ML091810090
| ML091810090 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/2009 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| ES-301, ES-301-2 | |
| Download: ML091810090 (250) | |
Text
ES-301 Control Room/In Plant Systems Outline Form ES-301-2 Facility: BFN (NRC EXAM) Date of Examination: 12/0BIOB Exam Level (circle one): RO I $R.O-II SRO-U Operating Test Number: HLT0707 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
Safety System I JPM Title Type Code* JPM Number Function A. SLC Injection - Faulted 1 fails to isolate AMELS 1 606F-U2 (2-EOI App-3A) (211 000K4.02) (SIM A)
~~tlflI,~y~Lifl~up.~~ondS.jF'fl,"-Fault~d":'HPHtrs**
- 'isoliated(EQI./S.;p;$A) .(295Q31EA1~.QQ)(SII'III.B)
C. Re-open MSIVs following Gp 1 Isolation (EOI App-8B) (223002K4.03) (SIM C)
DELS 3 35-U2 D. Loss of Shutdown Cooling - Faulted - desired pump fails to start (AOI-74-1) (RO Only) (295021AA1.02) ADELS 4 201 F-U2 SIM 0
- r;.i. . J~AP0per.<ationt6*Drywen '. .
- .~~IAp.-14B) .. *.22.~Q01A4.04} *SIM.E)
F~*'**llfietj!<3.tO*4kV. S!'D .*.bdi\~t9-23-**lfaqlted -Low~ Qil
...... res~;$Rr~.* ~.~ ... 1(3Aor A (2E)~OQ.OA4.0t*;$II'IIIF G. RBCCW Pump Discharge Hdr Low Press alarm -
Faulted 4B fails to close (ARP~4C Win 12)
(226001A4.12) (SIM G)
~Ht{Rr1rlJarY:~QqtaIqm.entV~j[\tiqQth[:u.~4-j* 9 __ .faq}te~"*-J . *. . i****. 'i rele~s~tates hi h{EOIApp~12) (~9$02~EA1;0~)'(SIM H>>
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
I. Start RCIC from outside Control Room (3-AOI-100-2 (217000A4.03) (IN-PLANT A)
J.*. Byp~~.s~Glqltiigf;t**:Wat~rLe\l~I*~.h~t~Ovvr;tir;tt~rlock
. 2:'E:QIA~j6H ******2.170QOA4.0S;{iN:.PLANIS .
K. Place 4kv SID bd 250v Battery Charger liS -
Faulted - voltage unstable (0-01-570) ANL 6 115F-U2 (263000K1.02) (IN-PLANT C)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO I SRO-II SRO-U (A)lternate Path 4-6 I 4-6 I 2-3 (C)ontrol Room (D)irect from bank ::;;9 I ::;B I ::;4 (E)mergency or abnormal in-plant 2::1 I 2::1 I 2::1 (EN)gineered Safety Feature I I 2:: 1 (control room system)
(L)ow-Power I Shutdown 2::1 I 2::1 I 2::1 (N)ew or (M)odified from bank including 1(A) 2::2 I 2::2 I 2::1 (P)revious 2 exams ::;3 I ::;3 I ::;2 (randomly selected)
(R)CA 2::1 I 2::1 I 2::1 Simulator
JPM NO. 606F REV. NO.5 PAGE 1 of 11 JPM NUMBER: 606F TITLE: EOI APPENDIX-3A - SLC INJECTION TASK NUMBER: U-OOO-EM-73 SUBMITTED BY: DATE: _ _ __
VALIDATED BY: DATE: _ _ __
APPROVED BY: DATE: _ _ __
TRAINING PLANTCONCURRENCE: _ _ _ _ _ _ _ _ _ __ DATE: _ _ _ __
OPERATIONS
- Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence
JPM NO. 606F REV. NO.5 PAGE 2 of 11 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 05/12/01 All Initial issue 1 10/22/98 All Re-formatled 2 10103/00 All General revision 3 09/13/02 All Modified failure mode for NRC 4 07/08/06 All General revision 5 06/12/08 All General revision & re-format
JPM NO. 606F REV. NO.5 PAGE 3 of 11 OPERATOR: _______________________________________________
JPM NUMBER: 606F TASK NUMBER: U-OOO-EM-73 TASK TITLE: EOI APPENDIX-3A - SLC INJECTION KIA NUMBER: 211000A4.02 KIA RATING: RO 4.2 SRO 4.2 TASK STANDARD: PERFORM OPERATION NECESSARY TO START AN SLC PUMP AND INJECT SLC SOLUTION INTO THE RPV AS DIRECTED BY 2-EOI APPENDIX-3A PERFORMANCE LOCATION: SIMULATOR X PLANT __ CONTROL ROOM __
REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-3A, Rev 5 VALIDATION TIME: SIMULATOR:_......;:5:..:..;:O=-=O'---_ LOCAL: _ _ __
MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)
PERFORMANCE TIME:
COMMENTS:
l ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ __
JPM NO. 606F REV. NO.5 PAGE 4 of 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an operator on Unit 2. The reactor has scrammed and control rods failed to insert. 2-EOI-1 has been entered and followed to RC/Q-12.
Reactor power is >5% and suppression pool temperature is 105°F and rising.
INITIATING CUES: The Unit Supervisor has directed you to inject SLC per 2-EOI Appendix-3A, SLClnjection.
JPM NO. 606F REV. NO.5 PAGE 5 of 11 START TIME _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.
STANDARD:
Obtained copy of 2-EOI Appendix-3A.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 1. UNLOCK and PLACE 2-HS-63-6A, SLC PUMP 2A/2B, control switch in START-A or START-B position.
STANDARD:
Unlocked and Placed SLC pump control switch in either START-A or START-B position.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 606F REV. NO.5 PAGE 6 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 2. CHECK SLC System for injection by observing the following:
- Selected pump starts, as indicated by red light illuminated above pump control switch.
- Squib valves fire, as indicated by SQUI8 VALVE A and 8 CONTINUITY blue lights extinguished,
- SLC SQUI8 VALVE CONTINUITY LOST Annunciator in alarm on Panel 9-5 (2-XA-55-58, Window 20).
- SLC INJECTION FLOW TO REACTOR Annunciator in alarm on Panel 9-5 (2-XA-55-58, Window 14).
(
STANDARD:
Verified selected SLC pump is injecting to RPV by Observing the above parameters.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 606F REV. NO.5 PAGE 7 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 3. IF ..... Proper system operation CANNOT be verified, THEN ... RETURN to Step 1 and START other SLC pump.
STANDARD:
N/A - verified proper operation of running pump and continues to step 4.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 4. VERIFY RWCU isolation by observing the following:
- RWCU Pumps 2A and 2B tripped
- 2-FCV-69-12, RWCU RETURN ISOLATION VALVE closed STANDARD:
Examinee Recognized the failure of 2-FCV-69-1 to isolate and manually Closes 2-FCV-69-1 by taking 2-HS-69-1 to the close direction on panel 9-4. Verified illuminated Green valve position indicating lights above the (other) respective valve handswitches and Verified RWCU pumps tripped by Observing illuminated Green breaker position indicating lights above pump handswitches. (Only closing 69-1 is Critical)
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 606F REV. NO.5 PAGE 8 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 5. VERIFY ADS inhibited.
STANDARD:
Verified 2-XS-1-159A and 2-XS-1-161A, Panel 2-9-3, in the INHIBIT position and Verified Alarm Panel 2-XA-55-3C, Window 18, "ADS LOGIC BUS A INHIBITED and 2-XA-55-3C, Window 31, "ADS LOGIC BUS B INHIBITED", in alarm.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 6. MONITOR reactor power for downward trend.
STANDARD:
Monitored all available APRMs/IRMs for downward reactor power trend.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 606F REV. NO.5 PAGE 9 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 7. MONITOR 2-Ll-63-1A, SLC STORAGE TANK LEVEL, and CHECK that level is dropping approximately 1% per minute.
STANDARD:
Observed 2-Ll-63-1A and Verified SLC storage tank level decreasing.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 606F REV. NO.5 PAGE 10 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:
PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:
PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
END OF TASK STOP TIME: _ _ _ _ _ __
PAGE 11 of 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an operator on Unit 2. The reactor has scrammed and control rods failed to insert. 2-EOI-1 has been entered and followed to RC/Q-12.
Reactor power is >5% and suppression pool temperature is 105°F and rising.
INITIATING CUES: The Unit Supervisor has directed you to inject SLC per 2-EOI Appendix-3A, SLC Injection.
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EOI PROGRAM ~AL SECTION IX 2-EOI APPENDIX-3A SLC INJECTION REVISION 5 PREPARED BY: M. Morrow PHONE: 3708 RESPONSIBLE ORGANIZATION: Operations APPROVED BY: A. S. Bhatnagar EFFECTIVE DATE: 10/26/00 LEVEL OF USE: REFERENCE USE VALIDATION DATE: 02/14/92 QUALITY-RELATED
HISTORY OF REVISION/REVIEW 2-EOI APPENDIX-3A REV.
NO. DATE: REVISED PAGES REASON FOR CURRENT REVISION o 6/15/92 ALL New procedure. Necessary to support implementation of Revision 4 EPGs into BFNP EOIs.
1 7/10/92 1 Incorporate Writer's Guide discrepancies, typos, and plant nomenclature discrepancies.
2 4/21/93 ALL Converted from WordPerfect 5.1 to Pagemaker 4.0 to better support desktop publishing capabilities.
References to Control Room Labels corrected.
1 Action verb "VERIFY" replaced with "CHECK" at Steps 2 and 7 for correct word usage.
3 12/28/93 1 Correct label discrepancies for pump control switch positions.
4 8/24/94 1 Corrected bullets and checkoff lines for step 2.
5 10/26/00 All Converted to MS-Word.
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2-EOI APPENOIX-3A Rev. 5 Page 1 of 2 2-EOI APPENDIX-3A SLC INJECTION LOCATION: Unit 2 Control Room ATTACHMENTS: None
- 1. UNLOCK and PLACE 2-HS-63-6A, SLC PUMP 2A/2B, control switch in START-A or START-B position.
- 2. CHECK SLC System for injection by observing the following:
- Selected pump starts, as indicated by red light illuminated above pump control switch.
- SLC SQUIB VALVE CONTINUITY LOST Annunciator in alarm on Panel 9-5 (2-XA-55-5B, Window 20) .
- SLC INJECTION FLOW TO REACTOR Annunciator in alarm on Panel 9-5 (2-XA-55-5B, Window 14) .
- 3. IF ..... Proper system operation CANNOT be verified, THEN ... RETURN to Step 1 and START other SLC pump.
- 4. VERIFY RWCU isolation by observing the following:
- RWCU Pumps 2A and 2B tripped
- 2-FCV-69-1, RWCU INBO SUCT ISOLATION VALVE closed
- 2-FCV-69-2, RWCU OUTBO SUCT ISOLATION VALVE closed
- 2-FCV-69-12, RWCU RETURN ISOLATION VALVE closed.
2-EOI APPENDIX-3A Rev. 5 Pa e 2 of 2
- 5. VERIFY ADS inhibited.
- 6. MONITOR reactor power for downward trend.
- 7. MONITOR 2-LI-63-1A, SLC STORAGE TANK LEVEL, and CHECK that level is dropping approximately 1% per minute.
- 8. WHEN . .. EITHER of the following exists:
- SLC tank level drops to 0, O~
- 9. NOTIFY Chemistry to mix additional solution to compensate for dilution as directed by the SRO.
- 10. WHEN ... Directed by the SRO to perform system flush, THEN ... REFER to 01-63, Section 8.1, for system flush.
LAST PAGE
JPM NO. 14F REV. NO.5 PAGE 1 of 17 JPM NUMBER: 14F TITLE: 2-EOI APPENDIX-5A - INJECTION SYSTEMS LlNEUP-CONDENSATE/FEEDWATER, HP HTRs ISOLATED.
TASK NUMBER: U-OOO-EM-29 SUBMITTED BY: DATE: _ _ __
APPROVED BY: DATE: _ _ __
TRAINING PLANTCONCURRENCE: _ _ _ _ _ _ _ _ _ __ DATE: _ _ _ __
OPERATIONS
- Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence
JPM NO. 14F REV. NO.5 PAGE 2 of 17 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 10/23/98 All Initial issue 1 10/23/01 3,4 Procedure revision, format, setpoint change 2 08/14/03 All Procedure revision, editorial, add setup cue 3 08/24/06 3 Procedure revision 4 06/01/07 All General revision 5 06/12/08 All General revision & re-format
JPM NO. 14F REV. NO.5 PAGE 3 of 17 OPERATOR: _______________________________________________
JPM NUMBER: 14F TASK NUMBER: U-000-EM-29 TASK TITLE: 2-EOI APPENDIX-5A - INJECTION SYSTEMS LlNEUP-CONDENSATE/FEEDWATER, HP HTRs ISOLATED.
KIA NUMBER: 295031 EA 1.08 KIA RATING: RO 3.8 SRO 3.9 TASK STANDARD: PERFORM CONTROL ROOM ACTIONS REQUIRED TO ESTABLISH THE CONDENSATE/FEEDWATER SYSTEM AS AN RPV INJECTION SYSTEM lAW 2-EOI APPENDIX-5A PERFORMANCE LOCATION: SIMULATOR X PLANT - - CONTROL ROOM __
REFERENCES/PROCEDU RES NEEDED: 2-EOI Appendix-5A, Rev 8 VALIDATION TIME: SIMULATOR: ___1.:.....;1~:0:....:::.0_ LOCAL: ________
MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)
PERFORMANCE TIME:
COMMENTS:
ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _____________________ DATE: _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 4 of 17 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit 2 Operator. The reactor has scrammed due to a trip of all Reactor Feedwater pumps and EOI-1 has been followed through RC/L-3.
INITIATING CUES: The problem that caused the trip of the RFP's has been corrected and the Unit Supervisor has directed you to restore and maintain RPV water level +2" to +51" as directed by 2-EOI Appendix-5A, INJECTION SYSTEMS LINEUP -
CONDENSATE/FEEDWATER.
(
JPM NO. 14F REV. NO.5 PAGE 5 of 17 START TIME _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.
STANDARD:
Obtained copy of 2-EOI Appendix-5A.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 1. VERIFY Condensate System in service, supplying suction to RFPs.
STANDARD:
Verified condensate system in service by observation of valve alignment, condensate and condensate booster pump operation and RFP alignment.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 6 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
STANDARD:
Verified MSIVs open by illuminated RED valve position indicating lamps on Panel 2-9-3 (vertical panel or benchboard).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 3. VERIFY Hotwell Pressure below -7 in. Hg.
STANDARD:
Verified Hotwell Pressure below -7 inches Hg. as indicated on 2-XR-2-2, Panel 2-9-6 or ICS computer.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 7 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
STANDARD:
Verified illuminated RED valve position indicating lamps above 2-HS-1-121, (129), or (137) on Panel 2-9-6 is lit for RFPT 2A, B, and C and take actions to close valve(s).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
( PERFORMANCE STEP: CRITICAL NOT CRITICAL x
STANDARD:
Verified illuminated RED valve position indicating lamp above 2-HS-1-125, (133), or (141).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 8 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 6. DEPRESS 2-HS-46-8A(9A)(10A), RFPT 2A(2B)(2C) SPEED CONT RAISE/LOWER, and VERIFY amber light is illuminated ..
STANDARD:
Depressed 2-HS-46-8A, (9A), or(10A) for selected RFPT Speed Cont Raise/Lower and Verified amber light illuminated.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 7. VERIFY a Main Oil Pump is running for RFPT to be started.
STANDARD:
Verified a Main Oil Pump is running for the selected RFPT by observing a RED indicating light above handswitch.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 9 of 17
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PERFORMANCE STEP: CRITICAL NOT CRITICAL x B. VERIFY for EACH of the following push buttons, the green light is illuminated and the red light is extinguished:
- 2-HS-3-20BA, RX WTR LVL CH A HI RFPT/MT TRIP RESET
- 2-HS-3-20B8, RX WTR LVL CH 8 HI RFPT/MT TRIP RESET STANDARD:
Verified GREEN light illuminated and RED light extinguished on 2-HS-3-20BA & 20B8.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 9. VERIFY OPEN the following valves:
Recognizes HP heater inlet and outlet valves closed and Opens a minimum of one set of the HP Heater FW Isolation Valves (inlet and outlet, 3-3B & 3-75, or 3-31 & 3-76, or 3-24 & 3-77).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 10 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 10. DEPRESS 2-HS-3-124A(150A)(175A), RFPT 2A(2B)(2C) TRIP RESET, and CHECK the following:
- Blue light extinguished.
- HP Stop Valve OPEN as indicated by red light above the following, as applicable:
o 2-HS-3-108, RFPT 2A HP STOP VLV TEST o 2-HS-3-134, RFPT 2B HP STOP VLV TEST o 2-HS-3-159, RFPT 2C HP STOP VLV TEST
- LP Stop Valve OPEN as indicated by red light above the following, as applicable:
o 2-HS-3-107, RFPT 2A LP STOP VLV TEST o 2-HS-3-133, RFPT 2B LP STOP VLV TEST o 2-HS-3-158, RFPT 2C LP STOP VLV TEST STANDARD:
(
Depressed TRIP RESET PB 3-124A, (150A), or (175A) for the selected pump, and Checked the BLUE light extinguished, HP Stop Valve Open as indicated by RED light above HS for the selected pump, and the LP Stop Valve Open as indicated by the RED light above HS for the selected pump.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 11 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 11. VERIFY OPEN 2-FCV-3-20(13)(6), RFP 2A(2B)(2C) MIN FLOW VALVE.
STANDARD:
Verified illuminated RED valve position indicating light for minimum flow valve 3-20, (13), or (6)above HS for selected pump.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 12. PLACE 2-HS-46-112A(138A)(163A), RFPT 2A(2B)(2C) START/LOCAL ENABLE, in START.
STANDARD:
Placed Start/Local Enable switch for the selected pump 46-112A, (138A), or (163A) in START.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 12 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 13. CHECK RFPT 2A(2S)(2C) speed increases to approximately 600 rpm.
STANDARD:
Checked RFPT Speed accelerated to approximately 600 rpm.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 14. VERIFY OPEN 2-FCV-3-19(12)(5), RFP 2A(2S)(2C) DISCHARGE VALVE.
STANDARD:
Verified illuminated RED valve position indicating light above discharge valve for the selected pump, 3-19, (12), or (5).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 13 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 15. RAISE RFPT 2A(2B)(2C) speed UNTIL RFP discharge pressure is approximately equal to RPV pressure using ANY of the following methods on Panel 2-9-5:
- Using individuaI2-HS-46-8A(9A)(10A), RFPT 2A(2B)(2C) SPEED CONT .
RAISE/LOWER switch in MANUAL GOVERNOR, OR
- Using 2-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 2-SIC-46-8(9)(1 0), RFPT 2A(2B)(2C) SPEED CONTROL PDS in AUTO STANDARD:
Raised selected RFPT speed Until RFP discharge pressure was approximately equal to RPV pressure utilizing one of the methods above on Panel 2-9-5.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 14of17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 16. SLOWLY RAISE speed of RFPT UNTIL RFW flow to the RPV is indicated using ANY of the following methods on Panel 2-9-5:
- Using individual 2-HS-46-8A(9A)(10A), RFPT 2A(2B)(2C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR
- Using 2-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 2-SIC-46-8(9)(1 0), RFPT 2A(2B)(2C) SPEED CONTROL PDS in AUTO STANDARD:
Slowly raised speed of selected RFPT Until RFW flow to the RPV is indicated utilizing one of the above methods.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 15 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 17. ADJUST RFPT speed as necessary to control injection using ANY of the following methods on Panel 2-9-5:
- Using individuaI2-HS-46-8A(9A)(10A), RFPT 2A(2B)(2C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR
- Using 2-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 2-SIC-46-8(9)(1 0), RFPT 2A(2B)(2C) SPEED CONTROL PDS in AUTO STANDARD:
(
Adjusted speed of selected RFPT as required utilizing one of the above methods.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 14F REV. NO.5 PAGE 16 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:
PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:
PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS:. _ _ _ _ __
END OF TASK STOP TIME: _ _ _ _ _ __
PAGE 17 of 17 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit 2 Operator. The reactor has scrammed due to a trip of all Reactor Feedwater pumps and EOI-1 has been followed through RC/L-3.
INITIATING CUES: The problem that caused the trip of the RFP's has been corrected and the Unit Supervisor has directed you to restore and maintain RPV water level +2" to +51" as directed by 2-EOI Appendix-5A, INJECTION SYSTEMS LINEUP -
CONDENSATE/FEEDWATER.
(
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EOI PROGRAM MANUAL SECTION IX 2-EOI APPENDIX-SA INJECTION SYSTEMS LINEUP CONDENSATE/FEEWATER REVISION 8 PREPARED BY: M. Morrow PHONE: 3708 RESPONSIBLE ORGANIZATION: Operations APPROVED BY: JEFF LEWIS EFFECTIVE DATE: 03/09/03 LEVEL OF USE: REFERENCE USE EOI VALIDATION DATE: 02/14/92 QUALITY-RELATED
HISTORY OF REVISION/REVIEW 2-EOI APPENDIX-SA REV.
NO. DATE: REVISED PAGES REASON FOR CURRENT REVISION o 6/15/92 ALL New procedure. Necessary to support implementation of Revision 4 EPGs into BFNP EOIs.
1 7/10/92 ALL Incorporate Writer's Guide discrepancies, typos, and plant nomenclature discrepancies.
2 4/21/93 ALL Converted from WordPerfect 5.1 to Pagemaker 4.0 to better support desktop publishing capabilities.
2 References to Control Room Labels corrected.
Phrase "maintain RPV level" replaced with "control injection" to address cases of usage with C4 flowchart.
1,2 Incorporated Changes as result of NRC comments:
1
- Added step for placing MGU in manual.
3 08/03/95 1 Revised Step 9 to require verification that all RX WTR LVL HI RFPT TRIP RESET amber lights are extinguished.
4 10/26/95 2 Corrected nomenclature for stop valves in Step 11.
5 ALL Digital Feedwater Control: DCNs W25841A, W25842A, W25843A,added new controllers.
6 10/26/00 All Converted to MS-Word.
HISTORY OF REVISION/REVIEW 2-EOI APPENDIX-SA REV.
NO. DATE: REVISED PAGES REASON FOR CURRENT REVISION 7 04/07/02 2 Step 12 - Corrected UNID of HS-46-112.
8 03/09/03 1 Step 6 - Corrected UNID of HS-46-8A.
2-EOI APPENDIX-5A Rev. B
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .page
. 1 of 4 2-EOI APPENDIX-SA INJECTION SYSTEMS LINEUP CONDENSATE/FEEWATER LOCATION: Unit 2 Control Room ATTACHMENTS: None
- 1. VERIFY Condensate System in service, supplying suction to RFPs.
- 3. VERIFY Hotwell Pressure below -7 in. Hg.
- 6. DEPRESS 2-HS-46-BA(9A) (lOA), RFPT 2A(2B) (2C) SPEED CONT RAISE/LOWER, and VERIFY amber light is illuminated.
- 7. VERIFY a Main Oil Pump is running for RFPT to be started.
B. VERIFY for EACH of the following pushbuttons, the green light is illuminated and the red light is extinguished:
- 2-HS-3-20BA, RX WTR LVL CH A HI RFPT/MT TRIP RESET
- 2-HS-3-20BB, RX WTR LVL CH B HI RFPT/MT TRIP RESET.
2-EOI APPENDIX-5A Rev. 8 Paqe 2 of 4
- 9. VERIFY OPEN the following valves:
- 10. DEPRESS 2-HS-3-124A(150A) (175A) , RFPT 2A(2B) (2C) TRIP RESET, and CHECK the following:
- Blue light extinguished.
- HP Stop Valve OPEN as indicated by red light above the following, as applicable:
0 2-HS-3-108, RFPT 2A HP STOP VLV TEST 0 2-HS-3-134, RFPT 2B HP STOP VLV TEST 0 2-HS-3-159, RFPT 2C HP STOP VLV TEST.
- LP Stop Valve OPEN as indicated by red light above the following, as applicable:
o 2-HS-3-107, RFPT 2A LP STOP VLV TEST o 2-HS-3-133, RFPT 2B LP STOP VLV TEST o 2-HS-3-158, RFPT 2C LP STOP VLV TEST.
- 11. VERIFY OPEN 2-FCV-3-20 (13) (6), RFP 2A(2B) (2C) MIN FLOW VALVE.
- 12. PLACE 2-HS-46-112A(138A) (163A), RFPT 2A(2B) (2C)
START/LOCAL ENABLE, in START.
- 13. CHECK RFPT 2A(2B) (2C) speed increases to approximately 600 rpm.
- 14. VERIFY OPEN 2-FCV-3-19 (12) (5), RFP 2A(2B) (2C) DISCHARGE VALVE.
2-EOI APPENDIX-SA Rev. 8 Pa e 3 of 4 lS. RAISE RFPT 2A (2B) (2C) speed UNTIL RFP discharge pressure is approximately equal to RPV pressure using ANY of the following methods on Panel 2-9-S:
- Using individual 2-HS-46-8A(9A) (lOA), RFPT 2A(2B) (2C)
SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR
- Using individual 2-SIC-46-8 (9) (10), RFPT 2A(2B) (2C)
SPEED CONTROL PDS in MANUAL, OR
- Using 2-LIC-46-S, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 2-SIC-46-8(9) (10), RFPT 2A(2B) (2C) SPEED CONTROL PDS in AUTO.
- 16. SLOWLY RAISE speed of RFPT UNTIL RFW flow to the RPV is indicated using ANY of the following methods on Panel 2-9-S:
- Using individual 2-HS-46-8A(9A) (lOA), RFPT 2A(2B) (2C)
SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR
- Using individual 2-SIC-46-8 (9) (10), RFPT 2A(2B) (2C)
SPEED CONTROL PDS in MANUAL, OR
- Using 2-LIC-46-S, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 2-SIC-46-8(9) (10), RFPT 2A(2B) (2C) SPEED CONTROL PDS in AUTO.
2-EOI APPENDIX-SA Rev. 8 Paqe 4 of 4
- 17. ADJUST RFPT speed as necessary to control injection using ANY of the following methods on Panel 2-9-S:
- Using individual 2-HS-46-8A(9A) (lOA), RFPT 2A(2B) (2C)
SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR
- Using individual 2-SIC-46-8 (9) (10), RFPT 2A(2B) (2C)
SPEED CONTROL PDS in MANUAL, OR
- Using 2-LIC-46-S, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 2-SIC-46-8 (9) (10), RFPT 2A(2B) (2C) SPEED CONTROL PDS in AUTO.
- 18. WHEN ... RPV level is approximately equal to desired level AND automatic level control is desired, THEN ... PLACE 2-LIC-46-S, REACTOR WATER LEVEL CONTROL PDS, in AUTO with individual 2-SIC-46-8(9) (10), RFPT 2A(2B) (2C) SPEED CONTROL PDS in AUTO.
LAST PAGE
JPM NO. 35 REV. NO. 10 PAGE 1 of 12 JPM NUMBER: 35 TITLE: 2-EOI APPENDIX 8B - REOPENING MSIVs FOLLOWING GROUP I ISOLATION TASK NUMBER: U-000-EM-46 SUBMITTED BY: DATE: _ _ __
VALIDATED BY: DATE: _ _ __
APPROVED BY: DATE: _ _ __
TRAINING PLANT CONCURRENCE: _ _ _ _ _ _ _ _ _ __ DATE: _ _ __
OPERATIONS
- Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence
JPM NO. 35 REV. NO. 10 PAGE 2 of 12 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 5 10/23/96 4,12 Changed critical step to non-critical on STAAR 6 08/07/97 All Format, added 3-way comm.
7 09/22/00 All General revision 8 09/29/05 5 Changed critical step, added verify 9 07/21/07 All General revision 10 06/14/08 All General revision & re-format
JPM NO. 35 REV. NO. 10 PAGE 3 of 12 OPERATOR: _______________________________________________
JPM NUMBER: 35 TASK NUMBER: U-000-EM-46 TASK TITLE: 2-EOI APPENDIX 8B - REOPENING MSIVs FOLLOWING GROUP I ISOLATION KIA NUMBER: 223002A4.03 KIA RATING: RO 3.6 SRO 3.5 TASK STANDARD: PERFORM THE CORRECT EQUIPMENT MANIPULATIONS REQUIRED TO EQUALIZE AROUND THE MSIVs AND REOPEN THE MSIVs PER 2-EOI APPENDIX-8B PERFORMANCE LOCATION: SIMULATOR X PLANT __ CONTROL ROOM __
REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-8B, Rev 4 VALIDATION TIME: SIMULATOR: 25:00 LOCAL: _ _ __
MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)
PERFORMANCE TIME:
COMMENTS:
ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ DATE: ___________
JPM NO. 35 REV. NO. 10 PAGE 4 of 12 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit 2 Operator. Unit 2 reactor has scrammed and isolated. HPCI is in service for RPV pressure control, "B" SJAE, and "A" OFF GAS PREHEATER are in service from AUX BOILER steam. Venting Primary containment per APP 12. EOI-1 and EOI-2 have been entered and conditions allow the MSIVs to be reopened to establish the main condenser as a heat sink.
INITIATING CUES: The Unit Supervisor directs you to reopen the MSIVs as directed by 2-EOI-Appendix 8B.
JPM NO. 35 REV. NO. 10 PAGE 5 of 12 START TIME ....,....-_ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.
STANDARD:
Obtained copy of 2-EOI-Appendix-8B.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 1. VERIFY ALL MSIV control switches in CLOSE position.
STANDARD:
Verified all eight MSIVs hand switches in the CLOSE position.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 35 REV. NO. 10 PAGE 6 of 12
(
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
STANDARD:
Placed both PCIS reset switches on Panel 9-4 to the left and right position and Verified that four RED light above the reset switches were illuminated.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 2-HS-3-125, RFPT 2A TRIP
(
- 2-HS-3-151, RFPT 2B TRIP
- 2-HS-3-176, RFPT 2C TRIP STANDARD:
Depressed 2-HS-3-125, 151, 176.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 35 REV. NO. 10 PAGE 7 of 12 NOTE: To prevent auto opening of 2-FCV-1-58, handswitch 2-HS-1-58A must be held in the CLOSE position until main turbine speed decreases to below 1700 RPM.
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 4. VERIFY CLOSED the following drain valves(Panel 9-3):
- 2-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER
- 2-FCV-1-59, DOWNSTREAM MSL DRAIN TO CONDENSER STANDARD:
Verified illuminated GREEN valve position indicating lights above 2-HS-1-59 [NOT CRITICAL]. Placed 2-HS-1-58 in the CLOSE position [CRITICAL] and Verified illuminated GREEN valve position indicating lamp above associated control switch [NOT CRITICAL].
SAT UNSAT N/A _ _ COMMENTS:*_ _ _ _ _ __
JPM NO. 35 REV. NO. 10 PAGE 8 of 12
(
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 2-FCV-1-15, MSIV LINE A OUTBOARD
- 2-FCV-1-27, MSIV LINE B OUTBOARD
- 2-FCV-1-38, MSIV LINE C OUTBOARD
- 2-FCV-1-52, MSIV LINE D OUTBOARD STANDARD:
Placed 2-HS-1-15, 27, 38 and 52 in the OPEN position (Critical) and Verified illuminated RED valve position indicating lamps above the associated control switches (Not Critical).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
STANDARD:
Depressed 2-HS-1-16 and/or Verified illuminated. VERIFIED SETPOINT as indicated on 2-PI-47-162 indicates greater than reactor pressure.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
JPM NO. 35 REV. NO. 10 PAGE 9 of 12 PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 7. OPEN the following drain valves (Panel 9-3):
- 2-FCV-1-57, MSIV DOWNSTREAM DRAINS SHUTOFF STANDARD:
Placed 2-HS-1-55 and 2-HS-1-56 in the OPEN position (Critical) and Verified illuminated RED valve position indicating lamps above the associated control switches (Not Critical). Verified illuminated RED valve position indicating lamp above 2-HS-1-57 (Not Critical).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
CAUTION Opening MSIVs when differential pressure is above 50 psid may result in piping system damage.
JPM NO. 35 REV. NO. 10 PAGE 10 of 12
(
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- 8. WHEN .. . Main steam pressure is within 50 psig of RPV pressure, THEN .. . OPEN the following inboard MSIVs (Panel 9-3):
- 2-FCV-1-14, MSIV LINE A INBOARD
- 2-FCV-1-26, MSIV LINE B INBOARD
- 2-FCV-1-37, MSIV LINE C INBOARD
- 2-FCV-1-51, MSIV LINE D INBOARD STANDARD:
( When main steam pressure as indicated by 2-PI-47-99 on Panel 9-7 is within 50 psig of reactor pressure, Placed HS-1-14, 26, 37 and 51 in the AUTO/OPEN position (Critical) and Verified RED valve position indicating lamps above associated hand switches (Non Critical).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 35 REV. NO. 10 PAGE 11 of 12 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:
PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:
PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
END OF TASK STOP TIME: _ _ _ _ _ __
PAGE 12 of 12 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit 2 Operator. Unit 2 reactor has scrammed and isolated. HPCI is in service for RPV pressure control, "B" SJAE, and "A" OFF GAS PREHEATER are in service from AUX BOILER steam. Venting Primary containment per APP 12. EOI-1 and EOI-2 have been entered and conditions allow the MSIVs to be reopened to establish the main condenser as a heat sink.
INITIATING CUES: The Unit Supervisor directs you to reopen the MSIVs as directed by 2-EOI-Appendix 8B.
(
(
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EOI PROGRAM MANUAL SECTION IX 2-EOI APPENDIX-8B REOPENING MSIVs FOLLOWING GROUP 1 ISOLATION REVISION 4 PREPARED BY: M. Morrow PHONE: 3708 RESPONSIBLE ORGANIZATION: Operations APPROVED BY: A. S. Bhatnagar EFFECTIVE DATE: 04/06/01 LEVEL OF USE: REFERENCE USE EOI VALIDATION DATE: 02/14/92 QUALITY-RELATED
(
HISTORY OF REVISION/REVIEW 2-EOI APPENDIX-8B REV.
NO. DATE: REVISED PAGES REASON FOR CURRENT REVISION o 6/15/92 ALL New procedure. Necessary to support implementation of Revision 4 EPGs into BFNP EOIs.
1 7/10/92 ALL Incorporate Writer's Guide discrepancies, typos, and plant nomenclature discrepancies.
2 4/21/93 ALL Converted from WordPerfect 5.1 to Pagemaker 4.0 to better support desktop publishing capabilities.
References to control room labels corrected.
Panel locations added.
Deleted requirement to reset RFPT trips.
1 Added note regarding the auto open feature of 2-FCV-1-58.
2 Added caution regarding opening MSIVs with >50 psig Dp.
( 3 10/26/00 All Converted to MS-Word.
4 04/06/01 2 Added the following new step 6, just before opening the equalizing steam path, as a result of the EHC upgrade of DCN 50479A: VERIFY EHC is in HEADER PRESSURE CONTROL with SET POINT set above reactor pressure.
2-EOI APPENDIX-8B Rev. 4
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .page 1 of 2 2-EOI APPENDIX-aB REOPENING MSIVs FOLLOWING GROUP 1 ISOLATION LOCATION: Unit 2 Control Room ATTACHMENTS: None
- 1. VERIFY ALL MSIV control switches in CLOSE position.
- 3. DEPRESS the following pushbuttons to trip RFPTs (Panel 9- 6) :
- 2-HS-3-125, RFPT 2A TRIP
- 2-HS-3-151, RFPT 2B TRIP
- 2-HS-3-176, RFPT 2C TRIP.
- 4. VERIFY CLOSED the following drain valves (Panel 9-3):
NOTE: To prevent auto opening of 2-FCV-1-58, handswitch 2-HS-1-58A must be held in the CLOSE position until main turbine speed decreases to below 1700 RPM.
- 2-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER
- 2-FCV-1-59, DOWNSTREAM MSL DRAIN TO CONDENSER.
- 2-FCV-1-15, MSIV LINE A OUTBOARD --
- 2-FCV-1-27, MSIV LINE B OUTBOARD --
- 2- FCV-1-3 8, MSIV LINE C OUTBOARD --
- 2-FCV-1-52, MSIV LINE D OUTBOARD. --
2-EOI APPENDIX-BB Rev. 4 Page 2 of 2
- 7. OPEN the following drain valves (Panel 9-3):
- 2-FCV-1-57, MSIV DOWNSTREAM DRAINS SHUTOFF.
CAUTION Opening MSIVs when differential pressure is above 50 psid may result in piping system damage.
B. WHEN ... Main steam pressure is within 50 psig of RPV pressure, THEN .. . OPEN the following inboard MSIVs (Panel 9-3):
- 2-FCV-1-14, MSIV LINE A INBOARD
- 2-FCV-1-26, MSIV LINE B INBOARD
- 2-FCV-1-37, MSIV LINE C INBOARD
- 2-FCV-1-51, MSIV LINE D INBOARD.
LAST PAGE
JPM NO. 201F REV. NO. 2 PAGE 1 of 24 JPM NUMBER: 201 F TITLE: LOSS OF SHUTDOWN COOLING TASK NUMBER: 0-74-AB-01 SUBMITTED BY: DATE: _ _ __
VALIDATED BY: DATE: _ _ __
APPROVED BY: DATE: _ _ __
TRAINING PLANTCONCURRENCE: _ _~_ _ _ _ _ __ DATE: _ _ __
OPERATIONS
- Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence
JPM NO.201F REV. NO. 2 PAGE 2 of 24 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 08/13/03 All Initial issue 1 03/28/06 All Procedure revision 2 06/29/08 All General revision & re-format
JPM NO. 201F REV. NO. 2 PAGE 3 of 24 OPERATOR: ________________________________________________
JPM NUMBER: 201 F TASK NUMBER: 0-74-AB-01 TASK TITLE: LOSS OF SHUTDOWN COOLING KIA NUMBER: 295021 AA 1.02 KIA RATING: RO 3.5 SRO 3.5 TASK STANDARD: SUCCESSFULLYRESTORE SHUTDOWN COOLING FOLLOWING LOSS DUE TO INADVERTENT RPS ACTUATION.
PERFORMANCE LOCATION: SIMULATOR X PLANT __ CONTROL ROOM __
REFERENCES/PROCEDURES NEEDED: 2-AOI-74-1, Rev 32 VALIDATION TIME: SIMULATOR: 25:00 LOCAL: _ _ __
MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)
PERFORMANCE TIME:
COMMENTS:
ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _____________ DATE: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 4 of 24 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit 2 operator. Unit 2 is in Mode 3 (Rx temp>
212°F) heading towards cold conditions for a refueling outage. RHR Loop II using 2B RHR Pump was in shutdown cooling and Unit 3 is carrying 1350 gpm RHRSW flow for "B" RHRSW Header. An inadvertent loss of 2B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 2B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 2B RPS. The Unit Supervisor has notified the Shift Manager of the problem.
INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 2B RHR pump in accordance with 2-AOI-74-1.
JPM NO. 201F REV. NO. 2 PAGE 5 of 24
( STARTTIME _ _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.
STANDARD:
Obtained copy of 2-AOI-74-1.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
CAUTIONS
- 1) Reactor vessel stratification may occur until Shutdown Cooling is restored or a reactor Recirculation Pump is placed in service.
- 2) Loss of Shutdown Cooling during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is most critical due to massive decay heat and limitations on the RHRSW Piping. If Shutdown Cooling is lost during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post reactor shutdown, priorities are required to be placed on the recovery of shutdown cooling in an expeditious manner [BFN PER 02-003140-000).
NOTE The following systems, if available, may be used as alternate methods of decay heat removal .Refer to the applicable Tec Spec Bases B 3.4.7, B 3.4.8, B 3.9.7, B 3.9.8 .
ADHR System- (0-01-72)
Fuel Pool Cooling System- (2-01-78)
RWCU System- (2-01-69)
Ambient losses with natural or forced circulation
(
JPM NO. 201F REV. NO. 2 PAGE 6 of 24
(
PERFORMANCE STEP: CRITICAL NOT CRITICAL x 4.2 Subsequent Actions
[1] IF any EOI entry condition is met, THEN ENTER the appropriate EOI(s). (Otherwise N/A)
STANDARD:
Determines no EOI entry conditions have been met and N/As step.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[2] NOTIFY the Shift Manager.
STANDARD:
N/A - given in the initial conditions.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 70f24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[3] IF Refueling is in progress, THEN NOTIFY the Refueling Floor SRO. (Otherwise N/A)
STANDARD:
N/A - Mode 3 given in initial conditions. Not required to notify Refueling Floor SRO.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[4] REVIEW EPIP-1, Emergency Plan Classification Logic, for entry conditions.
STANDARD:
N/A.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 8 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[5] IF Shutdown Cooling isolates on low RPV water level or high Drywell press (GROUP 2 ISOL) AND RPV water level needs restoring using LPCI, THEN (Otherwise N/A)
PERFORM the following before reaching -122 inches RPV water level:
[5.1] PERFORM .... .
[5.2] DEPRESS .... ..
[5.3] IF ................ .
STANDARD:
Determines water level does NOT need restoring, N/A's all section 4.2[5] and continues to step 4.2[6]
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 9 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[6] IF Primary Containment Integrity is required, THEN VERIFY RHR system discharge piping pressure is being maintained
>TRM 3.5.4 Limits. REFER TO 2-01-74. (Otherwise N/A)
STANDARD:
Determines Primary Containment IS required in Mode 3 and Verifies pressure is ~ 35 psig on 2-PI-74-65 for Loop II RHR. (2~01-74r137 P&L 3.1.1 or verifies pressure above mark on 2-PI-74-65).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
NOTES
- 1) With the Reactor in Cold Shutdown Condition (Mode 4 or Mode 5), reactor coolant stratification may be indicated by one of the following:
- Reactor pressure above 0 psig with any reactor coolant temperature indication reading at or below 212°F.
- Differential temperatures of 50°F or greater between either RX VESSEL BOTTOM HEAD (FLANGE DR LINE) 2-TE-56-29 (8) temperatures and RX VESSEL FW NOZZLE N4B END (N4B INBD)(N4B END)(N4D INBD) 2-TE 13(14)(15)(16) temperatures from the REACTOR VESSEL METAL TEMPERATURE recorder, 2-TR-56-4.
- With recirculation pumps and shutdown cooling out of service, a Feedwater sparger temperature of 200°F or greater on any RX VESSEL FW NOZZLE (N4B END (N4B INBD)(N4D END)(N4D INBD) 2-TE-56-13(14)(15)(16) temperatures from the REACTOR VESSEL METAL TEMPERATURE recorder, 2-TR-56-4.
- 2) [NERlC] For purposes of thermal stratification monitoring, the bottom head drain line is more representative as long as there is flow in the line. [GE SIL 251 and 4301
JPM NO. 201F REV. NO. 2 PAGE 10 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[7] PLOT heatup/cooldown rate as necessary.
REFER TO 2-SR-3.4.9.1 (1).
STANDARD:
Checks step off and continues to step 4.2[8]
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 11 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[8] DIRECT the STA to ESTIMATE the following times at least once per shift until a method of decay heat removal is restored:
[8.1] DETERMINE the time since shutdown.
[8.2] DETERMINE the current RPV heat-up rate from 2-SR-3.4.9.1 (1),
or, if reactor coolant stratification is suspected, USE Illustration 1.
IF additional information is required to determine the heat-up rates, THEN CONTACT Reactor Engineer.
[8.3] DETERMINE the reactor coolant temperature or use the last valid reactor coolant temperature available.
[8.4] ESTIMATE the time for reactor coolant temperature to reach 212°F, using data obtained in Steps 4.2[8.1] through 4.2[8.3].
[8.5] IF the Reactor Vessel head is removed and the cavity is flooded with the fuel pool gates installed, THEN (Otherwise N/A)
ESTIMATE the time for reactor coolant temperature to reach 125°F and 150°F using a plot of the actual heatup rate or Illustration 1.
STANDARD:
Directs STA to estimate the heat up rate and check for stratification at least once per shift.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 12 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[9] IF the loss of Shutdown Cooling is due to inadequate RHRSW flow, THEN START the standby RHRSW pump for the appropriate header.
REFER TO 0-01-23. (Otherwise N/A)
STANDARD:
N/As Step 4.2[9] since there is no loss of RHRSW.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
[10] IF the loss of Shutdown Cooling is due to Group 2 PCIS isolation, WHEN conditions which permit resetting Group 2 PCIS isolation are met, THEN (Otherwise N/A)
PERFORM the following:
[10.1] RESET Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 2-HS-64-16A-S32, and PCIS DIV II RESET, 2-HS-64-16A-S33, in reset.
STANDARD:
On Panel 2-9-4, Resets Group 2 isolation by momentarily PlaCing PCIS DIV I RESET, 2-HS-64-16A-S32, in reset and PCIS Div II RESET, 2-HS-64-16A-S33 to reset.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 13 of 24
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PERFORMANCE STEP: CRITICAL x NOT CRITICAL
[10.2] MOMENTARILY DEPRESS RHR SYS 1(11) SO CLG INBD INJECT ISOL RESET, 2-XS-74-126 and 2-XS-74-132. VERIFY 2-IL-74-126 and 2-IL-74-132 extinguished.
STANDARD:
Momentarily depresses RHR SYS II SO CLG INBD INJECT ISOL RESET, 2-XS-74-132 (Critical). Verify 2-IL-74-132 extinguished (Not critical). Depresses RHR SYS I SO CLG INBD INJECT ISOL RESET, 2-XS-74-126 (Not critical) and Verify 2-IL-74-126 extinguished (Not critical).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 14 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[11] IF the loss of Shutdown Cooling is due to Group 2 PCIS AND the isolation signal fails to reset or remain reset due to invalid and/or sporadic signals, THEN (Otherwise N/A)
PERFORM the following:
[11.1] VERIFy ... .
[11.2] OBTAIN .. .
[11.3] DEFEAT .. .
[11.4] IF ........... .
STANDARD:
N/As all Step 4.2[11], the PCIS signal should have reset above.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 15 of 24 PERFORMANCE STEP: CRITICAL x NOT CRITICAL
[12] IF the Group 2 PCIS Isolation has been reset, THEN RETURN the affected loop of RHR to Shutdown Cooling as follows.
[12.1] CLOSE RHR SYS 1(11) LPCI OUTBD INJECT VALVE, 2-FCV-74-52(66).
STANDARD:
Places 2-HS-74-66 in close until only GREEN valve position indicating lamp is illuminated.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
NOTE 2-POI-74-2 aligns the RHR system to prevent SOC isolations during modes 4 and 5 operations. For Step 4.2[12.2], it accomplishes this by opening RHR SYS 1(11) LPCI INBD INJECT VALVE, 2-FCV-74:'53(67) and opening its associated breaker. If an isolation is received the valve will NOT close because the breaker is open. Therefore, to restore Shutdown Cooling, it is NOT necessary to manipulate this already open valve.
JPM NO. 201F REV. NO. 2 PAGE 16 of 24 PERFORMANCE STEP: CRITICAL x NOT CRITICAL
[12.2] OPEN RHR SYS 1(11) LPCI INBD INJECT VALVE, 2-FCV-74-53(67)
(IF the valve is aligned per 2-POI-74-2 (valve open with its breaker open), THEN N/A this step).
STANDARD:
Opens 2-FCV-74-67 (Critical) and verifies only RED valve position indicating lamp illuminated (Not Critical).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[12.3] VERIFY RHR SYSTEM 1(11) MIN FLOW INHIBIT switch, 2-HS-74-148(149) in INHIBIT STANDARD:
Verifies 2-HS-74-149 is in INHIBIT.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 17of24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[12.4] VERIFY CLOSED RHR SYSTEM 1(11) MIN FLOW VALVE, 2-FCV-74-7(30).
STANDARD:
Verifies 2-FCV-74-30 is CLOSED.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[12.5] VERIFY CLOSED RHR PUMP 2A(2B) and 2C(2D) SUPPR POOL SUCT VLVs, 2-FCV-74-1(24) and 2-FCV- 74-12(35).
STANDARD:
Verifies 2-FCV-74-24 and 2-FCV-74-35 are CLOSED.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
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JPM NO. 201F REV. NO. 2 PAGE 18 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[12.6] VERIFY OPEN RHR PUMP 2A(2B) and 2C(2D) SO COOLING SUCT VLVs, 2-FCV-74-2(25) and 2-FCV-74-13(36).
STANDARD:
Verifies 2-FCV-74-25 and 2-FCV-74-36 are OPEN.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
NOTE 2-POI-74-2 aligns the RHR system to prevent SOC isolations during modes 4 and 5 operations. For Step 4.2[12.7], it accomplishes this by opening either RHR SHUTDOWN COOLING SUCT OUTBD VLV, 2-FCV-74-47 or INBD ISOLVLV, 2-FCV-74-48 and opening the associated breaker. If an isolation is received the valve will NOT close because the breaker is open. Therefore, to restore Shutdown Cooling, it is NOT necessary to manipulate this already open valve. The other valve will still have power and if closed, is required to be reopened.
JPM NO. 201F REV. NO. 2 PAGE 19 of 24 PERFORMANCE STEP: CRITICAL x NOT CRITICAL
[12.7] OPEN RHR SHUTDOWN COOLING SUCT OUTBD and INBD ISOL VLVs, 2-FCV-74-47 and 2-FCV-74-48 (If either valve is aligned per 2-POI-74-2 (valve open with its breaker open), this step will be N/A for that valve. The other valve will still need to be opened to restore a suction path).
STANDARD:
Places 2-HS-74-47 in Open (Critical) and Verified 2-FCV-74-47 only RED valve position indicating lamp is illuminated (Not Critical) and Verified 2-FCV-74-48 only RED valve position indicating lamp is illuminated (Not Critical) (2-POI-74-2 is not in effect since not currently in Mode 4 or 5).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
[12.8] RESTART tripped RHR pump(s) RHR PUMP 2A(2C)(2B)(2D) using 2-HS-74-5A(16A)(28A)(39A)
STANDARD:
Places 2-HS-74-28A (2B RHR Pump) in Start and Recognizes Failure to start.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 20 of 24
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PERFORMANCE STEP: CRITICAL NOT CRITICAL x Notify US of pump failure to start.
STANDARD:
Notifies US. (He/she should recommend starting 20 RHR pump)
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL Start 20 RHR pump.
STANDARD:
Places 2-HS-74-39A (20 RHR Pump) in Start (Critical) and Verifies only RED light illuminated above handswitch (Not Critical).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 21 of 24
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PERFORMANCE STEP: CRITICAL x NOT CRITICAL
[12.9] THROTTLE RHR SYS 1(11) LPCI OUTBD INJECTION VALVE, 2-FCV-74-52(66), to establish and maintain RHR flow as indicated by 2-FI-74-50(64), RHR SYS 1(11) FLOW, as follows:
RHR Pumps 1 2 in Operation Loop Flow 7,000 to 10,000 14,000 to 20,000 Loop Flow (1 or more fuel bundles removed from core) 6,000 to 6,500 N/A STANDARD:
Manipulates 2-HS-74-66 to obtain RHR System II Loop flow between 7,000 and 10,000 gpm on 2-FI-74-64.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 201F REV. NO. 2 PAGE 22 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[12.10] WHEN time permits after RHR pump is started, THEN VERIFY RHR Pump Breaker charging spring recharged by observing amber breaker spring charged light is on and closing spring target indicates charged.
STANDARD:
Dispatched personnel to Verify RHR Pump 2D breaker closing spring recharged and investigate 2B RHR pump failure.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
[12.11 ] SLOWLY THROTTLE RHR HX 2A(2C)(2B)(2D) RHRSW OUTLET VALVE, 2-FCV-23-34(40)(46)(52), to obtain desired cooldown rate.
STANDARD:
Using 2-HS-23-52A and co-ordinating with Unit 3, reduces D2 RHRSW pump cooling flow to -900 gpm as indicated on 2-FI-23-54 (while Unit 3 picks up minimum flow) and using 2-HS-23-46A raises B2 RHRSW pump dilution flow to -4000 gpm (while Unit 3 lowers their flow to 0 gpm) as indicated on 2-FI-23-48.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
(
JPM NO. 201F REV. NO. 2 PAGE 23 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:
PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:
PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
END OF TASK STOP TIME: _ _ _ _ _ __
PAGE 24 of 24 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit 2 operator. Unit 2 is in Mode 3 (Rx temp>
212°F) heading towards cold conditions for a refueling outage. RHR Loop II using 2B RHR Pump was in shutdown cooling and Unit 3 is carrying 1350 gpm RHRSW flow for "B" RHRSW Header. An inadvertent loss of 2B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 2B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 2B RPS. The Unit Supervisor has notified the Shift Manager of the problem.
INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 2B RHR pump in accordance with 2-AOI-74-1.
()
(~
.~.
Browns Ferry Nuclear Plant Unit 2 Abnormal Operating Instruction 2-AOI-74-1 Loss of Shutdown Cooling Revision 0032 Quality Related Level of Use: Continuous Use Effective Date: 10-21-2006 Responsible Organization: OPS, Operations Prepared By: Michael K Teggins Approved By: James A. McCrary
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Page 2 of 31 Current Revision Description Pages Affected: 13,14 Type of Change: ENHANCEMENT Tracking Number: 033 PCR 06003017 Added Steps 4.2[12.3] through 4.2[12.6] to verify positions for the minimum flow inhibit switch, minimum flow valve, suppression pool suction valves, and shutdown cooling suction valves to support restoration of an loop of RHR loop to the Shutdown Cooling mode.
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit2 Rev. 0032 Page 3 of 31 Table of Contents 1.0 PURPOSE .................................................................................................................... 4 2.0 SyMPTOMS ................................................................................................................. 4 3.0 AUTOMATIC ACTIONS ..............................................................................................l 5 4.0 OPERATOR ACTIONS ................................................................................................ 6 4.1 Immediate Actions ......................................................................... ,.............................. 6 4.2 Subsequent Actions ...................................................................................................... 6
5.0 REFERENCES
........................................................................................................... 21 5.1 Technical Specifications ............................................................................................. 21 5.2 Technical Requirements Manual-TRM ........................................................................ 22 5.3 Final Safety Analysis Report ....................................................................................... 22 5.4 Plant Instructions ........................................................................................................ 22 5.5 Plant Drawings ............................................................................................................ 23
(~ 5.6 Miscellaneous Documents .......................................................................................... 24 6.0 ILLUSTRATIONS/ATTACHMENTS ........................................................................... 24 Illustration 1: U2 Heatup Rate with Loss of Cooling ..................................................... 25 Attachment 1: Defeating/Restoring PCIS Group 2 Isolation Logic for Shutdown Cooling .................................................................................... 26
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Page 4 of 31 1.0 PURPOSE This instruction provides the symptoms and operator actions for a Loss of Shutdown Cooling.
2.0 SYMPTOMS A. RHR Pump Trip while in Shutdown Cooling Mode:
- 1. RHR SYS I PUMP A(C) TRIPPED, various conditions
[2-XA-55-3D, Window 13(14)]
- 2. RHR SYS II PUMP B(D) TRIPPED, various conditions
[2-XA-55-3E, Window 13(14)]
B. Low RHR Shutdown Cooling Flow while in Shutdown Cooling Mode:
NOTE Valves aligned per 2-POI-74-2 in modes 4 or 5 may NOT be in the required accident position with the breakers open and will NOT isolate.
C. Automatic isolation (PCIS Group II or 100 psig) or manual isolation of RHR System while in Shutdown Cooling Mode:
- 2. 2-FCV-74-47, RHR SHUTDOWN COOLING SUCT OUTBD ISOL VLV CLOSED.
- 3. 2-FCV-74-48, RHR SHUTDOWN COOLING SUCT INBD ISOL VLV CLOSED.
- 4. 2-FCV-74-53, RHR SYS I LPCIINBD INJECT VALVE CLOSED.
- 5. 2-FCV-74-67, RHR SYS II LPCIINBD INJECT VALVE CLOSED.
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Page 5 of 31 2.0 SYMPTOMS (continued)
D. Loss of RHRSW while in Shutdown Cooling Mode:
E. High RHR cooling water temperature while in Shutdown Cooling Mode:
- 1. RHR/FPC HX OUTLET TEMP HIGH at 125°F (2-XA-55-3E, Window 18)
- a. Indication of pressure on RPV or rising Reactor coolant temperature while in a Cold Shutdown condition (Mode 4 or Mode 5).
- b. Indication of RPV water level below Level 3 or Drywell pressure above 2.45 psig.
3.0 AUTOMATIC ACTIONS None
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Page 6 of 31 4.0 OPERATOR ACTIONS 4.1 Immediate Actions None 4.2 Subsequent Actions CAUTIONS
- 1) Reactor vessel stratification may occur until Shutdown Cooling is restored or a Reactor Recirculation Pump is placed in service.
- 2) Loss of Shutdown Cooling during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is most critical due to massive decay heat and limitations on the RHRSW Piping. If Shutdown Cooling is lost during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post reactor shutdown, priorities are required to be placed on the recovery of shutdown cooling in an expeditious manner
[BFN PER 02-003140-000].
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NOTE The following systems, if available, may be used as alternate methods of decay heat removal .Refer to the applicable Tec Spec Bases B 3.4.7, B 3.4.8, B 3.9.7, B 3.9.8 ADHR System- (0-01-72)
Fuel Pool Cooling System- (2-01-78)
RWCU System- (2-01-69)
Ambient losses with natural or forced circulation
[1] IF any EOI entry condition is met, THEN ENTER the appropriate EOI(s). (Otherwise N/A) D
[2] NOTIFY the Shift Manager. D
[3] IF Refueling is in progress, THEN NOTIFY the Refueling Floor SRO. (Otherwise N/A) D
[4] REVIEW EPIP-1, Emergency Plan Classification Logic, for entry conditions. D
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Page 7 of 31 4.2 Subsequent Actions (continued)
[5] IF Shutdown Cooling isolates on low RPV water level or high Drywell press (GROUP 2 ISOL) AND RPV water level needs restoring using LPCI, THEN (Otherwise N/A)
PERFORM the following before reaching -122 inches RPV water level: o NOTE The LPCI inboard injection valve that is aligned per 2-POI-74-2 will already be in the required accident position with the breakers open and will NOT isolate.
[5.1 ] PERFORM the following on a group 2 isolation: o
[5.1.1] IF 2-POI-74-2 is in effect, THEN VERIFY CLOSED one of the following valves:
(Otherwise N/A) o
(
- RHR SHUTDOWN COOLING SUCT OUTBD ISOL VLV, 2-FCV-74-47. 0
- RHR SHUTDOWN COOLING SUCT INBD ISOL VLV, 2-FCV-74-48.
o
- VERIFY CLOSED the LPCI inboard injection valve NOT aligned for 2-POI-74-2, (RHR SYS I LPCI INBD INJECT VALVE, 2-FCV-74-53 OR RHR SYS II LPCIINBD INJECT VALVE, 2-FCV-74-67) 0
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Page 8 of 31 4.2 Subsequent Actions (continued)
[5.1.2] IF 2-POI-74-2 is NOT in effect, THEN VERIFY CLOSED the following valves on a Group 2 isolation: 0
- RHR SHUTDOWN COOLING SUCT OUTBD ISOL VLV, 2-FCV-74-47. 0
- RHR SHUTDOWN COOLING SUCT INBD ISOL VLV, 2-FCV-74-48. 0
- RHR SYS II LPCIINBD INJECT VALVE, 2-FCV-74-67. 0
[5.2] DEPRESS RHR SYS 1(11) SO CLG INBD INJECT ISOL RESET, 2-XS-74-126 and 2-XS-74-132 AND VERIFY 2-IL-74-126 and 2-IL-74-132 extinguished. 0
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Pa_ge 9 of 31 4.2 Subsequent Actions (continued)
[5.3] IF the RHR loop that was in shutdown cooling is needed for RPV water level makeup, THEN PERFORM the following: o
[5.3.1 ] CLOSE RHR PUMP 2A(2B) and 2C(2D)
SO COOLING SUCT VLVs, 2-FCV-74-2(25) and 2-FCV-74-13(36). o CAUTION
[NER) Failure to have the RHR SHUTDOWN COOLING SUCT OUTBD OR INBD ISOL VLV, 2-FCV-74-47 OR 2-FCV-74-48, closed may result in inadvertent draining of the reactor vessel through the RHR PUMP 2A(2B) OR 2C(2D) SUPPR POOL SUCT VLVs, 2-FCV-74-1 (24) OR 2-FCV-7 4-12(35).[INPO SOER 87-002)
[5.3.2] OPEN RHR PUMP 2A(2B) and 2C(2D)
SUPPR POOL SUCTVLVs, 2-FCV-74-1(24) and 2-FCV-74-12(35). o
[5.3.3] PLACE RHR SYSTEM 1(11) MIN FLOW INHIBIT switch, 2-HS-74-148(149), in NORM. o
[5.3.4] VERIFY RHR SYSTEM 1(11) MIN FLOW VALVE, 2-FCV-74-7(30), opens. o
[6] IF Primary Containment Integrity is required, THEN VERIFY RHR system discharge piping pressure is being maintained >TRM 3.5.4 Limits. REFER TO 2-01-74.
(Otherwise N/A) o
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit2 Rev. 0032 Page 10 of 31 4.2 Subsequent Actions (continued)
NOTES
- 1) With the Reactor in Cold Shutdown Condition (Mode 4 or Mode 5), reactor coolant stratification may be indicated by one of the following:
- Reactor pressure above 0 psig with any reactor coolant temperature indication reading at or below 212°F.
- Differential temperatures of 50°F or greater between either RX VESSEL BOTTOM HEAD (FLANGE DR LINE) 2-TE-56-29 (8) temperatures and RX VESSEL FW NOZZLE N4B END (N4B INBD)(N4B END)(N4D INBD) 2-TE-56-13(14)(15)(16) temperatures from the REACTOR VESSEL METAL TEMPERATURE recorder, 2-TR-56-4.
- With recirculation pumps and shutdown cooling out of service, a Feedwater sparger temperature of 200°F or greater on any RX VESSEL FW NOZZLE (N4B END (N4B INBD)(N4D END)(N4D INBD) 2-TE-56-13(14)(15)(16) temperatures from the REACTOR VESSEL METAL TEMPERATURE recorder, 2-TR-56-4.
- 2) (NERlC) For purposes of thermal stratification monitoring, the bottom head drain line is more representative as long as there is flow in the line. [GE SIL 251 and 430)
[7] PLOT heatup/cooldown rate as necessary.
REFER TO 2-SR-3.4.9.1 (1). o
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Page 11 of 31 4.2 Subsequent Actions (continued)
[8] DIRECT the STA to ESTIMATE the following times at least once per shift until a method of decay heat removal is restored: D
[8.1 ] DETERMINE the time since shutdown. D
[8.2] DETERMINE the current RPV heat-up rate from 2-SR-3.4.9.1 (1), or, if reactor coolant stratification is suspected, USE Illustration 1. IF additional information is required to determine the heat-up rates, THEN CONTACT Reactor Engineer. D
[8.3] DETERMINE the reactor coolant temperature or use the last valid reactor coolant temperature available. D
[8.4] ESTIMATE the time for reactor coolant temperature to reach 212°F, using data obtained in Steps 4.2[8.1]
through 4.2[8.3]. D
[8.5] IF the Reactor Vessel head is removed and the cavity is flooded with the fuel pool gates installed, THEN (Otherwise N/A)
ESTIMATE the time for reactor coolant temperature to reach 125°F and 150°F using a plot of the actual heatup rate or Illustration 1. D
[9] IF the loss of Shutdown Cooling is due to inadequate RHRSW flow, THEN START the standby RHRSW pump for the appropriate header.
REFER TO 0-01-23. (Otherwise N/A) D
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Page 12 of 31 4.2 Subsequent Actions (continued)
[10] IF the loss of Shutdown Cooling is due to Group 2 PCIS isolation, WHEN conditions which permit resetting Group 2 PCIS isolation are met, THEN (Otherwise N/A)
PERFORM the following: o
[10.1] RESET Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 2-HS-64-16A-S32, and PCIS DIV II RESET, 2-HS-64-16A-S33, in reset. 0
[10.2] MOMENTARILY DEPRESS RHR SYS 1(11) SD CLG INBD INJECT ISOL RESET, 2-XS-74-126 and 2-XS-74-132. VERIFY 2-IL-74-126 and 2-IL-74-132 extinguished. o
[11] IF the loss of Shutdown Cooling is due to Group 2 PCIS AND the isolation signal fails to reset or remain reset due to invalid and/or sporadic signals, THEN (Otherwise N/A)
PERFORM the following: o
[11.1] VERIFY primary containment integrity is NOT required. 0 CAUTION Defeating of required PCIS group 2 isolation logic for Shutdown Cooling is ONLY to be used for an isolation due to a verified false or spurious signal OR an instrument failure.
Allowance for defeating these interlocks is NOT permitted for isolations due to an actual low water level condition.
[11.2] OBTAIN Shift Manager permission to defeat the Group 2 PCIS isolation logic for Shutdown Cooling. 0
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit2 Rev. 0032 Page 13 of 31 4.2 Subsequent Actions (continued)
[11.3] DEFEAT RHR Group 2 PCIS isolation logic.
REFER TO Attachment 1. o CAUTION Group 2 PCIS isolation logic is required to be operable in Mode 3, 4 or 5 in accordance with requirements of Technical Specifications 3.3.6.1.
[11.4] IF conditions change such that primary containment integrity is required to be reestablished, THEN IMMEDIATELY RESTORE Group 2 PCIS Isolation Logic. REFER TO Attachment 1 . o
[12] IF the Group 2 PCIS Isolation has been reset, THEN RETURN the affected loop of RHR to Shutdown Cooling as follows. o
[12.1] CLOSE RHR SYS 1(11) LPCI OUTBO INJECT VALVE, 2-FCV-7 4-52(66). o NOTE 2-POI-74-2 aligns the RHR system to prevent SOC isolations during modes 4 and 5 operations. For Step 4.2[12.2], it accomplishes this by opening RHR SYS 1(11) LPCI INBO INJECT VALVE, 2-FCV-74-53(67) and opening its associated breaker. If an isolation is received the valve will NOT close because the breaker is open. Therefore, to restore Shutdown Cooling, it is NOT necessary to manipulate this already open valve.
[12.2] OPEN RHR SYS 1(11) LPCIINBO INJECT VALVE, 2-FCV-74-53(67) (IF the valve is aligned per 2-POI-74-2 (valve open with its breaker open), THEN N/A this step). o
[12.3] VERIFY RHR SYSTEM 1(11) MIN FLOW INHIBIT switch, 2-HS-74-148(149) in INHIBIT 0
[12.4] VERIFY CLOSED RHR SYSTEM 1(11) MIN FLOW VALVE,2-FCV-74-7(30). 0
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit 2 Rev. 0032 Page 14 of 31 4.2 Subsequent Actions (continued)
[12.5] VERIFY CLOSED RHR PUMP 2A(2S) and 2C(2D)
SUPPR POOL SUCTVLVs, 2-FCV-74-1(24) and 2-FCV-74-12(35). 0
[12.6] VERIFY OPEN RHR PUMP 2A(2S) and 2C(2D) SD COOLING SUCT VLVs, 2-FCV-74-2(25) and 2-FCV 13(36). 0 NOTE 2-POI-74-2 aligns the RHR system to prevent SDC isolations during modes 4 and 5 operations. For Step 4.2[12.7], it accomplishes this by opening either RHR SHUTDOWN COOLING SUCT OUTSD VLV, 2-FCV-74-47 or INSD ISOL VLV, 2-FCV-74-48 and opening the associated breaker. If an isolation is received the valve will NOT close because the breaker is open. Therefore, to restore Shutdown Cooling, it is NOT necessary to manipulate this already open valve. The other valve will still have power and if closed, is required to be reopened.
[12.7] OPEN RHR SHUTDOWN COOLING SUCT OUTSD and INSD ISOL VLVs, 2-FCV-74-47 and 2-FCV-74-48 (If either valve is aligned per 2-POI-74-2 (valve open with its breaker open), this step will be N/A for that valve.
The other valve will still need to be opened to restore a suction path). 0
[12.8] RESTART tripped RHR pump(s) RHR PUMP 2A(2C)(2S)(2D) using 2-HS-74-5A(16A)(28A)(39A) 0
[12.9] THROTTLE RHR SYS 1(11) LPCI OUTSD INJECTION VALVE, 2-FCV-74-52(66), to establish and maintain RHR flow as indicated by 2-FI-74-50(64), RHR SYS 1(11)
FLOW, as follows: 0 RHR Pumps in Operation 1 2 Loop Flow 7,000 to 10,000 14,000 to 20,000 Loop Flow (1 or more fuel 6,000 to 6,500 N/A bundles removed from core)
BFN Loss of Shutdown Cooling 2-AOI-74-1 Unit2 Rev. 0032 Page 15 of 31 4.2 Subsequent Actions (continued)
[12.10] WHEN time permits after RHR pump is started, THEN VERIFY RHR Pump Breaker charging spring recharged by observing amber breaker spring charged light is on and closing spring target indicates charged. 0
[12.11 ] SLOWLY THROTTLE RHR HX 2A(2C)(2B)(2D)
RHRSW OUTLET VALVE, 2-FCV-23-34(40)(46)(52), to obtain desired cooldown rate. 0
[13] IF necessary, RAISE RWCU flow rate to maximum AND maximize RWCU blowdown as required to maintain reactor coolant temperatures less than 200°F on all indications.
REFER TO 2-01-69. o CAUTION Accurate coolant temperatures will NOT be available if all forced circulation is lost.
[14] [NERlC] IF forced circulation has been lost AND vessel cavity is less than 80 inches, THEN (Otherwise N/A)
PERFORM the following: o
[14.1] RAISE RPV water level to 80 inches as indicated on RX WTR LEVEL FLOOD-UP, 2-U-3-55. 0
[14.2] MAINTAIN RPVwater level between +70 inches to
+90 inches as indicated on RX WTR LEVEL FLOOD-UP, 2-U-3-55. 0
[14.3] RAISE monitoring frequency of reactor coolant temperature and pressure, using multiple indications. 0
[15] IF the affected loop of RHR cannot be placed back in Shutdown Cooling, THEN RESTORE power to affected breakers per 2-POI-74-2 if applicable (Otherwise N/A)
PLACE the alternate loop of RHR in Shutdown Cooling.
REFER TO 2-01-74. (Otherwise N/A) o
JPM NO. 376 REV. NO. 1 PAGE 1 of 14 JPM NUMBER: 376 TITLE: 3-EOI APPENDIX-14B - CAD OPERATION TO THE DRYWELL TASK NUMBER: U-OOO-EM-64 SUBMITTED BY: DATE: _ _ __
VALIDATED BY: DATE: _ _ __
APPROVED BY: DATE: _ _ __
TRAINING PLANTCONCURRENCE: _____________________ DATE: _ _ __
OPERATIONS
- Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence
JPM NO. 376 REV. NO. 1 PAGE 2 of 14 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 11/09/07 All Initial issue 1 08/28/08 All General revision &. re-format
JPM NO. 376 REV. NO. 1 PAGE 3 of 14 OPERATOR: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___
JPM NUMBER: 376 TASK NUMBER: U-OOO-EM-64 TASK TITLE: 3-EOI APPENDIX-14B - CAD OPERATION TO THE DRYWELL KIA NUMBER: 223001A4.04 KIA RATING: RO 3.5 SRO 3.6 TASK STANDARD: PERFORM MANIPULATIONS AS DIRECTED BY 3-EOI APPENDIX-14B REQUIRED TO ADMIT NITROGEN TO THE DRYWELL WITH THE CAD SYSTEM PERFORMANCE LOCATION: SI MULATOR ----:..X..:.....-_
REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-14B, Rev 4 VALIDATION TIME: S IMULATOR:_---:5::;..:..:O;:;..;:O:......-_ LOCAL: _________
MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)
PERFORMANCE TIME:
COMMENTS:
ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ __
JPM NO. 376 REV. NO. 1 PAGE 4 of 14 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an Operator. A LOCA has led to fuel failure and a rising level of hydrogen concentration in the Unit 3 Drywell. EOI-2 has been exited and SAMG-2 entered.
INITIATING CUES: The Unit Supervisor has directed you to align CAD System A to the drywell as directed by SAMG-2 step G-4 using 3-EOI Appendix-14B.
JPM NO. 376 REV. NO. 1 PAGE 50f 14 START TIME _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.
STANDARD:
Obtained copy of 3-EOI Appendix-14B.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
NOTE CAD may be initiated using either CAD TRAIN A (Division I) or CAD TRAIN B (Division II). Equipment identifiers for CAD Train B are in parentheses in the steps below.
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 1. VERIFY containment hydrogen/oxygen analyzer sample pumps in service.
STANDARD:
Verified Sample Pumps in service by observing illuminated RED status lamps above 3-HS-76-59 and 49 on Panels 3-9-54 and 55.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 376 REV. NO. 1 PAGE 6 of 14
(
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 2. MONITOR Drywell and Suppression Chamber Hydrogen and Oxygen concentrations with H2/02 CONCENTRATION recorders 3-XR-76-110A or 3-XR-76-110B (Panel 9-54 or 9-55).
STANDARD:
Located 3-XR-76-110A and 3-XR-76-110B and read off approximate indications.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 3. IF.............. Drywell or Suppression Chamber hydrogen or oxygen analyzers are or become inoperable, THEN....... NOTIFY Chem Lab to sample Drywell and Suppression Chamber for hydrogen and oxygen using CI-644.
STANDARD:
Acknowledged the above step and continued.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 376 REV. NO. 1 PAGE 7 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 4. NOTIFY STA to record post-LOCA containment parameters on Attachment 1 of this procedure every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as required by FSAR.
STANDARD:
Simulated Notifying STA by phone or voice to perform Attachment 1 of this procedure every four (4) hours.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 376 REV. NO. 1 PAGE 8 of 14
(
CAUTION CAD operation with Primary Containment pressure above 30 psig may result in Containment failure.
The following are outside the CAD system FSAR design basis:
- Venting Primary Containment during CAD addition.
- Adding CAD to Drywell and Suppression Chamber at same time.
PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 5. IF.............. While executing this procedure for CAD addition per SAMG-2, Step G-4 or G-9,
- Primary Containment Pressure approaches 30 psig, OR
- Primary Containment is to be vented, THEN....... BEFORE:
- Primary Containment Pressure reaches 30 psig, OR
- Primary Containment venting begins, PERFORM Step 7 to STOP CAD addition to the Primary Containment.
STANDARD:
Verified Primary Containment < 30 psig and acknowledges primary containment not to be vented at this time.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 376 REV~ NO. 1 PAGE 9 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 6. PLACE CAD System in service as follows:
- a. IF ............. CAD addition is required per SAMG-2, Step G-4 or G-9, THEN....... VERIFY all Primary Containment venting is stopped AND Primary Containment Pressure is below 30 psig.
STANDARD:
Verified Primary Containment < 30 psig and acknowledges primary containment not being vented.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
STANDARD:
Placed 0-HS-84-SA in the OPEN position (Critical) and verified illuminated RED valve position indicating lamp (Not Critical).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 376 REV. NO. 1 PAGE 10 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- c. IF ............. CAD addition to Suppression Chamber is required, THEN....... CONTINUE in this procedure at Step 6.e.
STANDARD:
Recognizes that Cad addition to the Suppression Chamber is not required (from Initial Conditions and Initiating Cues) and continues at step d.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
PERFORMANCE STEP: CRITICAL x NOT CRITICAL
- d. INITIATE CAD to Drywell as follows:
(
- 1) PLACE 3-HS-B4-BAlB(BC/D), SUPPR CHBRlDW CAD 3A(3B)
SPL Y SEL, handswitch on Panel 3-9-54(55), in DRYWELL.
- 2) CONTINUE in this procedure at Step 6.f.
STANDARD:
Placed 3-HS-B4-BAIB in the DRYWELL position (Critical) and continues at step 6f (Not Critical).
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __
(
\
JPM NO. 376 REV. NO. 1 PAGE11of14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- f. CHECK CAD operating properly as follows on Panel 3-9-54(55):
- 0-TI-84-27/3(28/3), VAPOR A(8) OUTLET TEMP, indicates approximately 20 degrees below outside air temperature.
- 0-PI-84-6/3(17/3), VAPOR A(8) OUTLET PRESS, indicates below 150 psig.
STANDARD:
Located 0-FI-84-7/3, 0-TI-84-27/3, and 0-PI-84-6/3 (on side of Unit 3 Panel) and Verified acceptable indications.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 376 REV. NO. 1 PAGE 12 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x
- 7. WHEN ..... . Directed by SRO or by Step 5, THEN ...... . STOP CAD addition to the Drywell or Suppression Chamber as follows:
- a. PLACE 3-HS-84-8NB(8C/D), SUPPR CHBRlDW CAD 3A(3B) SPL Y SEL handswitch on Panel 3-9-54(55), in OFF.
c...... IF ..... . CAD is NOT being used to supply Drywell Control Air, THEN ... CLOSE O-FCV-84-5(16), CAD SYSTEM A(B) N2 SHUTOFF, on Panel 3-9-54(55).
STANDARD:
N/A SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
JPM NO. 376 REV. NO. 1 PAGE 13 of 14
(
PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:
PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:
PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.
SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __
END OF TASK STOP TIME: _ _ _ _ _ __
PAGE 14 of 14
(
IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an Operator. A LOCA has led to fuel failure and a rising level of hydrogen concentration in the Unit 3 Drywell. EOI-2 has been exited and SAMG-2 entered.
INITIATING CUES: The Unit Supervisor has directed you to align CAD System A to the drywell as directed by SAMG-2 step G-4 using 3-EOI Appendix-14B.
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EOI PROGRAM MANUAL SECTION IX 3-EOI APPENDIX-148 CAD OPERATION REVISION 4 PREPARED BY: M. Morrow PHONE: 3708 RESPONSIBLE ORGANIZATION: Operations APPROVED BY: Tony Elms EFFECTIVE DATE: 04/24/2008 LEVEL OF USE: REFERENCE USE EOI VALIDATION DATE: 02/14/1992 QUALITY -RELATED
HISTORY OF REVISION/REVIEW 3-EOI APPENDIX-148 REV. REVISED REASON FOR CURRENT REVISION NO. PAGES 4 1 Step 2: Changed hydrogen and oxygen recorder reference to 3-XR-76-110A or B. (DCN 66228A) 4 Attachment 1: Changed hydrogen and oxygen recorder reference to 3-XR-76-110A or B. (DCN 66228A)
3-EOI APPENDIX-14B Rev. 4
. g e10f4
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .pa 3-EOI APPENDIX .. 148 CAD OPERATION LOCATION: Unit 3 Control Room ATTACHMENTS: 1. Post-LOCA Containment Parameters NOTE: CAD may be initiated using either CAD TRAIN A (Division I) or CAD TRAIN B (Division II). Equipment identifiers for CAD Train B are in parentheses in the steps below.
- 1. VERIFY containment hydrogen/oxygen analyzer sample pumps in service.
- 2. MONITOR Drywell and Suppression Chamber Hydrogen and Oxygen concentrations with H2/02 CONCENTRATION recorders 3-XR-76-110A or 3-XR-76-110B (Panel 9-54 or 9-55).
- 3. IF .............. Drywell or Suppression Chamber hydrogen or oxygen analyzers are or become inoperable, THEN ....... NOTIFY Chem Lab to sample Drywell and Suppression Chamber for hydrogen and oxygen using CI-644.
- 4. NOTIFY STA to record post-LOCA containment parameters on Attachment 1 of this procedure every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as required by FSAR.
3-EOI APPENDIX-14B Rev. 4 Page 2 of4 CAUTION CAD operation with Primary Containment pressure above 30 psig may result in Containment failure.
The following are outside the CAD system FSAR design basis:
- Venting Primary Containment during CAD addition.
- Adding CAD to Drywell and Suppression Chamber at same time.
- 5. IF .............. While executing this procedure for CAD addition per SAMG-2, Step G-4 or G-9,
- Primary Containment Pressure approaches 30 psig, OR
- Primary Containment is to be vented, THEN ....... BEFORE:
- Primary Containment Pressure reaches 30 psig, OR
- Primary Containment venting begins, PERFORM Step 7 to STOP CAD addition to the Primary Containment.
- 6. PLACE CAD System in service as follows:
- a. IF ............. CAD addition is required per SAMG-2, Step G-4 or G-9, THEN ....... VERIFY all Primary Containment venting is stopped AND Primary Containment Pressure is below 30 psig.
- b. OPEN O-FCV-84-5(16), CAD SYSTEM A(B) N2 SHUTOFF VALVE, on Panel 3-9-54(55).
- c. IF ............. CAD addition to Suppression Chamber is required, THEN ....... CONTINUE in this procedure at Step 6.e.
3-EOI APPENDIX-14B Rev. 4 Page 3 of4
- 6. (Continued)
- d. INITIATE CAD to Drywell as follows:
- 1) PLACE 3-HS-84-8A1B(8C/D), SUPPR CHBR/DW CAD 3A(3B)
SPLY SEL, handswitch on Panel 3-9-54(55), in DRYWELL.
- 2) CONTINUE in this procedure at Step 6.f.
- e. INITIATE CAD to Suppression Chamber by PLACING 3-HS-84-8A1B(8C/D), SUPPR CHBR/DW CAD 3A(3B) SPLY SEL, handswitch on Panel 3-9-54(55), in SUPPR CHBR.
- f. CHECK CAD operating properly as follows on Panel 3-9-54(55):
- 0-TI-84-27/3(28/3), VAPOR A(B) OUTLET TEMP, indicates approximately 20 degrees below outside air temperature.
- 0-PI-84-6/3(17/3), VAPOR A(B) OUTLET PRESS, indicates below 150 psig.
- 7. WHEN ...... Directed by SRO or by Step 5, THEN ....... STOP CAD addition to the Drywell or Suppression Chamber as follows:
- a. PLACE 3-HS-84-8A1B(8C/D), SUPPR CHBR/DW CAD 3A(3B) SPLY SEL handswitch on Panel 3-9-54(55), in OFF.
c ...... IF ......... CAD is NOT being used to supply Drywell Control Air, THEN ... CLOSE 0-FCV-84-5(16), CAD SYSTEM A(B) N2 SHUTOFF, on Panel 3-9-54(55).
END OF TEXT
3-EOI APPENDIX-1 Rev. 4 Page 4 of4 ATTACHMENT 1 POST-LOCA CONTAINMENT PARAMETERS RECORD readings every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> DATE/TIME DATE/TIME DATE/TIME DATE/TIME RECORDER
/ / / /
OW TEMP TI-64-52 SCTEMP XR-64-52 OW PRESS PI-64-160A SC PRESS XR-64-52 H2 XR-76-110A OW or 02 XR-76-110B H2 XR-76-110A SC or 02 XR-76-110B - ----- I LAST PAGE