls to maintain level Terminate scenario once normal charging has been placed in service.
L091 NRC Sim Exam 06 Rev 1.doc Page 10 of 17 Rev 1
MAJOR EVENT
SUMMARY
AND SCENARIO OBJECTIVES
- 1. DG 1-1 day tank low level alarm (TS). The crew will investigate per the appropriate ARPs, and apply Tech Specs.
- 2. RHR Pp 1-1 blow its UC fuses (TS). The crew will diagnose this via an alarm and board indications, declare the pump INOPERABLE (after investigation), and apply Tech Spec 3.0.3 to start a shut down of the unit. A ramp is started to shut down the unit.
- 3. PCV-135 demand fails low, causing a loss of letdown flow, and letdown to divert through the letdown relief to the PRT. The crew will diagnose the failure, and place excess letdown in service.
- 4. Later in the ramp, unwarranted outward rod motion will occur. Manual control will be attempted, but outward motion will continue, prompting a manual reactor trip.
- 5. When the manual reactor trip is attempted, it fails (ATWS). Opening 13D and 13E in EOP E-0 is successful (CT) in tripping the reactor (no entry to FR-S.1), and E-0 is continued.
- 6. A 400 gpm SGTR occurs on the 1-4 S/G 5 minutes after the reactor trip (probably during EOP E-0.1 actions). The crew will get an SI (may initiate a manual SI), return to EOP E-0, and identify the SGTR. The crew will then isolate the leak (CT), and cooldown the RCS (depressurize to refill the Pzr, and terminate ECCS flow are optional and at NRC discretion, and are also CTs).
The scenario is terminated once the cooldown is completed and temperature stabilized in E-3 (unless the NRC desires to see the depressurization/SI termination steps).
L091 NRC Sim Exam 06 Rev 1.doc Page 11 of 17 Rev 1
ATTACHMENT 1 - SIMULATOR SETUP TIME LINE CONSOLE ENTRY SYMPTOMS/CUES/DESCRIPTION Setup Simulator IC-510 100% power, Mol, CB = 774 per Checklist
- Integrators: BA - 00, and PW - 20
- Tags: RHR Pp 1-2 Setup Drill 81 Reset normal engineering values Setup ser 0298 0 Takes RHR Pp 1-2 OOS dsc rhr24 act,0,0,0,d,0 Control Boards - CC1 Place Htr Grp 1-4 in ON Setup Plant Abnormal Status Board Update previous Excess Letdown boron to 827 ppm (and date to 3 weeks ago)
CONTROL BOARD SETUP Copies of commonly used forms and procedures are available.
Any tags are placed/removed as necessary. RHR Pp 1-2 Primary integrator = 20 gal, Boron = 00 gal.
Record PPC MAX (BOL = 100.1, MOL = 100.0, EOL = 100.2) on CC2 lamicoid The plant Abnormal Status Board is updated with last CCP C B near 774 and current date.
Circuit breaker flags are correct.
Equipment status lamicoids are correct:
B.A. XFER PP SUPPLYING BLENDER - BA Pp 1-2 SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - Cont. Rm. Vent Train 1 Bus F SELECTED TO BUS 1H - Cont. Rm. Vent Train 1 Bus H The proper Delta-I curve and Reactivity Handbook for the simulator INIT are in place The Rod Step Counters indicate correctly.
PPC Setup:
o Trend TAVG, ALM/MODE-1, Trend CHARGING, Sim Large on big screen o RONCONFIG is updated.
o PENs running.
o R2BCONFIG blowdown flows at 90 gpm.
o Operational mode correct for current conditions. 1 o Delta-I target slope matches Delta-I curve (DELTAICONFIG)
SPDS (screens and time updating), A screen RM, B screen SPDS.
The chart recorders are operating properly, and advanced.
Run the clear recorders program to clear digital charts All printer are on, with adequate paper/ink/etc., and are in the ON LINE status.
The Annunciator Horn is on (BELL ON).
Sound Effects are on (SOUND ON).
The video and audio systems are SECURED.
1 Allow about ten minutes for the PPC to automatically update the plant mode. If still not correct, go to APMC. Follow menu to manually override to correct mode.
L091 NRC Sim Exam 06 Rev 1.doc Page 12 of 17 Rev 1
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X 0 min, prior to DRILL 6906 in AUTO Scenario malfunctions are inputted once the crew turnover takes the watch 1 min after crew ser 0255 act,1,0,60,d,0 DG 1-1 day tank low level alarm takes the watch X Cue: (using time compression) (after C/R requests status of local alarm and DG status) PK DG11-3-4 is in (low day tank level); 1-1 DG day tank level is 6 and dropping slowly.
X Cue: (using time compression) (after C/R requests to follow up on alarm and investigate) The F/O transfer pump is running, and the LCV is open, but the tank is not filling. There is a few drops per minute leak on the day tank. The WCL has arrived on station, and is helping work through the rest of the annunciator response.
X Note: (see Vol 9b, figure CMD 1E-21.2b) 6 corresponds to about 238 gallons in the day tank, which is below the 250 gal minimum TS level.
Once Tech Specs dsc rhr25 act,0,0,1800,d,0 RHR Pp 1-1 UC fuses blow (cause PK16-18 to completed on DG alarm) above, per lead examiner X Cue: (using time compression) The UC fuses are blown on the 1-1 RHR Pp, and there is a slight burnt smell in and near the breaker cubicle. Maintenance estimates the RTS at about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
X Cue: (once SFM determines that S/D is required) The SM directs that U-1 ramp the unit immediately to shut down the unit. Plan to separate the unit in about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> from now. (this will require a ramp rate > 5 mw/min, and get the ramp started more quickly, using OP AP-25 vs OP L-4)
Info only Control Boards Crew starts ramp down to take unit off line per TS 3.5.2.B Once ramp in cnh cvc8 2,0,0,1800,c,ggo,0 PCV-135 (ltdn pressure control valve) fails to zero progress, per demand (manual and auto); normal letdown no lead examiner longer available X Cue: (from Shift Manager, when excess letdown procedure gets to decision point on flush of lines)
Flushing of the excess letdown line is NOT required.
X Once excess ltdn DRILL 6909 in AUTO (does Unwarranted control rod outward motion in AUTO; is in service, per below actions) motion continues in Manual (requires Rx trip) lead examiner ovr xc1i085e act,0,0,9,c, (conditional on 8167 open) xv2o223r,0 (auto inhibited) ovr xc1i085f act,1,0,9,c, xv2o223r,0 (manual ensured) ovr xc1i086c act,0,0,9,c, xv2o223r,0 (in inhibited) ovr xc1i200o act,1,0,9,c, xv2o223r,0 (out signal ON)
When Rx Trip mal ppl5a act 3,0,0,d,0 ATWS (manual trip switches dont work, but opening attempted mal ppl5b act 3,0,0,d,0 bkrs 13D and 13E result in the reactor tripping)
(installed 0 min)
(continued on next page)
L091 NRC Sim Exam 06 Rev 1.doc Page 13 of 17 Rev 1
TIMELINE AND INSTRUCTOR ACTIONS FOR SIMULATION TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X When requested mal ppl5a clr (wait 60 sec) Simulates opening U-1 RTBs locally to open the U-1 mal ppl5a clr (wait 60 sec)
RTBs X Cue: Once U-1 RTBs have been opened, report that to the Control Room.
X After Rx Trip PA DRILL 32 in AUTO NO Action on reactor trip 5 min after mal rcs4D act 400,1,300,c, 400 gpm SGTR on the 1-4 S/G reactor trip fnispr.lt.5,0 X When requested DRILL 17 in AUTO Opens SGBD sample valves locally to sample S/Gs (if lineup made)
L091 NRC Sim Exam 06 Rev 1.doc Page 14 of 17 Rev 1
DRILL FILE TEXT
- NRC L091 Exam Scenario 6 (6906)
- jfb1 04/26/11
- init 510
- DG 1-1 day tank low level (input 255) ser 0255 act,1,0,60,d,0 #ALM301C
- PCV-135 controller fails low (auto and manual)(conditional is "go" on ramp) cnh cvc8 2,0,0,1800,c,ggo,0 #xcnh135a
- Outward rod motion (Auto and Manual) - USE DRILL 6909
- ATWS (13D and E will trip, remain in E-0) mal ppl5a act 3,0,0,d,0 mal ppl5b act 3,0,0,d,0
- 400 gpm SGTR 5 minutes after trip mal rcs4D act 400,1,300,c,fnispr.lt.5,0
- NRC L091 Exam Scenario 06 (outward rod motion) (6909)
- jfb1, 04/26/11
- Outward rod motion (Auto and Manual) (if cleared or adjusted, ensure these occur all at once,
- or in order if possible)(conditional is 8167 "open" light) ovr xc1i085e act,0,0,9,c,xv2o223r,0 #CC1056A (inhibits AUTO position on rods) ovr xc1i085f act,1,0,9,c,xv2o223r,0 #CC1056F (ensures MAN on rod selector) ovr xc1i086c act,0,0,9,c,xv2o223r,0 #CC1054A (ensures no rods in signal) ovr xc1i200o act,1,0,9,c,xv2o223r,0 #CC1055A (ensures rods out signal)
L091 NRC Sim Exam 06 Rev 1.doc Page 15 of 17 Rev 1
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 193 Days Operating Mode: 1 Gross Generation: 1191 MWe Power Level: 100 % Net Generation: 1148 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): 307 SCF / 326 SCFD 5 day ave NEW EMERGENT WORK:
- RHR Pp 1-2 SHUTDOWN TECH SPECS / ECGS:
- 3.5.2.A, RHR Pp 1-2 ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- None TURNOVER ITEMS:
- RHR Pp 1-2 seized during an STP run last shift; the pump is cleared, and the current estimate on RTS is 48 hrs (OOS for 3 hrs)
PRIORITY ITEMS FOR NEXT SHIFT:
- Maintain 100% power OPERABILITY ITEMS:
- 3.5.2.A, RHR Pp 1-2 ANNUNCIATORS IN ALARM:
- No unexpected alarms L091 NRC Sim Exam 06 Rev 1.doc Page 16 of 17 Rev 1
Shift Foreman Turnover TURNOVER ITEMS:
- U maintain 100% - no one in containment
- U-2 is at 100%
REACTIVITY MANAGEMENT:
- Time in core life: MOL.
- Power History: Steady State, previously at 100% for 88 days. Currently power at 100%
- Boron concentration is 774 ppm from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 231 steps on CBD.
- Diluting the RCS approximately 20 gallons every 2 hrs.
- The last dilution was completed 5 min ago.
- Rod motion: none planned, as needed to maintain I on target CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
- None OTHER ABNORMAL PLANT STATUS
- See Plant Abnormal Status Board L091 NRC Sim Exam 06 Rev 1.doc Page 17 of 17 Rev 1