ML030430606
| ML030430606 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/05/2002 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Scalice J Tennessee Valley Authority |
| References | |
| 50-327/02-301, 50-328/02-301 50-327/02-301, 50-328/02-301 | |
| Download: ML030430606 (333) | |
Text
Draft Submittal (Pink Paper)
SEQUOYAH NUCLEAR PLANT EXAM 2002-301 50-327 & 50-328 DECEMBER 2 - 6, 2002 I
"-1. Administrative Questions/JPMs
-2. In-plant JPMs
-3. Control Room JPMs (simulator JPMs)
-4. Administrative Topics Outline ES-301-1
- Control Room Systems and Facility Walk-Through Test Outline ES-301-2
Form ES-301-1 ES-301 Administrative Topics Outli-e
- - Industry OE importance item
Administrative Topics Outline Form ES-301-1 ES-301 Facility: Sequoyah Date of Examination: 12-02-02 Operating Test Number: 1 Examination Level (circle one): SRO Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Plant JPM # 161, Calculate Subcooling Margin Parameter Verification Maximum # of fuel assemblies in refueling canal.
Refueling 2.2.30/3.5 Operations Unexpected increase in count rate during fuel load.
2.2.30/3.5 A.2 Equipment Work Request Priority. 2.2.19/3.1 Control Releasing equipment for maintenance. 2.2.17/3.5 A.3 Radiation JPM (NEW) Calculate Stay Time Control A.4 Emergency JPM #164, (NEW) Classify the REP Plan
ES-301 Control Room Systems and Facility Walk-Through Test OutlinForm ES-301-2 Facility: Seouoyah Date of Examination: 12-02-02 Exam Level (circle one): RO Operating Test No.: I B.1 Control Room Systems System/ JPM Title Type Code* Safety Function 150, Flush Unit 1 Blender Piping D, S 1 136, Recovery from SI and Solid Water Conditions D, S, L 3 Z_
077-4 AP2, Perform D/G Load Test on 1A-A D/G D, S, A 6 34, Loss of Secondary Heat Sink D, S, L, 4S t(
PSA 021, Respond to a Failure of PR N-41 D, S 7 065, Re-establishment of Containment Pressure Control D,S 5 14 AP, Control Room Inaccessibility N,S,A, L 8 099 AP, Locally Align 1B-B CCS Pump to Supply B Train D, P, R, A 8 42, Placing Vital Inverter 1-11 Back in Service b 6 201R AP1, Local Isolation of Charging with Local Control N, P, R, L, 2 of Seal Injection Flow A
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
r ,*'-I 1'-,.÷, Q,,~-,,t- s andt F:acilitv W alk-Throu h Test Outline F-orm r-b-ou 1-2 Facility: Sequoyah Date of Examination: 12-02-02 Exam Level (circle one): SRO (U) Operating Test No.: 1 B.1 Control Room Systems System / JPM Title Type Code* Safety Function
- - I 4 D,S I 150, Flush Unit 1 Blender Piping D, S, L, 4S 34, Loss of Secondary Heat Sink PSA N,S,A,L 8 014 AP, Control Room Inaccessibility 42, Placing Vital Inverter 1-11 Back in Service D 6 N, P, R, L, 2 201 R AP1, Local Isolation of Charging with Local Control of Seal Injection Flow A
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
JPM#161 Page 1 of6 REV. 1 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 161 Calculate Subcooling Margin PREPARED/
REVISED BY: Date/
VALIDATED BY:
- Date/
APPROVED BY: Date/
(Operations Training Manager)
CONCURRED: ** Date/
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM 2#161 Page of 6 REV. 1 NUCLEAR TRAINING
-v REVISION/USAGE LOG DESCRIPTION OF V DATE PAGES PREPARED/
REVISION AFFECTED REVISED BY:
NUMBER I V IY REVISIO 1411 L. Pauley/P. Gass 0 Initial Issue Y 07/18/00 I All 12/17/01 L. Pauley pen/ink Minor changes to setup and recalculated N 4,5,6 subcooling margin N 8/22/02 4,5,6 J P Kearney 1 Incorporated penAnk change V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM #161 Page 3 of 6 REV. 1 SEQUOYAH NUCLEAR PLANT RO/SRO
/ JOB PERFORMANCE MEASURE Task: Calculate Subcooling with no Subcooling Monitors and NO Plant computers available.
JA/TA task #: (RO/SRO)
K/A Ratings: 002K5.09 (3.7/4/2) 002A1.04 (3.9/4.1)
Task Standard:
and calculated results Determine actual subcooling margin based on Control Board Indicators using Steam Tables.
Evaluation Method : Simulator ___X In-Plant_
Performer: Start Time NAME UNSAT Performance Time Finish Time
'erformance Rating: SAT__
Evaluator: /
SIGNATURE DATE COMMENTS
JPM #161 Page 4 of 6 REV. 1 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps identified by an asterisk ()
- 2. Sequenced steps identified by an "s"
- 3. Any UNSAT requires comments
- 4. Initialize the simulator in IC-92. Trip the Reactor, and FREEZE the simulator when RCS pressure is -2110 psig and RCS HL temperature is - 5500 F (if necessary open PZR spray valve to lower pressure). Place covers over the Saturation Monitor Displays.
- 5. Supply Examinee with a Steam Table and hand held calculator.
Validation Time: CR. 15 mins Local Tools/Equipment/Procedures Needed:
References:
Reference Title Rev No.
- 1. Steam Tables Combustion Engineering Steam Tables 15 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. I will provide initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Unit has tripped from 100% power and all system have responded normally.
The ICS computers and Saturation Monitor Displays were out of service just before the trip and have not been returned to service.
INITIATING CUES:
You are the Unit 1 RO and the US has directed you to determine the amount of Subcooling in the RCS if any. Report your findings to the US when your calculations are complete.
JPM #161 Page 5 of 6 REV. 1 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT
-STEP 1 .: Operator obtains a copy of Steam Tables and a Hand held SAT calculator.
UNSAT NOTE: Calculator and Steam Tables are located on Simulator Desk.
Start Time NOTE: If JPM is performed in the Main Control Room, the examiner should provide a Calculator and Steam Tables.
STANDARD: Operator locates Steam Tables and a Hand held calculator.
STEP 2.: Obtain RCS Hot Leg Temperature. __ SAT UNSAT Cue: If JPM is performed in the Main Control Room, Examiner will give the examinee a temperature of 5500 F. Critical Step STANDARD: Operator observes RCS Hot Leg Temperature Indicators marked as PAM and determines HL Temperature is approximately 550 degrees F. (1-TI-68-1, 1-TI-68-24, i-TI-68-43, 1-TI-68-65)
"- 'STEP 3.: Obtain RCS Pressure. SSAT Cue: If JPM is performed in the Main Control Room, Examiner will UNSAT give the examinee a pressure of 2110 psig.
STANDARD: Operator observes RCS Pressure Indicators marked as PAM and Critical Step determines RCS Pressure is approximately 2110 PSIG. (1-PI 68-66A, 1-PI-68-62, 1-PI-68-69)
STEP 4.: Determine Saturation Temperature for RCS Pressure of 2110 __- SAT psig.
UNSAT STANDARD: MCR calculation: Operator refers to Steam Tables and Critical Step determines Saturation temperature for 2150 psig is approximately 647 degrees.
Simulator Calculation: May be different based on simulator RCS pressure and temperature.
JPM #161 Page 6 of 6 REV. 1 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT
--STEP5.: Determine subcooling margin forgiven parameters.
SAT NOTE: Subcooling calculationresults in- 96 degrees Fsubcooled. UNSAT (92 to 102 degrees will be acceptableif no cues for temperature or pressureare given by the examiner.)
Critical Step STANDARD: Operator determines subcooling is approximately 96 degrees F.
based on calculation from given information. Stop Time End of JPM
A.1 Q.1 Fuel Handling A maximum of three fuel assemblies are allowed to be in the refueling canal at the same time. What are the specific locations permitted for these three fuel assemblies in the refueling canal?
Reference Allowed Yes Answer:
Two fuel assemblies are permitted in the rod cluster control changing fixture. The third fuel assembly is allowed either in the upender, in the fuel transfer tube, or in transit to or from the refueling cavity.
Reference:
FHI-3, Movement of Fuel, P. 15 K/A: 2.2.30 (2.6/3.5)
SQN FHI-3 MOVEMENT OF FUEL Rev: 36 1,2 Page 15 of 97 II. PRECAUTIONS Continued
- 17. Due to possible seal failure on the SFP gate; an Operator is required to be at the Rx side controls at all times when the Fuel Transfer Cart is on the Rx side. An operator is required at all times on the SFP side when the blind flange is removed and wafer valve is open, and the transfer canal is dry, to watch for SFP gate seal failure. [C.1]
D. MAIN CONTROL ROOM The applicable control room fuel assembly monitoring system (i.e. electronic fuel shuffle program) should be kept current during major fuel-handling operations (not required during movement of new fuel into the SFP). The Fuel Assembly Transfer Forms (FATF's) are the official record for fuel movement.
Ill. LIMITATIONS A. The hoist "slow" speed shall be used prior to entering a confined area (such as a fuel rack or upender) when bottom fuel nozzle of fuel assembly is approximately 10 inches above the confined area and continue in "slow" speed until bottom fuel nozzle is inside the confined area. The hoist "slow" speed shall also be used prior to bottom of fuel assembly reaching bottom of the confined area, (when bottom of fuel assembly is approximately 10 inches from bottom) until fuel assembly reaches the bottom.
B. The maximum number of nuclear fuel assemblies allowed out of approved storage locations for Sequoyah Nuclear Plant shall be as listed below: [C.5]
- 1. One unirradiated nuclear fuel assembly shall be allowed within the fuel handling area, outside of metal shipping containers, or the new fuel storage vault.
- 2. One nuclear fuel assembly shall be allowed within the spent fuel storage pool boundary when not seated in a storage cell. The spent fuel storage pool boundary includes the cask loading area and fuel transfer canal excluding the upender.
- 3. Three nuclear fuel assemblies shall be allowed within the refueling canal.
The refueling canal includes the fuel transfer tube boundary, the rod cluster control changing fixture and the upender. This allows for two nuclear fuel assemblies to be in the rod cluster control changing fixture while the third nuclear fuel assembly is being transferred through the fuel transfer tube, is in the upender, or is in transit to or from the reactor cavity.
- 4. One fuel assembly shall be allowed within the reactor cavity.
C. DO NOT allow the RCS and Spent Fuel Pit temperature to decrease below 50 degrees, which is the bound of the criticality analysis. [C.9]
A.1 Q.2 Fuel Handling Refueling operations are in progress on Unit 1. The core has been completely off-loaded and 10 new assemblies have been loaded. Count rate on all nuclear instrument channels are 60 cps. After loading the 1lhfuel assembly, neutron count rate increases to between 180 and 320 cps on all nuclear instrument channels (with no movement of neutron detectors or source).
Reference Allowed Yes Answer:
Fuel loading may continue because there are no restrictions on nuclear instrumentation readings until after the first 12 fuel assemblies are loaded.
Reference:
FHI-3, Movement of Fuel, P.7 K/A: 2.2.30 (2.6/3.5)
SON FHI-3 MOVEMENT OF FUEL Rev: 36 1,2 Page 7 of 97 II. PRECAUTIONS Continued
- d. The fuel assembly is fully seated before releasing the handling tool. For the manipulator crane this means Z-Z tape is within 1/4 inch of full down travel prior to unlatching a fuel assembly.
- e. Always check Z-Z axis tape for gripper location before moving manipulator crane. Disregard all indicating lights until this is done. Ifnot shown in the proper position, then have the limit switches checked.
- f. Lateral movement of the fuel handling hoist is prohibited while any part of the latched fuel assembly is inserted into the storage cells, transfer system, or elevator; unless lateral movement is required to compensate for fuel bow and the FHS approves the action.
- 11. Water in the fuel storage pool and core should be clear enough during periods of fuel movement to view the top of the fuel assemblies, storage racks, new fuel elevator, and upenders.
Adequate lighting should be provided to establish clear visibility in the fuel storage pool and core.
During a core reload, in addition to the above requirements, the lower core support plate and pins must be visible in order to verify proper engagement of the bottom nozzle with lower core plate pins.
Supplemental lighting (drop lights or equivalent) should be provided as required.
- 12. Do not switch the CONVEYOR DIRECTION switch to the desired direction, Rx or pit side, until ready to start conveyor cart. This is to help prevent inadvertent movement of conveyor.
- 13. Use visual aids such as television cameras and binoculars and viewing boxes as necessary.
- 14. Fuel loading/unloading operations stop immediately if: [C.4]
- a. An unanticipated increase in the neutron count rates by a factor of two (2) occurs on all responding nuclear channels during any single loading step after the initial twelve fuel assemblies are loaded. (Excluding anticipated change due to detector and/or source movement).
A.2 Q.1I Equipment Control On Unit 1, what is the concern with using Alternate Dilute additions to the VCT? Why?
Reference Allowed Yes Answer:
Alternate dilution in small amounts is acceptable on a regular basis, provided no significant changes in seal water temperature or seal leakoff are indicated. Batches of 5 to 10 gallons may be added through FCV-62-144 on a frequency not to exceed once per 30 minutes.
ICS points for No. 1 seal leakoffs and seal water temperatures on the RCPs should be monitored during and after dilution.
This allows mixing of incoming water and less temperature changes on the RCP seals.
Reference:
0-SO-62-7, p. 1 8 K/A: 2.2.2 (4.0/3.5)
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SQN O 0-SO-62-7 1,2 BORON CONCENTRATION CONTROL Rev. 19 Page 18 of 129 Unit Date 6.2 Dilute (Continued)
[11] VERIFY the following;
[a] Inlet to top of VCT FFCV-62-1281 is OPEN.
[b] Primary Water flow by rFI-62-142A1 or rFQ-62-1421.
NOTE Alternate dilution in small amounts is acceptable on a regular basis, provided no significant changes in seal water temperature or seal leakoff are indicated. Batches of 5 to 10 gallons may be added through FCV-62-144 on a frequency not to exceed once per 30 minutes. ICS points for No.
1 seal leakoffs and seal water temperatures on the RCPs should be monitored during and after dilution.
[12] IF primary water addition to the bottom of the VCT iFCV-62-1441 is desired, THEN
[a] CLOSE rFCV-62-1281 with rHS-62-1281.
[b] OPEN rFCV-62-1441 with rHS-62-1441.
[c] VERIFY Primary Water flow by rFI-62-142A1 or iFQ-62-1421.
NOTE It will take approximately 15 minutes before any changes to reactivity are indicated on nuclear instrumentation or RCS temperature indication.
[13] MONITOR nuclear instrumentation and reactor coolant temperature to ensure the proper response from dilution is achieved. 17
A.2 Q.2 Equipment Control 3/4>
- a. Describe the rod thermal lockup concern that exists when RCS temperature changes with the reactor shutdown.
- b. How is the possibility of rod thermal lockup minimized prior to a planned RCS heatup or cooldown?
Reference Allowed Yes Answer:
- a. Rod thermal lockup can occur from a 50 degree RCS temperature change if the rods are fully inserted and the reactor trip breakers are closed.
- b. The possibility of rod thermal lockup is minimized by withdrawing shutdown and control rods at least 5 steps prior to the RCS temperature change.
Reference:
O-GO-l, p.9 K/A: 2.2.1 (3.7/3.6)
SQN UNIT STARTUP FROM COLD 0-GO-1 1 &2 SHUTDOWN TO HOT STANDBY Rev: 27 Page 9 of 97 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS A. Criticality shall be anticipated any time the shutdown or control banks are being withdrawn or when dilution operations are in progress.
B. Rod thermal lock-up during plant cooldown is not a concern when the reactor trip breakers are OPEN. If reactor trip breakers are CLOSED and an RCS cooldown of > 50'F is planned, the shutdown and control banks should be withdrawn at least 5 steps each. This will limit the possibility of "thermal lock up" of the rods. [C.9]
C. In the source range, changes in boron concentration should be made as a batch process. Allow 15 minutes after each batch process for system mixing and sampling. Approximately one hour is needed for the chemistry section to obtain results from the analysis of a representative sample.
D. Continuous flow shall be maintained in the pressurizer spray lines to protect the lines from thermal shock and help maintain uniform water chemistry.
E. The boron concentration in the pressurizer should be maintained within 50 ppm of the RCS by use of pressurizer heaters and spray.
F. Any time the MSIVs are closed and vacuum is on the main condenser, consideration shall be given to saturation temperature and pressure conditions in the steam generators if they are exposed to condenser vacuum. Swell and shrink of steam generator levels shall also be considered if a differential pressure exists across the MSIV's (i.e., vacuum vs. N2 pressure). This may prevent an ESF actuation. (Ref. PRO 1-84-344).
G. Any pressure differential change across the containment divider barrier when lower compartment pressure is higher than upper compartment could cause the lower ice condenser inlet doors to open. CRDM fan operation when aligned to the shroud with the divider barrier not being intact between lower and upper containment could cause the lower ice condenser inlet doors to open.
A.2 Q.1 Equipment Repair Unit 2 is operating at 100% power steady state when the following alarm actuates:
"COMPUTER ALARM ROD DEV & SEQ NIS PWR RANGE TILTS" Upon investigation it is determined that control rod H4 is mis-aligned from its bank by 20 steps, immovable, and un-trippable. When the Work Request for control rod H4 is prepared, what priority is appropriate for these conditions?
Reference Allowed Yes Answer:
Priority P-2, the SM may assign a P- 1 if he deems it an emergency
Reference:
SPP-7.1, Appendix B K/A: 2.2.19 (2.1/3.1)
May refer to: TS 3.1.3.1 ARP 1-AR-M4-B, D4 SPP-6.1
<2
TVANSTANDARD SPP-7.1 Rev. 3 PROGRAMS AND WORK CONTROL PROCESS Page 16 of 19 PROCESSES APPENDIX B Page 1 of 1 SCHEDULING PRIORITY PRIORITY DEFINITION 1 An emergency situation which requires immediate action.
Emergency These activities require the approval of the Operations Shift Manager who will ensure that an appropriate manager is assigned responsibility of directing the activity until completion in accordance with SPP-6.0, "Maintenance and Modifications", SPP-6.1, "Work Order Process Initiation", and MMDP-1, "Maintenance Management System."
2 An immediate attention situation which if not Immediate Attention corrected would adversely affect plant operation.
Situation that warrant Priority 2 should be planned and worked continuously (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day) until completion. The requirements may be relaxed at the discretion of the Operations Shift Manager (SM).
3 An activity which can be performed with the unit Routine Priority on-line at or near full power. Operations can direct a priority 3 activity to be emerged into the schedule by coordination with the work week manager.
4 An activity which requires a reactor shutdown or Planned and Forced the turbine to reduce load or shut down. These Outage activities do not require a refueling outage to be performed, but may require the reactor to go to Cold Shutdown.
5 An activity to be performed in a refueling outage.
Refueling Outage 6 An activity which needs to be performed prior to Pre-outage the commencement of a refueling outage.
7 An activity on non-plant or spare equipment. An Spare activity on plant process equipment which is cosmetic in nature that plant operation for an indefinite period of time will not be compromised by the deficiency.
The second and third positions of the priority field in the maintenance data base are used for scheduling purposes to provide additional information relative to when the work activity should be scheduled.
manager as Additional characters in the priority field should be used at the discretion of the scheduling special needs arise. Definition of these priorities will be defined in the drop down screen of the computerized maintenance system.
A.2 Q.2 Equipment Repair Unit 2 is operating at 100% steady state. The TDAFW pump is scheduled to be removed from service for routine cleaning, inspection, and lubrication. It is expected to be returned to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Prior to SM releasing the pump for maintenance, who else must review and approve the planned work?
Reference Allowed Yes Answer:
The WCC SRO performs the initial review of the WO, the Operations designee approves the work to begin.
Reference:
ODM-1.0, Appendix M SPP-7.1 TS 3.7.1.2 K/A: 2.2.17 (2.3/3.5)
OPERATIONS DIRECTIVE MANUAL ODM-1.0 Conduct Of Operations Appendix M - Work Control
- 8. The SM/US shall evaluate WO against the criteria in SPP-3.1 to determine if a condition adverse to quality exists. If yes, initiate a PER in accordance with SPP-3.1. (SPP-6.1 section 3.3)
Unit Supervisor
- 1. The Unit 1 US and the Unit 2 US are each jointly responsible with the WCC SRO for implementing the schedule for their units, including all Operations activities as well as support for work scheduled by other departments. The US prioritizes tasks on his unit to minimize equipment downtime (e.g., release clearances and perform PMTs in a timely manner). Special emphasis is given to work that involves either the Maintenance Rule or entry into an LCO.
- 2. The US notifies the SM if unable to complete or support scheduled work.
He is the primary contact and coordinator for site groups needing Operations support in completing scheduled activities.The WCC SRO should maintain a broad awareness of maintenance activities being performed in the plant, and aggressively pursue completion of scheduled activities.
- 2. The WCC SRO reviews emergent work for clearance need, and either writes one or defers it to the UM if workload constraints prevent supporting it.
- 3. The WCC SRO coordinates PMT completion with the Risk SRO, the craft and the US for package closure or operability declaration.
- 4. The WCC SRO updates the schedule and provides it to the WWM or Daily Scheduling (DSG). The WCC SRO should add information useful to on shift personnel to a scheduled activity to aid in allocating resources, prioritizing activities and minimizing equipment unavailability.
- 5. The WCC SRO will perform initial reviews of WO, review/revise RTO tests as necessary to ensure TS operability and surveillance requirements are met without imposing any adverse affects on the system or equipment, contact System Engineering if assistance is needed, approve the RTO tests, ensure that the PMT satisfies all TS requirements, include status control requirements in the WO package, ensure that the PMTs are performed at the appropriate system operating conditions or plant modes, review WO scope changes and revise RTO tests as necessary. (SPP-6.3 section 3.4 and SPP-7.1 section 3.4)
Appendix M - Work Control Revision 0 Page 2 of 7
OPERATIONS DIRECTIVE MANUAL ODM-1.0 Conduct Of Operations Appendix M - Work Control Unit Manager
- 1. The UM provides Operations input at scheduling meetings. He represents Operations at the daily schedule variance meeting, and provides response for scheduled activities that were not completed. He provides input to the DSG concerning scheduled activities.
- 2. The UM resolves scheduling conflicts brought to him by onshift personnel, either due to the nature of the problem or the workload, and obtains additional resources from the Operations Superintendent when necessary. The UM determines with the WWM if rejected work should be rescheduled or remain until resolved.
- 3. The UMs are responsible for day to day oversight of the WCC. In their absence the Risk SRO will assume these responsibilities. The WCC oversight function ensures; schedule risk is assessed, Operations schedule performance is monitored, clearances are written to support the schedule, work package reviews are completed to support the schedule, action is taken to resolve work package rejections, schedules contain adequate information on what needs to be done for rejected work, issues that may negatively impact schedule performance are identified, schedules contain desired information on Operations activities/concerns, work is tracked for those fragnet activities that involve LCO entry, and PMTs in FS status are tracked and closed in a timely manner.
Risk SRO
- 1. The RSRO is the normal point of contact for the DSG when questions arise concerning feasibility of performing work or determining proper logic ties.
The RSRO fills the role of the UM when he is unavailable.
- 2. The RSRO reviews the frozen T-l or T-2 schedule for risk to nuclear safety and continued operation, and is responsible for ensuring that the schedule makes sense from an Operations perspective. He ensures LCO times are optimized, hold order placement and removal are timed properly, and sensitive equipment is flagged. He provides input to DSG to add a schedule note,to clarify an activity, or to add an Operations activity in support of another activity. The RSRO is the primary coordinator for PMTs (performance and tracking).
WCC Operations Specialist
- 1. The WCC OS reports to the UM, and is responsible for writing clearances at T-3 before WO packages are scheduled. The WCC OS informs the UM if he rejects a package during this clearance review.
- 2. While performing package reviews for necessary clearances, the WCC OS also identifies pertinent information, and forwards it to the UM to add to the SAppendix M - Work Control Revision 0 Page 3 of 7
OPERATIONS DIRECTIVE MANUAL ODM-1.O Conduct Of Operations Appendix M - Work Control schedule. Additionally, if a clearance will require greater than two hours to place due to the large number of tags or time required to drain etc., the WCC OS will estimate the time required and pass on that information.
- 3. The WCC OS may assist the WCC SRO by writing clearances for routine or emergent work. If this impacts his ability to complete the advance clearances needed to support the upcoming work week, the UM will be notified.
- 4. The WCC OS should add information useful to on shift personnel to a scheduled activity to aid in allocating resources, prioritizing activities and minimizing equipment unavailability.
B. General Requirements
- 1. The WWM, RSRO and UMs are responsible for efficiently scheduling equipment outages. Their goal is to get the greatest number of deficiencies corrected in the least number of equipment outages.
- 2. A hard copy printout of Control Room Panel Deficiencies will be maintained in the MCR in the "WR Book". A program has been set up in the Sequoyah Site Information program to access the list of WRs coded with this focus area, in addition to allowing the addition of notes and panel numbers. Control Room Panel Deficiencies are comprised of the following: MCR nuisance alarms; Disabled annunciators; Instruments and controls that are not able to perform their function.
- 3. ODM-3.7 contains the details of the OWA program. Operations personnel will maintain cognizance of those items or issues currently designated as OWAs.
When writing or screening WRs, Operations personnel should maintain a sensitivity towards deficiencies that may create an OWA.
- 4. Troubleshooting plans that involve quality or safety related components or place the plant at some risk to generation should be reviewed with the Duty Operations Manager and/or the Duty Plant Manager. Troubleshooting plans for safety or quality related systems or components should be evaluated to the 10CFR 50.59 criteria. A programmatic approach to development of a troubleshooting plan can be found in 0-TI-GTS-000-623.0 "Guidelines for Planning and Execution or Troubleshooting Activities".
- 5. The following data must be entered as a minimum on the WO; name and employee ID number, equipment UNID, description of problem (symptoms and observations), and location of component/equipment. (SPP-6.1 section 3.2.3)
Appendix M - Work Control Revision 0 Page 4 of 7
OPERATIONS DIRECTIVE MANUAL ODM-t.O Conduct Of Operations Appendix M - Work Control
- 6. Submit WOs initiated manually to the Operations Shift Manager (SM) or designee for evaluation and approval within one (1) shift. WOs initiated electronically are routed automatically. (SPP-6.1 section 3.2.5)
- 7. End device testing shall be performed when it is necessary to exercise the end device in order to demonstrate that the maintenance has been performed correctly or in order to demonstrate TS operability. In cases where plant conditions do not support exercising an end device, as authorized by an approved procedure or by the Shift Manager, bench tests or alternate checks shall be considered and affected configuration changes shall be verified by independent verification. (SPP-6.3 section 3.2.B)
- 8. PMTs for safety-related circuits shall include testing to ensure affected portions of the logic circuitry, including the parallel logic, interlocks, bypass and inhibit circuits, relay contacts, control switches, and other relevant electrical components are tested if they were potentially affected. In cases where plant conditions do not support functional testing of a component such as an instrument or a relay after its connection into a circuit, as authorized by an approved procedure or by the Shift Manager, bench tests or alternate checks shall be considered and affected configuration changes shall be verified by independent verification. (SPP-6.3 section 3.2.E)
- 9. Technical assistance may be provided by Site Engineering, Operations, or others as necessary in determining the correct PMT. (SPP-6.3 section 3.2.G)
- 10. Revisions to RTO tests may be made by two SROs without routing back through the review cycle provided that the reason is documented and both SROs sign the revision and IQR and 10 CFR 50.59 review was not required previously. A PMT requirement may be waived provided that the Shift Manager authorizes the waiver, the reason is documented, and affected configuration changes are verified by independent verification. (SPP-6.3 section 3.4)
- 11. For non-outage PMTs which cannot be initiated within the shift of completion of the field work, 1) leave the existing clearance/hold order in place if applicable, or, 2) if the equipment is to be returned to service, issue a caution order in accordance with SPP-10.2. Operability of Technical Specification equipment, Technical Specification attendant equipment and other equipment encompassed by the license is not to be impacted (e.g., EQ, PAM, ODCM).
(SPP-6.3 section 3.5)
- 12. The Shift Manager (SM)/designee shall be notified prior to the start of any Hot Work activity involving tungsten inert gas (TIG) welding in the Reactor, Control, Auxiliary, or Turbine Buildings. (SPP-10.11 section 3.1.D)
Appendix M - Work Control Revision 0 Page 5 of 7
OPERATIONS DIRECTIVE MANUAL ODM-1.0 Conduct Of Operations Appendix M - Work Control
- 13. Prior to performing a Special Test the test director must obtain permission from the SM to perform the test. Upon completion of a Special Test a signoff will be obtained by the SM. (SPP-8.4 section 3.2.6)
- 14. Qualified Operations personnel shall operate equipment as directed by the SM, US, UO in accordance with an approved plant procedure or work document.
(SPP-10.1 section 3.2.1.A)
- 15. Anyone may submit either a single item or an aggregate effect for consideration as an Operator Workaround. Submission may be by a simple Write-up of the problem, which should be forwarded to the SM/US. (OPDP 1 section 3.14)
- 16. All activities which change or have the potential to change a plant component, system, or unit configuration shall be scheduled, planned, approved, and performed using established Work Control processes and practices. (SPP-7.0 section 3.1)
- 17. Risk assessments for implementation of immediate attention, Fix-It-Now (FIN) team work and unscheduled minor maintenance, and unscheduled work are performed by Operations and generally will not require an Appendix C of SPP 7.1. (SPP-7.1 section 3.3)
- 18. The SM has the authority to call out all required persons regardless of discipline. (SPP-10.0 section 3.3)
- 19. The responsible supervisor shall sign Form SPP-8. 1-1, "Test Director Assignment Sheet" to attest the Test Director possesses the qualification to perform or oversee the conduct of the test. (SPP-8.1 section 3.1)
C. References
- 1. SPP-3.0
- 2. SPP-6.0
- 3. SPP-6.1
- 4. SPP-6.3
- 5. SPP-7.0
- 6. SPP-7.1
- 7. SPP-8.2
- 8. SPP-8.4
- 9. SPP-10.0
- 10. SPP-10.1
- 11. SPP-10.11
- 12. OPDP-1 Appendix M - Work Control Revision 0 Page 6 of 7
OPERATIONS DIRECTIVE MANUAL ODM-I.O Conduct Of Operations Appendix M - Work Control SCHEDULE CHANGE FORM
<-A Instructions: Complete the applicable portion of this form and, at a minimum, route to the Unit Managers.
WORK DOCUMENT/SCHEDULED ACTIVITY: SHIFT: 0 1 (Days) DATE:
(Nights)
WORK REJECTION RESPONSIBLE SECTION:
FOREMAN / CRAFTSMAN:
REASON FOR REJECTION1 :
SCHEDULING SUGGESTIONS:
SRO PERFORMING EVALUATION: SM APPROVAL:
SCHEDULE SUGGESTION SUGGESTED ADDITION:
ROUTING: 0 WORK PACKAGE (ORIGINAL) OSM JWWM 2 COUM 1 ',2CMSS IOther:
Note 1: If the rejection is for a PM, review SSP-6.3 Appendix A and B to correct the PM package.
Note 2: WWM/UM are responsible to ensure EMPAC status is updated w/notes on rejected package.
Appendix M -Work Control Revision 0 Page 7 of 7
TVAN STANDARD SPP-7.1 PROGRAMS AND WORK CONTROL PROCESS Rev. 3 PROCESSES Page 9 of 19 H. If the activity does not require a system window, then add to any convenient work window.
The Maintenance organization will plan the work request in accordance with SPP-6.0, "Maintenance and Modifications", SPP-6.1, "Work Order Process Initiation", and MMDP-1, "Maintenance Management System."
J. The implementing organization will review the WO package in parallel with detailed schedule development. The review will consider:
- 1. Personnel protection
- Clearances.
- Radiological protection.
- Confined spaces.
- Industrial Safety.
- 2. Plant Protection/Permits/Limitations
- Flood barriers.
- Security barriers.
- Inoperability of a safety system resulting from support system work.
- 3. Resources
- Parts/Materials/Services. Including reserving and/or staging parts.
- Drawings/References. Obtain copies as needed.
- Manpower/Skills. Review and adjust estimates, crew assignments and personnel qualifications.
- Support. Identify and arrange support items such as scaffolding.
- 4. Impacts to plant safety functions of alterations to the facility or procedures for the duration of the activity. Examples include jumpering of terminals, lifting leads, placing temporary lead shielding on pipes and equipment, removal of barriers, and use of temporary blocks, bypasses, scaffolding, and supports.
3.4 Scheduled Activity Review and Work Authorization 3.4.1 Work Package and Scheduling Review A. Implementing Organization reviews WO package to ensure:
- Work scope fully understood.
& Hold order boundaries adequate for work scope.
- All permits identified.
0 All required pre-testing identified.
0 All support identified.
- Post activity testing adequately identified.
- Appropriate materials identified.
WVAN STANDARD SPP-7.1 PROGRAMS AND WORK CONTROL PROCESS Rev. 3 PROCESSES Page 11 of 19
- Pre-job, test overview, safety briefing are complete.
- Procedures and drawings verified for use.
B. Operations should authorize
- Work orders prior to the shift during which the work activity is scheduled to be performed.
- All activities that are covered within the scope of an established clearance.
3.5 Managing Risk 3.5.1 Risk Thresholds
- 1. For those SSCs modeled in the site PSA, the following risk thresholds are established with approval/ actions described below:
"* Incremental core damage probability (ICDP) greater than 1E-05 should not be entered voluntarily.(RED)
"* ICDP greater than 5E-06 but less than 1E-05, assess non quantifiable factors, establish risk management actions per 3.5.2.1 (ORANGE).
"* lCDP greater than 1E-06 but less than 5E-06, assess non quantifiable factors, establish risk management actions per 3.5.2.1 (YELLOW).
"* ICDP less than 1E-06, no separate risk management plans or approval are required (GREEN).
3.5.2 Risk management actions include the following, as appropriate:
- 1. For those activities requiring risk management actions, those actions include, as appropriate actions to provide risk awareness and control, actions to reduce duration, and actions to reduce magnitude of risk increase. These actions might include:
"* Discussion of activity with operating shift and operator approval of planned evolution
"* Pre-job briefing of maintenance personnel emphasizing the risk aspects of the evolution
"* Presence of appropriate technical personnel for appropriate portions of the activity
"* Pre-staging of parts and materials
"* Walk down tagout and activity prior to conducting maintenance
"* Conduct of training and mock ups to familiarize personnel with the activity
"* Perform activity around the clock
"* Establish contingency plans to restore the out of service rapidly, if needed
"* Minimizing other work in areas that could affect event initiators (e.g.
reactor protection system areas, switchyard, diesel generator rooms, switchgear rooms) to decrease the frequency of initiating events that are mitigated by the safety function served by the out of service SSC
"* Minimize work in areas that could affect other redundant systems such that there is enhanced likelihood of the availability of the safety functions at issue served by the SSCs in those areas
JPM #166 Page 1 of 5 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 166 Survey Map PREPARED/
REVISED BY: Date/
VALIDATED BY: Date/
-Date/
APPROVED BY:
(Operations Training Manager)
CONCURRED: ** Date/
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
" Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM #166 Page 2 of 5 Rev. 0 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION AFFECTE REVISED BY:
D 0 Initial Issue N 9/25/02 All JP Kearney V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM #166 Page 3 of 5 Rev. 0 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task:
Using a Survey Map JA/TA task #: 3430290302 (RO)
K/A Ratings: 2.3.2 (2.5/2.9) 2.3.10 (2.9/3.3)
Task Standard:
Using a radiation survey map and an RWP, the examinee will determine:
- required anti-contamination clothing requirements;
- available stay time for an operator to perform routine surveillance in lower containment; and
- contact reading, 30cm reading, and general area reading in the vicinity of the RCDT.
Evaluation Method : Simulator In-Plant X Performer:
NAME Start Time
"\' Performance Rating: SAT__ UNSAT Performance Time__ Finish Time Evaluator: /
SIGNATURE DATE COMMENTS
JPM #166 Page 4 of 5 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Sequenced steps identified by an "s"
- 2. Any UNSAT requires comments
- 3. Initialize the simulator in IC-10 and leave in FREEZE. Simulator is NOT required to complete this JPM.
- 4. Provide Operator with a calculator and equation sheet if required.
- 5. The simulator is not needed to complete this JPM.
Validation Time: CR. Local 7 min.
Tools/Equipment/Procedures Needed:
Survey #041602-4, RWP # 02027020
References:
Reference Title Rev No.
SPP-5.1 Radiological Controls 4 READ TO OPERATOR DIRECTIONS TO TRAINEE:
I will explain the initial conditions and state the task to be performed. All steps of this JPM shall be simulated. 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return, the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 2 is in Mode 5. You are an extra AUO assigned to perform routine surveillance inside the polar crane wall of U2.
INITIATING CUES:
You are to review the radiological conditions for the area. Using the radiation survey map and RWP provided, determine:
- 1. required anti-contamination clothing requirements;
- 2. maximum available stay time for an operator to perform routine surveillance in lower containment; and
- 3. contact reading, 30cm reading, and general area reading in the vicinity of the RCDT.
JPM 166 Page 5 of 5 Rev. 0 Job Performance Checklist:
SATIUNSAT STFPPISTA NDARn STE./-TAND1R STEP 1.: Determine the required anti-contamination clothing requirements SAT UNSAT STANDARD: Operator determines that work step 2 (OPS INSPECTION) of the RWP applies and determines the following clothing is required: Start Time.__
.modesty clothing
- one pair of cloth booties
- one pair of gloves with cloth inserts
- one pair of coveralls
- one pair shoe covers
- hood Critical Step
- secure wraps for gloves and booties STEP 2.: Determine the available stay time for an operator to perform routine _ SAT surveillance in lower containment.
UNSAT STANDARD: Operator determines that general area radiation inside the polar crane wall is 10 mrem/hr and the dose alarm is set at 100 mrem. Thus the available stay time is 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
Critical Step Stay time = [100 mrem]/[10 mrem/hr] = 10 hrs.
STEP 3.: Determine the contact reading, 30cm reading, and general area reading SAT in the vicinity of the RCDT. UNSAT STANDARD: Operator determines:
contact reading = 3.5 rem/hr 30cm reading = 300 mrem/hr general area reading = 25 mrem/hr Critical Step Stop Time END of JPM
Sequoyah Nuclear Station VSDS Survey Report U2 ELEVATIO N M7*
SO 45 135 fCri AllRil 95 Survey .by: Cagle, TerniL instrument Nos.: 524208,N/A,N/A,N/A Dale _S~u wey # f- SurVey
ý'Survey printed on: 911712002 at: 14:38
Sequoyah Nuclear Plant Unit: 2 Permit Number: 02027020 Revision Number: 0 Page: 1 RADIOLOGICAL WORK PERMIT UNIT 2 LOWER CONTAINMENT BRIEFING REQUIRED QUARTERLY GENERAL DESCRIPTION Status: TERMINATED Start Date: 15-APR-2002 End Date: 14-JUN-2002 Type: SPECIFIC MAP ID: Outage: Y Name: U2C11 PSE: N Task: ROUTINE OPERATIONS AND SURVEILLANCE HP Coverage: INTERMITTENT Authorization Type: ALL ALARA Review Number: 2002-98 Prim*ary WorkDoc:
Person-mrem Estimate: 2000 Person-Hr: s Estimate: 600 Dose Alarm: 100 Dose Rate Alarm: 250 DAC-hrs Tracked: Y Work Area
Description:
Lower Containment All Areas DESCRIPTION OF WORK TO BE PERFORMED IOPS INSPECTIONS AND VALVE ALIGNMENTS.
1 ANTI-CONTAMINATION CLOTHING RZQUIRMENTS 1,2,3 BOOTIES, CLOTH, ONE PAIR 1,2,3 GLOVES, RUBBER, ONE PAIR 1,2,3,4 CLOTH INSERTS 1,2,3,4 COVERALLS, ONE PAIR 1,2,3,4 MODESTY CLOTHING 1,2,3,4 SECURE GLOVES/BOOTIES 1,2,3,4 SHOE COVERS, ONE PAIR 1,2,3,4 HOOD 4 BOOTIES, CLOTH, TWO PAIR 4 PAPER SUIT 4 GLOVES, RUBBER, TWO PAIR DOS IMETRY REQUIREMENTS ELECTRONIC DOSIMETER ITLD BRIEFING REQUIREMETzS PRE-JOB BRIEFING EQUIS I-------- -
WORK STEPS 1 RADCON SURVEYS 2 OPS INSPECTIONS 3 VALVE ALIGNMENTS 4 ENTRY INTO POSTED HIGH CONTAMINATION AREAS
Sequoyah Nuclear plant Unit; 2 Permit Number; 02027020 Revision Number: 0 Page: 2 RADIOLOGICAL WORK pERMIT x UNIT 2 LOWER CONTAINMENT BRIEFING REQUIRED QUARTERLY WOflM INSTRUCTIONS 1 REVIEW SURVEY PRIOR TO ENTRY.
2 NOTIFY RADCON PRIOR TO START OF WORK.
3 DO NOT STAND ON LOWER COMPARTMENT OR CRDM COOLERS, PIPING OR FLEX HOSES.
4 TVA SUPPLIED CLOTHING MAY BE USED INSTEAD OF MODESTY CLOTHING.
5 NOTIFY RADCON IMMEDIATELY IF SPILLS OF CONTAMINATED LIQUIDS OCCUR.
6 FACESHIELD,DISPOSABLE APRON AND SLEEVES MAY BE REQUIRED AS DIRECTED BY RADCON.
7 ENTRY INTO THE S/G LAYDOWN AREAS REQUIRES PERMISSION FROM THE RADCON SHIFT SUPERVISOR.
8 AVOID WORK ON LOOPS WHEN S/G SECONDARY SIDE IS DRAINED AND DURING THE RCS MID-LOOP PERIOD 9 FOLLOW SOP DIRECTIONS FOR REMOVAL OF PROTECTIVE CLOTHING.
10 PLASTIC SUITS WILL BE REQUIRED IN LIEU OF PAPER SUITS WHEN WATER IS PRESENT OR EXPECTED.
11 ESF SUITS MAY BE REQUIRED IN LIEU OF PAPERSUIT.
SPECIAL INSTRUCTIONS 1 INFORMAL TEDE EVALUATION WAS PERFORMED.
HP Coverage: None 2 ACCESS TO THIS RWP INDICATES THE WORKER CAN HEAR THE ED ALARM OR OTHER DOSE WARNING MEASURES HAVE BEEN PROVIDED.
HP Coverage: None APPROVAL Prepared By: CATURNER Approved By:
Approved By:
Final Approval: CDSTEPHE End of RWP
TVAN STANDARD SPP-5.1 PROGRAMS AND RADIOLOGICAL CONTROLS Rev. 4 PROCESSES Page 8 of 33 D. Dosimetry processing equipment, TLDs, pocket chambers, and electronic dosimetry shall be calibrated in accordance with approved procedures.
E. As a minimum, all assigned TLDs are read at least semi annually. Special TLD readouts are performed as necessary.
F. All individuals (facility staff, temporary workers, etc.) who enter the RCA and are expected to receive measurable occupational exposure to radiation from licensed and unlicensed radiation sources under the control of the licensee (i.e., Ž-10 mrem) during the monitoring period shall, as a minimum, be provided with a NVLAP accredited dosimetry device appropriate for the radiological environment.
G. All individuals (facility staff, temporary workers, etc.) who enter the RCA and are not expected to receive measurable occupational exposure to radiation from licensed and unlicensed radiation sources under the control of the licensee (i.e.,
>10 mrem) during the monitoring period shall, as a minimum, be provided with a secondary monitoring device and be escorted by an individual provided with a NVLAP accredited dosimetry device appropriate for the radiological environment.
3.4.1.2 Restricted Area*
Any individual who enters a restricted area (in accordance with 10 CFR 20.1003) should be monitored for occupational exposure to radiation from licensed and unlicensed radiation sources under the control of the licensee, using a NVLAP accredited dosimeter(s), unless it is demonstrated through prospective determination that such monitoring is not necessary. When monitoring is not required workplace monitoring is appropriate. Minors likely to receive, in 1 year, a total effective dose equivalent in excess of 100 mrem shall be individually monitored.
3.4.1.3 Radiologically Controlled Area*
A system shall be implemented to track and control worker radiation exposures. The assigned deep-dose equivalent and shallow-dose equivalent must be for the part of the body receiving the highest exposure.
A. Dosimetry shall normally be worn on the front of the person between the neck and beltline. Itshall be in a clearly visible position. When worn in combination, the secondary dosimetry should be located near the TLD. The TLD beta window side of the TLD shall always face outward. When in a radiation area or high radiation area, the pocket chamber and/or electronic dosimeter should be placed in a location that will allow the user to frequently read the pocket chamber and/or electronic dosimeter.
"TVAN STANDARD SPP-5.1 PROGRAMS AND RADIOLOGICAL CONTROLS Rev. 4 PROCESSES Page 9 of 33 B. Individuals shall inform RADCON (or RSO) when a secondary dosimeter being used for dose control; a pocket chamber reads in excess of % scale or an electronic dosimeter alarms due to integrated dose. The wearer shall report to RADCON (or RSO) to have the pocket chamber reading recorded and the pocket chamber and/or the electronic dosimeter reset.
C. In the case of single dosimeter usage, placement of the dosimeter may be varied at RADCON's (or RSO's) discretion.
Repositioning of the whole-body dosimeter should be considered when it is likely that a location on the whole-body will exceed the chest dose by more than 50 percent, a DDE of more than 300 mrem is expected for the task, and the whole body dose rate is >100 mrem/hr.
D. Ifthe highest dose location on the whole-body is not known, the work area dose-rate gradients make it likely that a location on the whole-body will exceed the chest dose by more than 50 percent, a whole-body dose in excess of 300 mrem is expected during the task, and the whole body dose rates in the immediate work area are at least 100 mrem per hour, then multiple TLD badges should be worn on those whole-body locations that might receive the highest dose. The secondary dosimeter should be located near the whole body part that is likely to receive the highest DDE.
E. The deep-dose equivalent, lens dose equivalent, and shallow dose equivalent may be assessed from surveys or other radiation measurements for the purpose of demonstrating compliance with the occupational dose limits, if the individual monitoring device was not in the region of highest potential exposure, or the results of individual monitoring are unavailable F. Extremity monitors should be provided when an extremity could receive 500 mrem or more and greater than two times the whole body dose, or if it is determined that extremity monitoring is required under 10 CFR 20.1502 3.4.1.4 NVLAP Programs shall be established to obtain and maintain accreditation of dosimetry processing under the NVLAP. The Authorized Representative shall be responsible for this program and shall serve as the official contact between TVA and the accrediting organization.
3.4.1.5 Dose Calculations/Investiaations*
In some instances, due to the loss or damage of a monitoring device or the inability of the monitoring device to measure certain types of radiation, it will be necessary to calculate an individual's dose as appropriate. All calculations shall be documented and included in the employee's personal exposure history record. Permanent radiation exposure records will be handled as sensitive material and transferred to a record custodian.
RWT010 Revision 5 Page 38 of 91 Accumulated Dose Alarm When the accumulated dose alarm set point is reached, the electronic dosimeter generates an audible alarm and the message "Dose Alarm" flashes in the display.
Exit the area immediately and notify RADCON.
Dose Rate Alarm When the dose rate alarm set point is reached, the electronic dosimeter generates an audible alarm and the message "Rate Alarm" flashes in the display.
In addition during the alarm, the LED indicator provides 3 short flashes emitted at a rate of 3 flashes per second. Exit the area immediately and notify RADCON.
If any of the following is displayed on the ED, leave the area and notify RADCON.
A) The window is blank.
B) The window is reading "pause" when the dosimeter should be on C) The window is reading "DF BAT" D) The window is reading "BA LO" Screen aldo35 Wearing Dosimetry Explain how to wear dosimetry devices properly Where do I Wear it?
including placement.
Dosimetry should be worn on the FRONT part of the body between the WAIST and NECK with the beta window of the Thermoluminescence Dosimeter (TLD) facing away from the body (clip toward body) and be located next to the Electronic dosimeter (ED).
When in contaminated areas, wear the TLD inside the coveralls and clip the ED to either upper pocket. The digital readout may face in either direction. The ED may be required to be worn on the outside of the coveralls during entries to High Radiation areas.
Screen aldo36 How do I Wear it?
trn2 cr 99-0006 body)
Explain how to wear The beta window of the TLD should face away from the body (clip toward dosimetry devices properly and be located next to the ED.
including placement &
orientation.
RWT010 Revision 5 Page 72 of 91 Screen rwp31 SURVEY MAPS As mentioned earlier, most radiation work permits reference survey maps.
and provides Screen rwp32 A survey map contains a drawing of the area that was surveyed such as local dose rates, contamination levels, detailed radiological information radiological boundaries/postings, etc.
the use of Screen rwp38 Different types of information on the survey maps are noted through trn2 cr 99-0067 symbols and/or designators (may vary from site to site):
trn2 cr 99-0065 is shown trn2 cr 99-0069
"* Postings/barriers/areas are shown often by a solid line.Smear location by a number in a circle and level of contamination is in units of dpm/100cm2 .
Extract information from three a survey map. "* Dose rates are shown in units of mrem/hr unless otherwise noted. When together, either in a box or separated by slash marks, numbers are displayed whole body the first number is the contact dose rate, the second number is the dose rate.
(30 cm) dose rate and the third number is the general area (1 meter) general area dose
- Single numbers which are underlined or in boxes indicate rates.
- Air sample location is shown by a number inside a triangle (in cpm)
- The designations HS (Hot Spot), AWA (Step-Off-Pad) may be used to designate these areas on survey maps.
condition of "Screenrwp39 A survey map is another tool that shows you, in detail, the radiological certain work areas. Consider them when conducting pre-job briefs.
levels Screen quiz3 QUESTION: This document shows, in detail, local dose rates and contamination trn2 cr 99-0083 in a particular work area:
Survey Map or Radiation Work Permit or Radiological Posting that was surveyed Screen quiz3a ANSWER: Survey Map. Survey maps contain drawings of the area and provides detailed radiological information.
JPM 156 Page 1 of 12 Rev. 1 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 156 Monitor Status Trees - Degraded Core Cooling PREPARED/
REVISED BY: Date/
- Date/
VALIDATED BY:
APPROVED BY: Date/
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
- Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM 156 Page 2 of 12 Rev. 1 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION AFFECTED REVISED BY:
0 New JPM Y 2/15/01 All SR Taylor pen/ink Added setup for IC-86 and minor changes N 12/17/01 4 L. Pauley to setup. Updated K/As.
1 Incorporated pen/ink change N 8/22/02 4 J P Keamey V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM 156 Page 3 of 12 Rev. 1 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task: Monitor Status Trees and Identify Degraded Core Cooling Conditions Requiring Implementation FR-C.2 3110450601 (RO) 3110460602 (SRO) 3520950305 (STA)
JA/TA task #:
K/A Ratings:
(3.4/4.2) E14EA2.1 (3.3/3.8) E08EA2.1 (3.4/4.2)
E06EA2.1 (3.4/4.3) E05EA2.1 (3.4/4.4) E07EA2.1 (3.2/3.4)
E04EA2.1 E10EA2.1 (3.3/3.5) E13EA2.1 (2.9/3.4) E15EA3.1 (2.7/3.2)
E16EA2.1 (2.913.3) and determine Task Standard: Monitor Status Trees and identify Orange Paths to FR-C.2, FR-P.1, and FR-Z.1 that FR-C.2 is the highest priority and should be implemented.
Evaluation Method: Simulator X In-Plant Performer:
NAME Start time
_ UNSAT Performance Time Finish time Performance Rating : SAT -
Evaluator: /
SIGNATURE DATE COMMENTS
JPM 156 Page 4 of 12 Rev. 1 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps identified by the Words "Critical Step" in the SAT/UNSAT Column.
- 2. Sequenced steps identified by an "s"
- 3. Any UNSAT requires comments
- 4. Initialize Simulator to IC #93 (100% If IC-86 is not available THEN Initialize to IC 12 EOL) and enter the actions below to set up the JPM
- 5. Activate malfunction cs0la (Containment spray Pump IA Trip). Pull to lock and Tag Containment Spray pump 1A-A.
- 6. Activate Malfunction thola @ 100% (LOCA Hot Leg break Loop 1)
- 7. Ensure power on 1-FCV-63-1 with remote function RHR14
- 8. Control AFW as necessary by perform EA-3-8 and CLOSE ALL AFW flow to #4 SG when the #4 SG NR level is 5%. This will ensure one SG level is < 25% during performance of the Status Trees.
- 9. Place simulator in run until auto sump swapover is complete, then complete the manual ECCS swapover actions of ES-1.3 (Containment Spray alignment to sump is not required). Trip RCPs when Phase B occurs.
- 10. After Sump swapover is complete, activate Malfunctions eg02b (DIG 1 B-B Trip), ed0l (Loss of Offsite Power), RH01A (RHR pump 1A Trip). Lock out 1A CCP and IA SI pump.
Acknowledge alarms and clear white lights.
NOTE: The loss of power will cause the Saturation Margin Alarm to go DARK (XA-55-4B).
- 11. Run simulator until RVLIS Lower Range is less than 40%, and containment pressure >2.81 psid.
Ensure SR is re-instated and at least 1 S/G NR Level is >25% and at least 1 S/G NR level is
<25%. Also, verify that at least 1 Tcold is less than 250 and all Tcold channels are >191 OF.
- 12. Acknowledge alarms and place simulator in Freeze when all SR and IR range Startup Rate indicators show zero or Negative SUR. The simulator will remain in freeze during performance of the JPM.
- 13. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR 6 min. Local Tools/Equipment/Procedures Needed: FR-0, Status Trees.
REFERENCES:
Reference Title Rev No.
A. FR-0 Status Trees 11 Task Number Task Title Cont TRN 3110450601 Monitor Status Trees to ensure that the Critical Safety Functions are maintained Y 3110460602 Monitor Status Trees to ensure that the Critical Safety Functions are maintained Y 3520950305 Monitor status trees to ensure that the critical safety functions are maintained Y
{LICENSE PROGRAM)
JPM 156 Page 5 of 12 Rev. 1 READ TO OPERATOR Directions to Trainee:
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. All steps shall be simulated for this task, the simulator will remain in freeze during performance of this JPM. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Approximately 30 minutes ago, Unit I was at 100% power EOL with the 1A Containment Spray Pump Tagged for maintenance when a Large Break LOCA occurred. Just after ECCS pump sump swapover was completed per ES-1.3, a total loss of offsite power occurred and Diesel Generator 1 B-B failed.
Subsequently RHR pump IA tripped on overcurrent. Alarms have been acknowledged and pumps have been placed in pull-to-lock as appropriate. The Crew is currently in E-1. Typical crew actions to this point have been performed.
INITIATING CUES:
You are an RO and have been assigned to monitor status trees. Monitor the Status trees for the current conditions and inform the Unit Supervisor of the results.
JPM 156 Page 6 of 12 Rev. 1 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD T-Perform the Subcriticality Status Tree (F-0.1) SAT STEP 1:
UNSAT NOTE: The following steps are from performance of the subcriticality Status Tree.
Start Time Power Range less than 5%. SAT STEP 2:
UNSAT STANDARD: Operator checks power range less than 5% on 1-M-13 Power Range Drawer Indicators (1-XI-92-5005B, 5006B, 5007B, &
5008B) and determines Power Range is less than 5%.
Intermediate Range SUR Zero or Negative. SAT STEP 3:
UNSAT Cue: If simulatorwas not frozen with Zero or Negative SUR cue that it is when checked STANDARD: Operator checks Intermediate Range SUR Zero or Negative Using 1-M-13 Comparator and Rate Drawer (1-XX-92-5041)
Indicator with the Startup Rate Selector Switch to in both the N35 and N36 positions and determines it is Zero or Negative.
Source Range Reinstated. SAT STEP 4:
UNSAT STANDARD: Operator checks Source Range Reinstated by observing 1-M-13 Source Range indicators (1-XI-92-5001 B & 5002B) responses and determines it is Reinstated.
STEP 5: Source Range SUR Zero or Negative. SSAT UNSAT Cue: If simulatorwas not frozen with Zero or Negative SUR cue that it is when checked.
STANDARD: Operator checks Source Range SUR Zero or Negative Using 1 M-13 Comparator and Rate Drawer (1-XX-92-5041) Indicator with the Startup Rate Selector Switch to in both the N31 and N32 positions and determines it is Zero or Negative.
JPM 156 Page 7 of 12 Rev. 1 Job Performance Checklist:
STEPISTANDARD SAT/UNSAT STEP 6: Perform the Core Cooling Status Tree (F-0.2) __ SAT UNSAT NOTE: The following steps are from performance of the Core Cooling Status Tree.
STEP 7: Core Exit thermocouples less than 12000 F. SAT UNSAT NOTE: Operator must use the Exo Sensor "Next" button to see page 2 of some TIC quadrants. Quadrants 3 & 4 on 1-XI-94 101 have 2 pages, Quadrants I & 2 on 1-XI-94-102 have 2 pages STANDARD: Operator Checks thermocouples in all quadrants Exo-sensors (1 XI-94-101 & 102) on 1- M-4 using the Quad buttons to determine if 5 T/Cs have exceeded 12000 F as follows: One TIC near the core center and the hottest TIC in each quadrant (this can be verified by ensuring no TICs are above the limit without identifying a specific T/C near the core center). The Operator should determine that the limit has not been exceeded.
STEP 8: RCS Subcooling Based on Core Exit TIC greater than 40 0F. __ SAT UNSAT STANDARD: Operator Checks Subcooling on both Exo sensor"Margin" Displays (1-XI-94-101 & 102) on 1-M-4 to determine if subcooling is greater than 40tF. The Operator should determine that subcooling is not greater than 40 0F.
STEP 9: At least one RCP running. __ SAT UNSAT STANDARD: Operator Checks RCPs Running and determines that No RCPs are running.
JPM 156 Page 8 of 12 Rev. 1 Job Performance Checklist:
\12 STEP/STANDARD SAT/UNSAT STEP 10: Core Exit T/Cs Less than 7000F SAT UNSAT NOTE: Operator must use the Exo Sensor "Next" button to see page 2 of some T/C quadrants. Quadrants 3 & 4 on 1-XI-94 101 have 2 pages, Quadrants I & 2 on 1-XI-94-102 have 2 pages STANDARD: Operator Checks thermocouples in all quadrants on Exo sensors (1-XI-94-101 & 102) on 1-M-4 using the Quad buttons to determine if 5 TICs have exceeded 700 0 F as follows: One TIC near the core center and the hottest TIC in each quadrant (this can be verified by ensuring no TICs are above the limit without identifying a specific T/C near the core center). Operator should determine that core exit TIC are also less than 700 OF.
STEP 11: RVLIS Lower Range Greater than 40%. SAT UNSAT STANDARD: Operator Checks both PAM RVLIS Lower Range Channels (1-LI 68-368 & 371) on 1-M-4. Operator should determine RVLIS is not greater than 40% and identify that an Orange Path to FR-C.2 Critical Step exists. However, operator should continue checking status trees to ensure Red path does not exist on another status tree.
STEP 12: Perform the Heat Sink Status Tree (F-0.3) SAT UNSAT NOTE: The following steps are from performance of the Heat Sink Status Tree.
STEP 13: Narrow range level in at least one S/G greater than 10% [25% __ SAT ADV].
UNSAT NOTE: Adverse Setpoint will be required.
STANDARD: Operator Checks S/G Narrow Range level on all PAM S/G NR level instruments on 1-M-4 and determines at least one S/G NR Level is greater than 25%.
JPM 156 Page 9 of 12 Rev. 1 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 14: Pressure in All S/Gs less than 1117 psig. __ SAT UNSAT STANDARD: Operator Checks S/G Pressure on all PAM S/G Pressure instruments on 1-M-4 and determines all S/Gs are less than 1117 psig.
STEP 15: Narrow Range level in all S/Gs less than 81%. __ SAT UNSAT STANDARD: Operator Checks S/G Narrow Range level on all PAM S/G NR Level instruments on 1-M-4 and determines that all S/G levels are less than 81%.
STEP 16: Pressure in All S/Gs less than 1064 psig. SAT UNSAT STANDARD: Operator Checks S/G Pressure on all S/G PAM Pressure instruments on 1-M-4 and determines all S/Gs are less than 1064 psig.
STEP 17: Narrow Range level in all S/Gs greater than 10% [25% ADV]. SAT UNSAT NOTE: Adverse Setpoint will be required.
STANDARD: Operator Checks S/G Narrow Range level on all PAM S/G NR level instruments on 1-M-4 and determines that at least one S/G level is not greater than 25% and notes that a yellow path to FR H.5 exists.
STEP 18: Perform the Pressurized Thermal Shock Status Tree (F-0.4) __ SAT UNSAT NOTE: The following steps are from performance of the Pressurized Thermal Shock Status Tree.
JPM 156 Page 10 of 12 Rev. 1 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD STEP 19: All T-Colds dropped less than 1i00F in the last 60 minutes. __ SAT SUNSAT STANDARD: Operator Checks all RCS PAM T-Cold instruments on 1-M-5 (1 TI-68-18, 41,60, and 83) and determines that All T-Colds have not dropped less than 1 000 F in the last 60 minutes. (i.e. Any T Cold has exceeded the Cooldown limit)
STEP 20: All RCS Pressure Vs T-Cold points to the right of limit A on __ SAT Curve 3.
UNSAT STANDARD: Operator should use the lowest RCS PAM T-Cold on 1-M-5 (1 TI-68-18, 41,60, and 83) and highest RCS pressure reading from Exo sensors or PAM pressure instruments on 1-M-6 (1-PI 68-66A, 62, & 69) and determine that Limit A has not been exceeded on curve 3.
__SAT STEP 21: All T-Colds Greater than 250°F.
___ UNSAT STANDARD: Operator Checks All RCS PAM T-Cold instruments on 1-M-5 (1 TI-68-18, 41,60, and 83) and determines that All T-Colds are not Greater than 2500 F and identifies that an Orange path to FR- Critical Step P.1 exists. However, operator should continue checking status trees to ensure Red path does not exist on another status tree.
STEP 22: Perform the Containment Status Tree (F-0.5) __ SAT IUNSAT NOTE: The following steps are from performance of the Containment Status Tree.
STEP 23: Containment Pressure Less than 12.0 PSID. SAT SUNSAT STANDARD: Operator Checks PAM Containment pressure instruments on 1 M-6 (1-PDI-30-45 & 44) and determines that Containment Pressure is Less than 12.0 PSID.
JPM 156 Page 11 of 12 Rev. 1 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD I
STEP 24: Containment Pressure Less than 2.81 PSID. SAT UNSAT Examiner Note: Operator may report highest Orange path to US before checking inventory since the highest path available in inventory is Yellow. Critical Step STANDARD: Operator Checks PAM Containment pressure instruments on 1 M-6 (1-PDI-30-45 & 44) and determines that Containment Pressure is not Less than 2.81 PSID and identifies that an Orange path to FR-Z.1 exists. However, operator should continue checking status trees.
STEP 25: Perform the Inventory Status Tree (F-0.6) SAT UNSAT NOTE: The following steps are from performance of the Inventory Status Tree.
STEP 26: Pressurizer Level Less than 92% SAT UNSAT STANDARD: Operator Checks PAM Pressurizer level instruments on 1-M-4 (1-PI-68-333A, 335A, & 320) and determines that Pressurizer Level is Less than 92%.
STEP 27: Pressurizer Level Greater than 17%. SAT UNSAT STANDARD: Operator Checks PAM Pressurizer level instruments on 1-M-4 (1-PI-68-333A, 335A, & 320) and determines that Pressurizer Level is not Greater than 17% and notes that a yellow path to FR-l.2 exists.
JPM 156 Page 12 of 12 Rev. 1 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD r-Inform the Unit I Unit Supervisor that status trees have been SAT STEP 28:
monitored and that Orange paths exist on the Core cooling (to UNSAT FR-C.2), PTS (to FR-P.1) and Containment (to FR-Z.1) Status trees requiring transition to FR-C.2 the highest priority path.
Stop Time Cue: USISRO acknowledges the report.
Critical Step NOTE: Operator may also report Yellow paths on Heat Sink (FR H.5) and Inventory (FR-L.2). Reporting the yellow paths to the US/SRO is optional.
STANDARD: Operator Informs the Unit 1 Unit Supervisor that status trees have been monitored and that Orange paths exist on the Core cooling (to FR-C.2), PTS (to FR-P.1), and Containment (to FR Z.1) Status trees requiring transition to FR-C.2 the highest priority path.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL FUNCTION RESTORATION PROCEDURE FR-0 STATUS TREES Revision 11 QUALITY RELATED PREPARED/PRO OFREAD BY: RILEY WRIGHT DATE: 7/18/95 RESPONSIBLE 0)RGANIZATION: OPERATIONS APPROVED BY: ORIGINAL SIGNED BY W. R. LAGERGREN DATE: 8/24/95 EFFECTIVE DATE: 9/6/95 VERIFICATION DATE: 7/27/95 VALIDATION DATE: 7/30/95 REVISION DESCRIPTION: Revised to incorporate WOG ERG Revision 1 B.
( /
(
Subcriticality SQN FR-0 F-0.1
- Page 2 of 11 Rev. 11 GO TO FR-S.1 Wý GO TO FR-S.1 GO TO INTERMEDIATE RANGE FR-S.2 SUR MORE NEGATIVE THAN -0.2 DPM CSF SAT GO TO FR-S.2 CSF SAT
(7 SQN Core Cooling FR-0 F-0.2 Page 3 of 11 Rev. 11 GO TO FR-C.1 GO TO FR-C.1 0 GO TO 0
NOTE 1: > FR-C.2 RED PATH REQUIRES 90 090)
AT LEAST 5 TICs GREATER THAN THE APPLICABLE LIMIT AS FOLLOWS:
5 EXOSENSORTICs (ONE TIC NEAR CORE CENTER AND r 01
ýR GO TO FR-C.2 HOTTEST TIC IN EACH QUADRANT AS DETERMINED GO TO BY THE STA). FR-C.3 RVLIS DYNAMIC RANGE 0 :00 GO TO FR-C.2 GREATER THAN APPLICABLE VALUES IN TABLE 2 GO TO FR-C.3 RCS SUBCOOLING BASED ON CORE EXIT TiCs GREATER THAN 40°F a Wm N w9=1 a WM= m Ewa a GOV, CSF SAT
(K I, CORE C > LING SQN F-0.2 FR-0 Table 2 Page 4 of 11 Rev. 11 NOTE: RVLIS indication greater than values listed below indicated average system void fraction less than 50%.
RVLIS DYNAMIC RANGE RUNNING RCP CONFIGURATIONS LI-68-367 LI-68-370
(%) (%)
Loop 1 16 10 Loop 2 10 10 Loop 3 10 16 Loop 4 10 10 Loops 1 and 2 23 15 Loops 1 and 3 23 23 Loops 1 and 4 23 15 Loops 2 and 3 15 23 Loops 2 and 4 15 15 Loops 3 and 4 15 23 Loops 1, 2, and 3 30 30 Loops 1, 2, and 4 30 24 Loops 1, 3, and 4 30 30 Loops 2, 3, and 4 24 30 ALL RCPs RUNNING 44 44
-(7 K
- "SQN \
Heat Sink FR-0 Page 5 of 11 F-0.3 Rev. 11 S~GO TO TOTAL FEEDWATER FR-H.1 FLOW TO S/Gs GREATER THAN 440 GPM SI~s..........
- D GO T NARROW RANGE _ _ _ _ _Go TO NO FR-H.2 LEVEL IN AT LEAST *S IG s.............
ONE SIG GREATER THAN 10%
[25% ADV] YES GO TO
)WRAGE N W RANGE *~*'1 R-H.3 IN ALL SIGs rHAN 81%
YES NO GO TO PRESSURE IN ALL SIGs FR-H.4 LESS THAN 1064 PSIG NARROW RANGE LEVEL IN ALL SIGs NO .FR-O.T GREATER THAN 10%
[25% ADV]
\.
SQN Pressurized Ihermal Shock FR-0 F-0.4 Page 6 of 11 Rev. 11 GO TO FR-P.1 ALL RCS PRESSURE vs T-COLD POINTS TO RIGHT OF LIMIT A ON CURVE 3 GO TO FR-P.1 ANY T-COLD EXCEEDED U< MQ 0 COOLDOWN LIMIT GO TO FR-P.2 CSF SAT ALL T-COLDs DROPPED LESS THAN 100°F IN LAST 60 MINUTES .g 0 GO TO FR-P.1 GO TO FR-P.2 RCS PRESSURE LESS THAN COLD OVERPRESSURE LIMIT ALL T-COLDs WITHIN ON CURVE 4 (CURVE 5)
COOLDOWN LIMIT 2 M& GA CSF SAT 9 WAV H R RW.l W ' CSF SAT
7-(
Pressurized Thermal Shock SQN F-0.4 FR-0 Curve 3 Page 7 of 11 Rev. 11 PTS Limits Curve 3000 2500 2000 a,
U)>
1500 U) 1000 500 0
RCS Temperature - 0 F SON-S0S2-O1 1O-R3-YO3
( I)
Pressurized thermal Shock SQN F-0.4 FR-0 Curve 4 Page 8 of 11 Rev. 11 Cold Overpressure Protection Curve - Unit 1 3000 3000 2500 b.
CL 2000 a,
1500 (I,
(3 1000 500 U,
a.
C C
-4 0
100 200 300 400 500 200 F RCS Temperature - 0 F SQN-SQS2-0110-R3-Y04
/' 7I, Pressurizea, , nermal Shock SQN F-0.4 FR-0 Curve 5 Page 9 of 11 Rev. 11 Cold Overpressure Protection Curve - Unit 2 3000 3000 2500 2500 0k.
2000 2000 ci a
1500 1500 a
a-*
1000 1000
= fin 500 S
v--
0Z 0
0 I [100 200 300 400 500 200 F RCS Temperature - 0 F SGN-SQS2-O11O-R3-Y08
4-Inventory SQN FR-O F-0.6 Page 11 of 11 Rev. 11 G 0TO I
RVLIS UPPER PLENUM NO
~GO TO FR-.3 I RANGE IN IDLE LOOP(s)
GREATER THAN 98%
YE GO TO I__ _ ~ FRI WGO TO FR-I.2 RCP 1 OFF NO WW G CSF SAT OR RCP 3 OFF YES i NO .~ ' I' FR-I.3 CSF SAT
JPM # 164 Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 4,7 JPM # 164 Classify the Event per the REP (LOCA with Significant Fuel Failure and Potential Loss of Containment Integrity)
PREPARED!
REVISED BY: Date/
VALIDATED BY: Date/
APPROVED BY: Date/
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM # 164 Page 2 of 10 Rev. 0 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION j ___ AFFECTED REVISED BY:
0 New Y 10/1/02 All J P Kearney V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM # 164 Page 3 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT SRO JOB PERFORMANCE MEASURE Task:
Classify the Event per the REP (LOCA with Significant Fuel Failure and Potential Loss of Containment Integrity)
JA/TA task #: 3440030302 (SRO) 3440190302 (SRO)
K/A Ratings:
2.4.29 (2.6/4.0) 2.4.38 (2.2/4.0) 2.4.44 (2.1/4.0) 2.4.30 (2.2/3.6) 2.4.40 (2.3/4.0) 2.4.37 (2.0/3.5) 2.4.41 (2.3/4.1)
Task Standard:
The event is classified as a GENERAL EMERGENCY based on Loss of Both Fuel Clad and RCS Barriers, and Potential Loss of Containment. The event's protective action recommendation is Recommendation 1 based on a projected dose at greater than 5 miles.
Evaluation Method : Simulator X In-Plant
- This JPM will be simulated Performer:
NAME Start Time
'ý Performance Rating: SAT UNSAT Performance Time Finish Time Evaluator: /
SIGNATURE DATE COMMENTS
JPM # 164 Page 4 of 10 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Sequenced steps identified by an "s"
- 2. Any UNSAT requires comments
- 3. Initialize the simulator in IC-10 and leave in FREEZE.
- 4. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
- 5. Caution: DO NOT LET THE EXAMINEE FAX THE NOTIFICATION FORM Validation Time: CR. 17 mins Local Tools/Equipment/Procedures Needed:
EPIP-1 EPIP-5
References:
I Reference Title Rev No. I
- 1. EPIP-1 Emergency Plan Initiating Conditions Matrix 33
- 2. EPIP-5 General Emergency 29 PROVIDE THIS AS HANDOUT AND REVIEW WITH OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps of this JPM shall be simulated. 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you The simulator is NOT representative of the scenario you are about to address.
INITIAL CONDITIONS:
- 1. Approximately 50 minutes ago, Unit 1 experienced an AUTO SI from a small RCS leak which quickly escalated to a LOCA and a high containment pressure.
- 2. RCS pressure has stabilized at 600 psig. The CLAs are injecting.
- 3. The ONLY ECCS pump available and in service is the 1 B-B RHR pump. The last of the other ECCS pumps tripped off shortly after the RCPs were removed from service per procedure.
- 4. The break size is such that partial core uncovery occurred during saturation blowdown at -1100 psi, prior to CLAs starting injection.
- 5. Containment hydrogen concentration is 6% as indicated on the H2 Analyzers (just completing 30 minute analyze mode).
- 6. Containment pressure is 1.8 psi and relatively stable.
- 7. Unit 2 is at 100% RTP and stable.
- 9. CECC EPIP-9, "Emergency Environmental Radiological Monitoring Procedures" has been implemented.
INITIATING CUES:
- 1. You are the US and have assumed the SED position.
- 2. The STA reports a RED path condition exists on Core Cooling.
- 3. The operating crew is taking appropriate actions per the emergency procedures, they are currently in E-1 at Step 15 and are now transitioning to FR-C.1.
- 4. You are to classify and document this event per the appropriate EPIP AND perform all required actions.
JPM # 164 Page 5 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP/SANDAT SAT STEP 1.: Refers to EPIP-1 to determine level of event.
UNSAT STANDARD: Operator refers to EPIP-1, Section 1, Fission Product Barrier Matrix.
Operator determines that they have met the conditions of 1.1.1 Loss, "Core Cooling Red" Critical Step 1.2.2 Loss "RCS leak results in subcooling <400 F" 1.3.2 Potential loss, "Cntmt H2 increases to greater >4%"
Task Start Utilizing "Emergency Class Criteria", operator determines the need to Time declare a General Emergency based on Loss of two barriers and Potential loss of third barrier.
STEP 2.: Implements EPIP-5 GENERAL EMERGENCY. __ SAT Enter time Declaration made: __ UNSAT Time from Task Acceptance to Declaration:
STANDARD: Operator Implements a GENERAL EMERGENCY per EPIP-5, Section 3.1.
Operator should classify the event within 15 minutes of the time the task was accepted. Declaration Time should be consistent with the time the examinee transitions from EPIP-1 to EPIP-5.
STEP 3.: ANNOUNCE to the operating crew: "A GENERAL EMERGENCY has been __ SAT declared based on (Core Cooling Red Path) AND (RCS leak results in subcooling <400 F) AND (Cntmt H2 increases to greater >4%). I will be __ UNSAT the Site Emergency Director".
STANDARD: Operator makes announcement to the crew.
STEP 4.: IF the Emergency Paging System (EPS) has not been previously initiated, __ SAT THEN activate EPS.
UNSAT Cue: If requested, the clerkIMSS will activate/monitorthe EPS.
STANDARD: Operator utilizes "Touch Screen" or directs the Clerk/MSS to activate the Critical Step EPS.
STEP 5.: IF EPS fails, THEN ..... SAT UNSAT STANDARD: Operator N/As this step
JPM # 164 Page 6 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SATIUNSAT STEP 6.: ANNOUNCE to plant personnel SAT "ATTENTION PLANT PERSONNEL. ATTENTION PLANT PERSONNEL. UNSAT A GENERAL EMERGENCY HAS BEEN DECLARED BASED ON LOSS OF 2 FISSION PRODUCT BARRIERS WITH A POTENTIAL LOSS OF 3RD BARRIER, AFFECTING UNIT 1. ALL TSC AND OSC PERSONNEL REPORT TO THE EMERGENCY FACILITIES IMMEDIATELY." Repeat the announcement.
STANDARD: Operator makes the PA announcement.
STEP 7.: If personnel accountability has not been previously initiated, THEN __ SAT
[a] Notify Security Shift Supervisor to implement EPIP-8.
[b] ACTIVATE emergency sirens for personnel assembly. __ UNSAT Cue: Role play as Security Shift Supervisor and acknowledge.
STANDARD: 1. Operator calls Security Shift Supervisor to implement EPIP-8.
- 2. Operator activates the emergency sirens. Critical Step STEP 8.: EVALUATE the appropriate protective actions (page 17). SAT UNSAT Cue: When asked "Rx coolant activity priorto the event was 0.5 micro curies per gram Dose EquivalentIodine 131'1 Cue: If Operatorchecks Cntmt HI Rad monitors, tell operator "There is no significantchange in theirreadings".
Cue: When asked, "The measured dose at 5 miles is 4.5E6 micro curriesper cc Iodine-131'; Critical Step STANDARD: Operator determines from page 17, logic chart in EPIP-5, that appropriate protective action recommendation is RECOMMENDATION 1.. This should be done on the notification form in the next JPM step.
JPM # 164 Page 7 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 9. Complete the GE Notification Form (page 18) and notify the Operations __ SAT Duty Specialist (ODS).
UNSAT NOTE: Enter time call is made to the ODS:
Critical Step Time from Declaration (step 2) to ODS Notification:
- a. This is a Real Event
- b. Their name, Shift Manager at SQN Plant.
- c. General Emergency declared on UNIT 1
- d. EAL No. LOSS 1.1.1, LOSS 1.2.2, and Potential LOSS 1.3.2.
- e. Brief description of incident: [Core Cooling Red Path AND RCS leak results in subcooling <40°F AND Cntmt H2 increases to greater >4%].
- f. Radiological Conditions [Airborne Release Offsite]
- g. Event Declared: [Time and Date]
- h. Protective Action Recommendation: [1 - Evacuate 2 mile radius and 10 miles downwind and shelter remainder of 10 mile EPZ].
- i. Wind speed at 46 meters [5 mph] AND wind direction at 46 meters
[Southwest at 235 degrees]
- j. Ask the ODS to repeat the information he has received to ensure accuracy.
Cue: 1. When examinee on proper1CS screen, 'Wind speed at 46 meters is 5 mph '"
- 2. When examinee on properICS screen, 'Wind direction at 46 meters is Southwest at 235 degrees".
- 3. Role play as the ODS andacknowledge report.
STANDARD: Operator should notify the ODS within 5 minutes after declaration is made giving the above information from page 18.
STEP 10.: FAX Notification Form (page 18) to the ODS. - SAT Cue: The supportA UO will send the FAX for you. __ UNSAT Caution: DO NOT LET THE EXAMINEE FAX THE FORM STANDARD: Operator addresses FAXing the Notification Form to the ODS.
STEP 11.: IF ODS CANNOT be contacted within 10 minutes of declaration.... __ SAT UNSAT STANDARD: Operator N/As this step and continues.
JPM # 164 Page 8 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEIP 12.: NOTIFY RADCON Shift Supervisor that "A GENERAL EMERGENCY HAS SAT BEEN DECLARED BASED ON [CORE COOLING RED PATH AND RCS UNSAT LEAK RESULTS IN SUBCOOLING <40°F AND CNTMT H2 INCREASES TO GREATER >4%], AFFECTING UNIT 1".
NOTE: This notification may be delegated to an extra SRO/RO.
Cue: As the Radcon Shift Supervisor,acknowledge the report Cue: If delegated,reportthat the notification has been completed STANDARD: Operator makes the notification and directs the Radcon Shift Supervisor to implement EPIP-14 AND CECC EPIP-9.
I.
STE P 13.: NOTIFY Chemistry Shift Supervisor that "A GENERAL EMERGENCY HAS SAT BEEN DECLARED BASED ON [CORE COOLING RED PATH AND RCS UNSAT LEAK RESULTS IN SUBCOOLING <400F AND CNTMT H2 INCREASES TO GREATER >4%]. AFFECTING UNIT 1".
NOTE: This notification may be delegated to an extra SRO/RO.
Cue: As the Chemistry Shift Supervisor,acknowledge the report.
Cue: If delegated,report that the notification has been completed.
STANDARD: Operator makes the notification and directs the Chemistry Shift Supervisor to implement EPIP-14.
t STEP 14.: MONITOR radiation monitors. When indication of an unplanned SAT radiological release, Then perform Dose Assessment.
UNSAT Cue: When examinee uses ICS or RM indication to determine radiation levels, cue the operator: "All RM reading - normal and Fieldsurveys are in progress".
STANDARD: 1. Since a radiological release is indicated by the field surveys, the Operator directs the Chemistry Shift Supervisor to perform a dose assessment per EPIP-1 3.
- 2. Operator should use either ICS or the RP-30 modules to determine effluent radiation conditions. No additional classifications determined.
- 3. Operator should provide the Chemistry Shift Supervisor the following:
Type of Event: LOCA Release Path: Unknown or Containment Leakage Expected Duration: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
JPM # 164 Page 9 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT
- STEP 15.: IF there are any personnel injuries THEN, IMPLEMENT EPIP-10. __ SAT UNSAT Cue: There have been no reports of personnelinjury.
STANDARD: Operator should N/A this step.
STEP 16.: IF there has been a security threat THEN, NOTIFY Security Shift __ SAT Supervisor to IMPLEMENT SSI-1.
UNSAT Cue: There have been no reports of a security threat STANDARD: Operator should N/A this step.
STEP 17.: Notify the Plant Management in accordance with SPP-3.5. __ SAT UNSAT NOTE: Activation of the EPS will make the Plant Management aware of the REP actuation, however administrative procedures require notification.
NOTE: This notification may be delegated to an extra SRO/RO.
Cue: As the NRC, acknowledge the report.
Cue: If delegated,report that the notification has been completed STANDARD: Operator contacts Plant Management and informs him of the REP classification and provides GE information from page 18.
STEP 18.: Notify the NRC via ENS in accordance with SPP-3.5. SAT Note: This notification may be delegated to an extra SRO/RO. __ UNSAT Cue: As the NRC, acknowledge the report. Critical Step Cue: If delegated,reportthat the notification has been completed Time of STANDARD: Operator should notify the NRC (headquarters) as soon as practicable, but Notification:
within 1 Hr. of declaration of the event. Operator provides GE information from page 18.
JPM # 164 Page 10 of 10 Rev. 0 Job Performance Checklist:
SAT/UNSAT STEPISTANDARD SAT
" STEP 19.: MONITOR plant conditions AND EVALUATE using EPIP-1 ......
UNSAT Cue: if operatorbegins Monitoring plant conditions, THEN tell him "The TSC is staffed and will COMPLETE GE follow-up Form'.
Stop Time:
STANDARD: Operator addresses completing GE follow-up Form (page 19).
End of JPM
JPM 150 Page 1 of 9 Rev. 1 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM 150 Flush Unit 1 Blender Piping Original Signatures on File PREPARED/
REVISED BY: Date/
- Date/
VALIDATED BY:
Date/
APPROVED BY:
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
- Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM 150 Page 2 of 9 Rev. 1 NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION AFFECTED REVISED BY:
0 New Y 10/7/98 All JP Kearney pen/ink 0-SO-62-7 rev change only N 9/21/99 4 SR Taylor pen/ink 0-SO-62-7 rev change only N 8/28/00 4 SR Taylor 1 Incorporated pen/ink changes; revised N 8/21/02 All J P Kearney per recent revisions to O-SO-62-7; no impact on JPM flow (Y or N).
V - Specify ifthe JPM change will require another Validation See cover sheet for criteria.
JPM 150 Page 3 of 9 Rev. I SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task: Flush Unit 1 Blender Piping JA/TAtask#: 0040450101 (RO)
K/A Ratings: 004A2.06 (4.2/4.3) 004A2.25 (3.8/4.3) 004A4.10 (3.6/3.2)
Task Standard: Complete flush of Blender piping per 0-SO-62-7, Boron Concentration Control, section 8.8.
Evaluation Method: Simulator X In-Plant Performer:
NAME Start Time Performance Rating: SAT UNSAT Performance Time FinishTime Evaluator: /
SIGNATURE DATE COMMENTS
JPM 150 Page 4 of 9 Rev. 1 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Sequenced steps identified by an "s"
- 2. Any UNSAT requires comments
- 3. Simulator setup: IC-8
- 4. Place 1-HS-62-230A, A Boric Acid Pump, in PTL and tag with a hold order.
- 5. Place hold order ( or orange sticker) on 1-FQ-62-142, Primary Water Batch Counter.
- 6. Booth operator needed to simulate opening and closing 1-62-1051B at steps 17 and 19.
- 7. Freeze the simulator until the operator has been briefed and is ready to perform task.
- 8. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. 15 mins Tools/Equipment/Procedures Needed:
0-SO-62-7, Boron Concentration Control, Section 8.8
References:
A. Reference Title Rev No.
A. 0-SO-62-7 Boron Concentration Control 19 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit is in mode 1.
- 2. Maintenance has completed unplugging of the boric acid system and has returned the system to service.
- 3. The "A"Boric Acid Pump is tagged for breaker inspection.
- 4. The Primary Water Batch Counter (1-FQ-62-142) was damaged during the recent outage and currently out of service.
INITIATING CUES:
- 1. You are the CRO and are directed to perform the post-maintenance flush of the Unit 1 Blender piping with primary water per 0-SO-62-7, Boron Concentration Control.
- 2. Inform US when any required action(s) associated with the performance of this task has been completed.
JPM 150 Page 5 of 9 Rev I JOB PERFORMANCE CHECKLIST STEP/STANDARD SAT/UNSAT STEP 1.: Obtain a copy of the appropriate procedure. __ SAT UNSAT Cue: Two AUOs are stationedat valves62-936 and 62-948 and have establishedradio communications with the control room. Start Time STANDARD: A copy of the O-SO-62.7 has been obtained and goes to section 8.8.
STEP 2.: Check the available capacity of the HUT(s) to receive the blend. __ SAT UNSAT CUE: The HUT tank levels are: A 10%, B 20%.
Cue: (If Asked) The Unit Supervisorwill review Technical Specifications.
STANDARD: Operator records the level of the A and B HUT.
STEP 3.: Ensure AUOs are stationed at valves62-936 and 62-948 and check __ SAT communications.
UNSAT Cue: A UOs reportthey are stationedat valves62-936 and 62-948.
STANDARD: Operator establishes radio communications.
STEP 4.: STOP the operating Boric Acid Pump. ___ SAT STANDARD: Positions 1-HS-62-232A, Boric Acid Pump 1B-B to stop. __ UNSAT STEP 5. Ensure the following handswitch in Pull-to-Lock. __ SAT STANDARD: Positions 1-HS-62-232A, Boric Acid Pump 1B-B in Pull-to-Lock __ UNSAT
JPM 150 page 6 of 9 Rev 1 JOB PERFORMANCE CHECKLIST STFPISTArJDARD SATIUNSAT CLOSE 1-62-1050B, Boric Acid Pump Suction Valve __ SAT STEP 6.:
UNSAT CUE: AUO reports 1-62-1050B is CLOSED.
Critical Step STANDARD: Directs AUO to Close valve 1-62-1050B. [PREVENTS FLOW DIVERSION]
CLOSE 1-FCV-62-237, A Bat recirc valve. _ SAT STEP 7.:
UNSAT STANDARD: Closes 1-FCV-62-237, A Bat Recirc. [PREVENTS FLOW DIVERSION]
Critical Step UNLOCK and CLOSE 1-62-1057, A Bat Recirc. _ SAT STEP 8.:
UNSAT CUE: AUO reports 1-62-1057 is CLOSED.
STANDARD: Directs AUO to Unlock and Close 1-62-1057, A Bat Recirc valve. Critical Step
[PREVENTS FLOW DIVERSION]
Place 1-HS-62-140A, Boric Acid to Blender Flow Control Switch to the SAT STEP 9.:
STOP position. UNSAT STANDARD: Positions 1-HS-62-140A, Boric Acid to Blender Flow Control Switch to STOP.
CLOSE 1-FCV-62-140D, Boric Acid to Blender. SAT STEP 10.:
UNSAT STANDARD: Positions 1-FCV-62-140D to CLOSE
JPM 150 Page 7 of 9 Rev 1 JOB PERFORMANCE CHECKLIST STEP/STANDARD SAT/UNSAT STEP 11.: CLOSE 1-FCV-62-143, Primary Water Valve to Blender. __ SAT UNSAT STANDARD: Positions 1-FCV-62-143 to CLOSE STEP 12.: ENSURE valves 0-62-1077 and 1-62-938 are CLOSED. __ SAT UNSAT CUE: AUO reports 0-62-1077 and 1-62-938 are CLOSED.
STANDARD: Directs AUO to check that valves 0-62-1077 and 1-62-938 are closed.
STEP 13.: ENSURE valves 1-FCV-62-144 and 1-FCV-62-128 are CLOSED. __ SAT UNSAT STANDARD: Checks that valves 1-FCV-62-144 and 1-FCV-62-128 are positioned to CLOSED STEP 14.: OPEN valves 1-62-936 and 1-62-948. __ SAT UNSAT Cue: AUO's reportthat 1-62-936 and 1-62-948 are OPEN.
STANDARD: Directs AUO's to OPEN 1-62-936 and 1-62-948. [ESTABLISHES Critical Step FLOW PATH]
STEP 15.: ENSURE that 1-62-951 is open. SAT UNSAT CUE: AUO reports 1-62-951 is OPEN STANDARD: Operator directs AUO to check that 1-62-951 is OPEN.
STEP 16.: OPEN 1-FCV-62-140D. __ SAT UNSAT STANDARD: Positions 1-FCV-62-140D to OPEN. [ESTABLISHES FLOW PATH]
Critical Step
JPM 150 Page 8 of 9 Rev 1 JOB PERFORMANCE CHECKLIST STEP/STANDARD SAT/UNSAT STEP 17.: UNLOCK and OPEN one of the primary water suction valves. SAT UNSAT NOTE: Booth operator inserts IOR zaofi62139 5. This will give a 25 gpm flow indication on FI-62-139.
Critical Step CUE: AUO reports 1-62-1051B is OPEN STANDARD: Directs AUO to unlock and open 1-62-1051 B, 1B-B Boric Acid Pump Primary Water Suction valve. [ESTABLISHES FLOW PATH]
STEP 18.: FLUSH piping with about 50 gallons of primary water into the HUT. __ SAT UNSAT STANDARD: Operator monitors 1-F1-62-139, Boric Acid Flow Meter for flow indication.
STEP 19.: After flushing is complete (about 50 gals.) CLOSE 1-FCV-62-140D and __ SAT 1-62-1051 B, Boric Acid Pump 1B-B Primary Water Suction Valve.
UNSAT NOTE: Booth operator deletes IOR zaofi62139 5. This will delete the 25 gpm flow indication on FI-62-139 Critical Step CUE: AUO reports 1-62-1051B is CLOSED.
STANDARD: Operator closes 1-FCV-62-140D and directs AUO to close 1-62-1051 B.
[STOPS FLOW]
STEP 20.: VERIFY valves 1-62-936 and 1-62-948 are closed. __ SAT UNSAT Cue: AUO's report that 1-62-936 and 1-62-948 are CLOSED.
Critical Step STANDARD: Directs AUO's to close valves 1-62-936 and 1-62-948. [STOPS FLOW]
JPM 150 Page 9 of 9 Rev 1 JOB PERFORMANCE CHECKLIST STEP/STANDARD SAT/UNSAT STEP 21.: THROTTLE OPEN 1-FCV-62-237, A BAT Recirc. __ SAT UNSAT CUE: AUO reports 1-62-1057 is THROTTLED OPEN.
STANDARD: Operator throttles open 1-FCV-62-237.
STEP 22.: OPEN 1-62-1057, A BAT Recirc SAT UNSAT CUE: AUO reports 1-62-1057 is open.
STANDARD: Operator directs AUO to open 1-62-1057.
STEP 23.: ENSURE Boric Acid Pump Suction Valve OPEN. __ SAT SUNSAT CUE: AUO reports 1-62-1050B is OPEN STANDARD: Directs AUO to open 1-62-1050B, 1B-B Boric Acid Pump suction valve.
STEP 24.: Inform US of completion of the performance of 0-SO-62-7, section 8.8 __ SAT UNSAT Cue: The US is evaluatingLCOs Stop Time Cue: NOTE: When the next step is addressedinform candidate that the OATC will realign the blender controls for AUTO makeup and verify valve positionspersteps 26 and 27 of section 8.8 of the procedure for Boric ConcentrationControl.
STANDARD: SM is informed that Flushing of Unit 1 Blender per 0-SO-62-7 has been performed.
<2
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTIONS 0-S0-62-7 BORON CONCENTRATION CONTROL Revision 19 QUALITY RELATED PREPARED BY: rW.Mathes RESPONSIBLE ORGANIZATION:. OPERATIONS
'\,APPROVED BY: J.A. DVORAK EFFECTIVE DATE: 27 Apr 02 LEVEL OF USE: MULTIPLE USE REVISION DESCRIPTION Revised in accordance with RT-020159 to add new Unit 2 Cycle 12 curves to Appendix E. Revised to add section 8.12 for blending to the "B" HUT from Ul blender. This is an intent change.
SQN BORON CONCENTRATION CONTROL Rev. 19 1,2Re.1 SQN 0-SO-62-7 Page 2 of 129 TABLE OF CONTENTS Page 1 of 2 Section Title Page TABLE OF CONTENTS .................................................................................... 2
1.0 INTRODUCTION
............................................................................................... 4 1.1 Purpose .......................................................................................................... 4 1 .2 S c o p e ................................................................................................................ 4
2.0 REFERENCES
.................................................................................................. 4 2.1 Performance References ................................................................................... 4 2.2 Developmental References ............................................................................... 5 3.0 PRECAUTIONS AND LIMITATIONS ................................................................ 6 4.0 PREREQUISITE ACTIONS .............................................................................. 7 5.0 STARTUP/STANDBY READINESS .................................................................. 10 5.1 Automatic Makeup ............................................................................................. 10
< > 6.0 NORMAL OPERATION .................................................................................... 14 6.1 At Power Routine Dilution ................................................................................. 14 6 .2 Dilute ................................................................................................................. 16 6.3 Alternate Dilute .................................................................................................. 22 6 .4 Bo ra te ................................................................................................................ 26 6.5 Manual Makeup Control .................................................................................... 30 7.0 SHUTDOW N ..................................................................................................... 34 8.0 INFREQUENT OPERA TION ............................................................................. 35 8.1 Blending to Spent Fuel Pit Using Blender via SFP Cooling Pum p Suction Pressure Indicators ............................................... 35 8.2 Blending to Spent Fuel Pit Using Blender via Bull Hose directly to Spent Fuel Pit ................................................................... 43 8.3 Blending to Refueling Water Storage Tank (RWST) Using Boric Acid Blender 50 8.4 Makeup to the Reactor Coolant System from the RWST in Modes 1-4 when Automatic/Manual Makeup is unavailable .............................. 55 8.5 Manual Makeup to the Reactor Coolant System from the RWST in Modes 5 or 6 ........................................................................ 58
SQN 0-SO-62-7 1,2 BORON CONCENTRATION CONTROL Rev. 19 Page 3 of 129 I
TABLE OF CONTENTS Page 2 of 2 Section Title Page 61 8.6 Blending to Transfer Canal Using Boric Acid Blender ..........................................
69 8.7 Blending to the Holdup Tank (HUT) Using Boric Acid Blender ............................
75 8.8 Flushing Unit 1 Blender/Piping Using Primary Water (Maintenance Activities) ...
80 8.9 Flushing Unit 2 Blender/Piping Using Primary Water (Maintenance Activities) ...
86 8.10 Rapid Boration using Emergency Borate Valve ...................................................
89 8.11 Manual Blending to RCS During Refill Operations in Mode 5 or 6 .......................
96 8.12 Blending to "B" Holdup Tank (HUT) Using Unit 1 Boric Acid Blender ..................
104 9.0 REC O R DS .........................................................................................................
APPENDIXES APPENDIX A: HOSE CONNECTION UTILIZING MAINTENANCE SUPPORT 105 APPENDIX B: BORIC ACID FLOW RATE CALCULATIONS ....................... 106 APPENDIX C: CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS) 108 APPENDIX D: CALCULATION FOR AMOUNT OF BORIC ACID OR PRIMARY WAT E R (TI-44) ...................................................................... 110 APPENDIX E: REACTIVITY BALANCE CALCULATION .............................. 111 APPENDIX F: CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUALMAKEUP TO RWST O R HO LD UP TA NK............................................................... 125 APPENDIX G: CALCULATION OF INTEGRATOR SETTINGS FOR MANUAL BLEND DURING RCS FILL ...................................................
SO URCE NOTES .............................................................................................
ATTACHMENTS ATTACHMENT 1: POWER CHECKLIST 1-62-7.01 ATTACHMENT 2: POWER CHECKLIST 2-62-7.02 ATTACHMENT 3: VALVE CHECKLIST 1-62-7.03 ATTACHMENT 4: VALVE CHECKLIST 2-62-7.04
S SQN 0-SO-62-7 1,2 BORON CONCENTRATION CONTROL Rev. 19 Page 4 of 129
1.0 INTRODUCTION
1.1 Purpose To provide instructions for operation of the Boron Control System.
1.2 Scope This instruction provides detailed steps for the following modes of operation:
Automatic Makeup At Power Routine Dilution (Information Use section)
Dilute and Alternate Dilute Borate Manual Makeup Control Blending to Spent Fuel Pit Using Boric Acid Blender via SFP Cooling Pump Suction Pressure Indicators Blending to Spent Fuel Pit Using Boric Acid Blender via Bull Hose Directly to Spent Fuel Pit Blending to RWST Using Boric Acid Blender Makeup to the Reactor Coolant System from the RWST in modes 1 4 when the Automatic/Manual Makeup is unavailable.
Manual Makeup to the Reactor Coolant System from the RWST in modes 5 or 6 Blending to Transfer Canal Using Boric Acid Blender Blending to the Holdup Tank using Boric Acid Blender Flushing Unit 1 Blender/Piping Using Primary Water (Maintenance Activities)
Flushing Unit 2 Blender/Piping Using Primary Water (Maintenance Activities)
2.0 REFERENCES
2.1 Performance References A. Procedures
- 1. 0-SO-62-10, Boric Acid Batch, Transfer, and Storage System
- 2. 0-SO-78-1, Spent Fuel Pit Cooling System B. Technical Instructions - TI-44, Boron Tables
SQN 0-SO-62-7 1,2 BORON CONCENTRATION CONTROL Rev. 19 Page 5 of 129 2.2 Developmental References A. Procedures
- 1. S01-62.2, Boron Concentration Control
- 2. 0-Pi-OPS-000-633.0, Aux. Cont. Rm. Switch Alignment Verification B. Technical Specifications
- 1. 3.1.1.1
- 2. 3.1.1.2
- 3. 3.9.1
- 4. 3.10.1
- 5. Bases 3/4.1.3 C. Technical Requirements Manual
- 1. 3.1.2.1
- 2. 3.1.2.2
- 3. 3.1.2.3
- 4. 3.1.2.4
- 5. 3.1.2.5
- 6. 3.1.2.6
- 7. Bases 3/4.1.2 C. FSAR
- 1. 9.3.4.2.5
- 2. 9.3.4.2.2
- 3. 9.3.4.2.6
- 4. 15.2.4
- 5. 15.2.14.1
- 6. 15.4.6.1 D. TVA Drawings
- 1. 47W809-1
- 2. 47W809-2
- 3. 47W809-5
SSQN 0-SO-62-7 1,2 BORON CONCENTRATION CONTROL Rev. 19 Page 6 of 129 3.0 PRECAUTIONS AND LIMITATIONS A. The mode selector switch should be returned to the AUTO makeup mode after any dilution or boration operation. The control switch must be turned to START in order for the auto makeup to function.
B. At least one Reactor Coolant Pump or one RHR Pump must be in operation during dilution operations. [C.6]
C. Maintain Pressurizer boron concentration within 50 ppm of reactor coolant loop boron concentration. This can be accomplished by turning pressurizer heaters on and allowing sprays to maintain RCS pressure within program.
D. Axial flux difference should be maintained within limits by using the control bank of rods while changing boron concentration.
E. Prior to making a positive reactivity change, Tech Specs should be referenced to ensure the unit is not in a Tech Spec action that prohibits a positive reactivity change. [C.1]
F. A boron sample should be obtained whenever reactor makeup water is added to the VCT, unless the unit is at power and results of the makeup are as expected.
G. When making an RCS dilution of _Ž 3000 gallons, it should be done in batches with an RCS boron concentration verification at the halfway point (e.g., 1500 gallons). Allow at least 15 minutes between batches. [C.5] [C.7]
H. Simultaneous makeup to the RWST and the RCS should be avoided to prevent the possibility of injecting unborated (or under borated) water into the core. [C.4]
[C.6] [C.7]
- 1. Reactivity balance calculations are required for any major plant changes. These changes include power increases and reductions greater than 5% Reactor power.
Although stated in the procedure that only one calculation is required for a major change in Reactor Power, calculations should be current and take into account the time dependency of parameters used in the calculation. [e.g. One calculation to decrease RX power to 70% power to remove a MFP is acceptable. In the event of a large power manipulation (GO startup or shutdown) several calculations will be required. A calculation should be performed for the increase to 30% Reactor power, another for an increase to 50%, and so on. These calculations may be correlated to GO plateaus.]
J. Boric Acid Controller may be adjusted for B-1 0 depletion for automatic and manual makeup to improve the accuracy of the blend. The B-1 0 depletion value for each unit can be obtained from the Rx Eng Information file located on the site intranet.
Reactor Eng Information ICON can be found on the control room PC's.
SQN 0-SO-62-7 SQN BORON CONCENTRATION CONTROL Rev. 19 1,2Re.1 Page 7 of 129 Unit Date 4.0 PREREQUISITE ACTIONS NOTE Throughout this Instruction where an IF/THEN statement exists, the step should be N/A if condition does not exist.
[1] ENSURE the instruction to be used is a copy of the effective version.
[2] ENSURE Precautions and Limitations, Section 3.0, has been reviewed.
[3] ENSURE Chemical and Volume Control System is in operation.
[4] IF in modes 1, 2, or 3, THEN ENSURE requirements of TRM L.C.O. 3.1.2.6 are met.
[5] IF in modes 4, 5, or 6, THEN ENSURE requirements of TRM L.C.O. 3.1.2.5 are met.
[6] ENSURE Primary Makeup Water system in service.
NOTE The following step is performed at the discretion of the RO and/or SRO.
[7] WHEN performing a dilution or boration, THEN ENERGIZE pressurizer heaters so sprays can equalize the boron concentration between the pressurizer and the RCS (N/A, if desired). El
[8] ENSURE appropriate Valve Checklist has been completed (N/A if not applicable).
VALVE CHECKLIST INITIALS 1-62-7.03 2 2-62-7.04
0-SO-62-7 SQN BORON CONCENTRATION CONTROL Rev. 19 1,2 Page 8 of' 129 1 Unit Date 4.0 PREREQUISITE ACTIONS (Continued)
[9] ENSURE appropriate Power Checklist had been completed (N/A if not applicable).
POWER CHECKLIST INITIALS 1-62-7.01 2-62-7.02
[10] IF Boric Acid Tank is the borated water source, THEN ENSURE Boric acid pump aligned properly in accordance with 0-SO-62-10.
[11] IF using the RWST for the borated water source, THEN ENSURE LCV-62-135 and/or LCV-62-136 OPERABLE.
[12] IF reactor is subcritical AND a boration or dilution is required, THEN PERFORM Appendix D NOTE Appendix D and E may be used to verify data provided by Reactor Engineering. IV is not required ifAppendices are performed by an SRO to verify Rx. Engineering data.
[13] IF reactor is critical AND Reactor power is to be changed by > 5%, THEN PERFORM the following:
[a] Appendix E Reactivity balance calculation.
[b] Appendix D Calculation for amount of boric acid or primary water (TI-44).
K->
SQN BORON CONCENTRATION CONTROL 0-SO-62-7 1,2 Rev. 19 Page 9 of 129 Unit Date 4.0 PREREQUISITE ACTIONS (Continued)
[14] INDICATE below which performance section of this instruction will be used and the reason for this performance:
El 5.0 STARTUP/STANDBY READINESS E 6.0 NORMAL OPERATION E] 7.0 SHUTDOWN El 8.0 INFREQUENT OPERATION REASON:
End of Section 4.0
SON 0-SO-62-7 1,2 BORON CONCENTRATION CONTROL Rev. 19 Page 76 of 129 Unit Date 8.8 Flushing Unit I Blender/Piping Using Primary Water (Maintenance Activities)
CAUTION 1 Returning the Boric Acid Blender to service after unplugging, cleaning, or maintenance on the Boric Acid System could introduce debris, sludge, air or chunks of solidified boron into the CCP suction resulting in pump damage. Extreme care must be exercised to properly flush the Boric Acid Blender system after an outage. [C.2]
CAUTION 2 CVCS letdown divert to HUT may be ineffective during Blend to HUT due to possible back seat of check valve 62-950.
NOTE Two AUOs should be stationed in the area of valves62-936 and 62-948, with direct communication to the MCR in order to close these valves when required in a timely manner.
[1] ENSURE sufficient capacity available in the HUT selected to receive blend.
HUT LEVEL INITIALS A %
B %
[2] REFERENCE the appropriate LCO (N/A if not applicable):
LCO INITIALS 3.1.2.1 3.1.2.2
[3] ENSURE AUOs are stationed in general vicinity of r62-9361 (690 Pent Room by Blender) and r62-9481 (690 West Wall of HUT Valve Gallery) and radio communications has been established.
0-SO-62-7 SON BORON CONCEINITRATION CONTROL Rev. 19 1~ 1,2 Page 77 of 129 Unit Date 8.8 Flushing Unit I Blender/Piping Using Primary Water (Maintenance Activities)
(Continued)
[4] STOP the operating Boric Acid Transfer Pump.
[5] ENSURE the following (N/A handswitch not used):
BORIC ACID PUMP HANDSWITCH PULL-TO-LOCK INITIALS 1A-A 1-HS-62-230A 1 B-B 1-HS-62-232A
[6] CLOSE one of the following Boric Acid Pump Suction Valves (N/A valve not used):
BORIC ACID PUMP SUCTION VALVE CLOSED INITIALS IA-A 1-62-1050A 1 B-B 1-62-1050B
[7] CLOSE rI-FCV-62-2371, A BAT Recirc.
[8] UNLOCK AND CLOSE rl-62-10571, A BAT Recirc.
[9] PLACE rt-HS-62-140A], Boric Acid to Blender Flow Control Switch to the STOP position.
[10] CLOSE r[-FCV-62-140D1, Boric Acid to Blender.
[11] CLOSE rI-FCV-62-1431, Primary Water Valve to the Blender.
0-SO-62-7 SON BORON CONCENTRATION CONTROL Rev. 19 1,2 Page 78 of 129 Unit Date 8.8 Flushing Unit I Blender/Piping Using Primary Water (Maintenance Activities)
(Continued)
[12] ENSURE the followin(
REQUIRED POSITION INITIALS VALVE NUMBER 0-62-1077 CLOSED 1-62-938 CLOSED
[13] ENSURE the following:
VALVE NUMBER HANDSWITCH POSITION INITIALS 1-FCV-62-144 CLOSED 1-FCV-62-128 CLOSED
[14] OPEN the following valves:
REQUIRED POSITION INITIALS INITIALS VALVE NUMBER 1-62-936 OPEN 1-62-948 OPEN I
[15] ENSURE rl-62-951 is OPEN.
[16] OPEN [l-FCV-62-140D1.
[17] UNLOCK AND OPEN one of the primary water suction valves to the pump (N/A other valve):
BORIC ACID PUMP PRIMARY WATER SUCTION VALVE INITIALS 1A-A 1-62-1051A 1B-B 1-62-1051B 3/4>
I o-SO-62-7 SQN BORON CONCENTRATION CONTROL Rev. 19 1,2 Page 79 of 129 Unit Date 8.8 Flushing Unit I Blender/Piping Using Primary Water (Maintenance Activities)
(Continued)
[18] FLUSH piping with approximately 50 gallons of primary water into the HUT.
[19] MONITOR rl-FI-62-1391, Boric Acid Flow Meter for flow indication. El
[20] WHEN flushing is complete, THEN
[a] CLOSE rl-FCV-62-140D1.
[b] CLOSE the following (NIA valve not used):
BORIC ACID PUMP PRIMARY WATER SUCTION VALVE INITIALS 1A-A 1-62-1051A 1B-B 1-62-1051B
[21] ENSURE the following:
VALVE NUMBER REQUIRED POSITION INITIALS 1-62-936 CLOSED 1-62-948 CLOSED
[22] THROTTLE OPEN rl-FCV-62-2371, A BAT Recirc.
[23] OPEN rI-62-10571, A BAT Recirc.
SQN 0-S0-62-7 BORON CONCENTRATION CONTROL Rev. 19 1,2 Page 80 of 129 I
Unit Date 8.8 Flushing Unit I Blender/Piping Using Primary Water (Maintenance Activities)
(Continued)
[24] ENSURE the following (N/A valve not used):
BORIC ACID PUMP SUCTION VALVE OPEN INITIALS 1A-A 1-62-1050A I B-B 1-62-1050B
[25] EVALUATE exiting LCOs entered from this instruction.
[26] REALIGN the blender controls for AUTO Makeup to the CVCS in accordance with Section 5.1.
[27] VERIFY the following:
[a] [fl-62-1051A CLOSED and LOCKED. IV
[bi rl-62-1051B1 CLOSED and LOCKED.
IV
[c] [1-62-936] CLOSED.
IV
[d] r1-62-9481 CLOSED.
IV
[e] [1-62-10571 OPEN and LOCKED.
IV
[f] rl-62-1050Al OPEN.
IV
[g] [1-62-1050Bi OPEN.
IV End of Section 8.8
JPM #1136 Page of 12 Rev. 2 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 136 Recovery From Safety Injection and Solid Water Conditions Original Signatures on File Original Signatures on File PREPARED/ Date/
REVISED BY:
VALIDATED BY:
- Date/
Date/
APPROVED BY:
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
" Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
K-I
JPM # 13612 Page 2 of Rev. 2 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION AFFECTED REVISED BY:
MI' I-I 0; fJI hlI S
0 Initial Write Y ý-11 9/18/95 All HJ Birch 1 Incorporate Rev B changes. Validate Y since original was not.
N 9/23/99 4 SR Taylor pen/ink EA-62-5 Rev Change only 9/27/99 4 SR Taylor pen/ink ES-I .1 Rev Change only N 8/22/00 all SR Taylor pen/ink EA-62-5 Rev Change only N N 8/20/02 All J P Keamey 2 Incorporated pen/ink changes; revised to latest revision to EA-62-5; no impact on JPM flow V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM # 136 Page 3 of 12 Rev. 2 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task: Terminate SI and Stabilize the JA/TA task #: 0001000501 (RO)
Plant K/A Ratings:
006050A1.01 (4.0-4.3) 011000A1.02 (3.3-3.5) 006050A4.02 (4.1-4.2) 011000A4.01 (3.5-3.2) 011000A1.01 (3.5-3.6) 011000A4.05 (3.2-2.9)
Task Standard:
Terminate Safety Injection and Stabilize the Plant.
Evaluation Method: Simulator X In-Plant Performer:
NAME Start time Performance Rating: SAT__ UNSAT Performance Time Finish time Evaluator: /
SIGNATURE DATE COMMENTS
JPM # 136 Page 4 of 12 Rev. 2 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Sequenced steps identified by an "s"
""2. Initialize simulator to IC 10. (Use IC 89 if available) Actuate Safety Injection Signal. Close TDAFW valves.
Allow the Pzr to go solid and the PORV to start OPENING. Freeze the simulator.
- 3. The Console operator will be required to acknowledge simulator alarms
- 4. Any UNSAT requires comments
- 5. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. 16 mins Local Tools/EquipmenftProcedures Needed:
ES-1.1 EA-62-5
REFERENCES:
IReference Title Rev No.
- 1. ES- 1SI Termination 7 2 EA-62-5 Establishing Normal Charging and Letdown 6 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you and to indicate completion of your answer to a knowledge question return the written copy of the question to me.
INITIAL CONDITIONS:
- 1. Unit 1 has experienced a Safety Injection from 100% power.
- 2. During the performance of E-0 the operators experienced multiple problems with AFW and were required to implement FR-H.1.
- 3. FR-H.1 has been completed and all problems corrected.
- 4. During the performance of FR-H.1 the pressurizer level went off sca!e and the PORVs have lifted several times.
INITIATING CUES:
- 1. The operators have just determined that the SI was spurious and E-0 has directed them to ES-i.1 "SI Termination.
He has cautioned you to minimize the Pzr level reduction rate to minimize the RCS pressure excursions during this recover.
- 3. Notify the SRO when CCP suction has been realigned to the VCT and pressurizer level is slowly decreasing.
JPM Page#5 136 of 12 Rev. 2 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD SAT STEP 1.: Obtain a copy of the procedure. UNSAT Start Time_._.
STANDARD: Operator obtains a copy of ES-I .1 SI Termination.
SAT STEP 2.: Reset SI and Check the following UNSAT SI ACTUATED permissive DARK.
AUTO SI BLOCKED permissive LIT.
Critical Step and that the STANDARD: Checks that the "SI ACTUATED" permissive is DARK "AUTO SI BLOCKED" permissive is lit (panel M-4 XA-55-4A)
SAT STEP 3.: MONITOR shutdown boards continuously energized. UNSAT Cue: The CRO will monitor the shutdown boards energized.
energized.
STANDARD: Operator addresses monitoring the SD Bds continuously SAT STEP 4.: Reset Phase A & Phase B. UNSAT Phase B reset NOT required since Phase B has NOT actuated. Critical Step NOTE:
push-buttons.
STANDARD: Operator depresses Train A & Train B Phase A reset (HS-30-63E & D). (May reset Phase B also)
SAT STEP 5.: ESTABLISH control air to containment USING EA-32-1. UNSAT Cue: The CRO will perform this EA.
STANDARD: Operator initiates EA-32-1.
JPM Page#6 136 of 12 Rev. 2 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD SAT STEP 6.: STOP all BUT one CCP and PLACE in A-AUTO.
UNSAT for one of the STANDARD: Checks both CCPs running. Places the control switch charging pumps in the STOP position, (HSs-63-108 or 104), verifies Critical Step pump stops - green light comes "on", amps go to zero, and then RETURNS the handswitch to the A-AUTO position.
SAT STEP 7.: CHECK RCS pressure stable or rising.
UNSAT OR RISING STANDARD: Operator checks RCS pressure to ensure it is STABLE (PAM INSTRUMENTS)
SAT STEP 8.: CLOSE inlet isolation valves FCV-63-39 and FCV-63-40. UNSAT by green light STANDARD: Operator closes FCV-63-39 and FCV-63-40 as indicated only lit on HSs. Critical Step SAT STEP 9.: CLOSE outlet isolation valves FCV-63-25 and FCV-63-26 UNSAT indicated by green light Critical Step STANDARD: Operator closes FCV-63-25 and FCV-63-26 as only lit on HSs.
SAT STEP 10.: CLOSE seal water flow control valve FCV-62-89.
UNSAT to zero. Critical Step STANDARD: Operator closes FCV-62-89 by dialing controller SAT STEP 11.: OPEN alternate or normal charging isolation valve FCV-62-85 or 86.
STANDARD: Operator verifies FCV-62-85 or 86 is open.
JPM # 136 Page 7 of 12 Rev. 2 Job Performance Checklist:
RTFPISTANDARD SAT/UNSAT STEP 12.: OPEN charging flow isolation valves FCV-62-90 and 91. __ SAT UNSAT STANDARD: Operator opens both FCV-62-90 and 91.
Critical Step STEP 13.: ESTABLISH desired charging flow USING FCV-62-89 and FCV-62-93. __ SAT UNSAT STANDARD: Operator adjusts FCV-62-89 & 93 to establish:
- 1) Seal injection flow 6-10 gpm (FIs-62-1, 14, 27, 40)
- 2) Charging flow should be approx. 60 gpm to prevent letdown Critical Step flashing when it is placed in service. (it is permissible to set charging at minimum at this time)
CONTROL charging flow to maintain pressurizer level.. SAT STEP 14.:
UNSAT STANDARD: Operator ensures FCV-62-89 & 93 to establish:
- 1) Seal injection flow 6-10 gpm (Fls-62-1, 14, 27, 40)
- 2) PZR level stable or increasing (LR-68-339)
- 3) Charging flow should be approx. 60 gpm to prevent letdown flashing when it is placed in service. (It is permissible to set charging at minimum at this time)
STEP 15.: Determine ifSI pumps should be stopped. __ SAT UNSAT STANDARD: Operator verifies:
that RCS pressure Ž 1500 psig (PAM Instruments)
RCS pressure stable or increasing SI pump flow on FI-63-151 ZERO SI pump flow on FI-63-20 ZERO STEP 16.: STOP SI pumps and PLACE in A-AUTO. __ SAT UNSAT STANDARD: Operator places control switches to the STOP position, verifies green lights "ON" HSs-63-10 & 15, then places both switches to the A-AUTO position.
JPM Page #8 136 of 12 Rev. 2 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT SAT STEP 17.: Determine if RHR pumiPs should be stopped.
UNSAT FCV-74-3 & 21 open.
STANDARD: Checks ECCS pumps aligned to RWST, "THENplaces control switch in the STOP position for both pumps verify green lights "ON", and amps go to zero, then return switches to the A-AUTO position.
Monitor ECCS flow NOT required. SAT STEP 18.:
UNSAT STANDARD: Operator monitors the following:
a) RCS subcooling based on core exit T/Cs> 40°F (PAM Instruments) b) PZR level> 10% (PAM Instruments)
SAT STEP 19.: MONITOR ifcontainment spray should be stopped:
UNSAT STANDARD: Operator determines not CS pumps running and goes to next step.
'I SAT STEP 20.: MONITOR if letdown can be established:
UNSAT STANDARD: Operator verifies pressurizer level greater than 20% and transitions to EA-62-5, Establishing Normal Charging and Letdown.
SAT NOTE: The following steps will be performed in EA-62-5 section 4.3.
UNSAT STEP 21.: VERIFY pressurizer level greater than 17%.
STANDARD: Operator verifies pzr level greater than 17%.
ENSURE letdown orifice isolation valves CLOSED: SAT STEP 22.:
I INJSAT UNSAT STANDARD: Operator verifies FCV-62-72, 73, 74 closed as indicated by green light ON HSs.
<112
JPM #9 136 Page of 12 Rev. 2 Job Performance Checklist:
SAT/UNSAT STFI:=STANnARD
__ SAT STEP 23.: OPEN letdown isolation valves:
UNSAT STANDARD: Operator verifies open FCV-62-69 and 70. Opens FCV-62-77 as indicated by Red light ON all HSs. Critical Step PLACE HIC-62-78 in MANUAL and open to -50%. __ SAT STEP 24.:
UNSAT STANDARD: HIC-62-78 controller placed in MANUAL and opened to -50%.
SAT STEP 25.: PLACE letdown pressure controller PCV-62-81 in MANUAL and ADJUST output between 50% and 60% open. UNSAT Critical Step STANDARD: PCV-62-81 controller placed in manual and its output adjusted between 50% and 60% open.
SAT STEP 26.: ADJUST charging flow as necessary to prevent flashing in the letdown line. UNSAT STANDARD: Operator adjusts charging flow to approximately 60 gpm. (this amount will prevent flashing)
OPEN letdown orifice isolation valves as needed: -- SAT STEP 27.:
UNSAT STANDARD: Operator opens either FCV-62-72, 73, OR, 74 as indicated by Red light Critical Step ON that HS.
SAT STEP 28.: ADJUST letdown pressure controller, PCV-62-81, output to obtain desired pressure, Match setpoint to existing pressure and THEN place UNSAT PCV-62-81 in AUTO.
Critical Step STANDARD: PCV-62-81 adjusted to get letdown pressure to approximately 325 psig and the controller placed in AUTO.
JPM #136 Page 10 of 12 Rev. 2 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT NOTE: Normal letdown temperature is -11 0 °F. __ SAT STEP 29.: ADJUST HIC-62-78 to obtain desired letdown temperature, as indicated __ UNSAT on TI-62-78, and place HIC-62-78 in AUTO.
STANDARD: Operator adjusts letdown temperature to -1 100F..
STEP 30.: IF necessary to stabilize letdown temperature on Unit 1, place HIC __ SAT 78A in Man and adjust in open direction. WHEN letdown HTX outlet temperature stabilized at approximately 11 00 F, PLACE in auto. __ UNSAT STANDARD: Operator ensures letdown temperature is stabilized.
STEP 32.: ENSURE high temperature divert valve, HS-62-79A, in DEMIN position. __ SAT UNSAT STANDARD: Operator ensures or places HS-62-79A is in DEMIN position and the right RED light ON.
STEP 33.: ADJUST charging and letdown as necessary to maintain RCP seal __ SAT injection flow and pressurizer level.
UNSAT NOTE: Since pressurizer level is off scale, it will be necessary to control RCS pressure to determine if level is rising / stable / or increasing.
Operator may use cold cal level indicator for trend.
STANDARD: FCV-62-89 and 93 adjusted to stabilize pzr pressure or slowly decrease pressure.
JPM Page#11136 of 12 Rev. 2 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD SAT Note: The following steps are in ES-1.1 UNSAT STEP 34.: CHECK VCT makeup control system: Makeup set for> RCS boron Conc. And set for automatic control.
Cue: The CRO will ensure check RCS boron and perform this step.
STANDARD: Operator addresses setting VCT makeup controls.
I SAT STEP 35.: DETERMINE ifCCP suction can be aligned to VCT: CHECK CCP suction aligned to RWST. UNSAT STANDARD: Operator determines that CCP is aligned to RWST (FCV-63-135 & 136 open).
OPEN VCT outlet valves LCV-62-132 and 133 and PLACE in SAT STEP 36.:
PULL A-P-AUTO UNSAT STANDARD: Operator opens LCV-62-132 and 133 verifies red lights ON, THEN places handswitches to PULL A-P-AUTO SAT STEP 37.: Close RWST valves LCV-62-135 and 136 and PLACE in PULL A-P-AUTO UNSAT STANDARD: Operator closes LCV-62-135 and 136 verifies green lights ON, THEN places handswitches to PULL A-P-AUTO
JPM Page #12136 of 12 Rev. 2 Job Performance Checklist:
SAT/UNSAT TCD/RTANflARfl Q'rcl)/QTANDARD I When Pzr pressure is stable (or slightly decreasing) with a slightly SSAT STEP 38.:
increasing VCT level, Inform SRO that SI is terminated, normal charging UNSAT and letdown has been established, and Pzr conditions indicate that level is decreasing Stop Time-Cue: When conditions indicate thatpressure is decreasingslowly, cold cal decreasing,and/orVCT level is increasingslowly; inform operatorthat pzr level indicatorsare startingto show level below 100%.
STANDARD: Operator informs SRO that SI is terminated, normal charging and letdown is established, and Pzr level in less than 100%.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY SUBPROCEDURE ES-I.1 SI TERMINATION Revision 7 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER DATE: 02/01/99 RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W.T. RYAN DATE: 2/3/99 EFFECTIVE DATE: 2/10/99 VERIFICATION DATE: 2/2/99 VALIDATION DATE: 2/3/99 REVISION DESCRIPTION: Reworded step 26 to comply with ERG and to eliminate confusion if a DIG is supplying a shutdown board. Revisedsteps 23 and 26 as a result of the title of EA-202-1 being changed. This is an intent revision.
This procedure contains a Foldout Page which is printed on the back of applicable pages and a Handout Page which is two-sided (3 copies).
I
1.0 PURPOSE This procedure provides operator actions to terminate safety injection and stabilize plant conditions.
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 ENTRY CONDITIONS E-0 Reactor Trip or Safety Injection:
- Specified termination criteria satisfied.
E-1 Loss of Reactor or Secondary Coolant:
- Specified termination criteria satisfied.
FR-H.1 Loss of Secondary Heat Sink:
- Secondary heat sink reestablished and SI terminated.
3.0 OPERATOR ACTIONS Page 2 of 17
STEPIACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED RESET Sland CHECK the following:
"* AUTO S.I. BLOCKED permissive LIT. [M-4A, 04]
"* S.I. ACTUATED permissive DARK. [M-4A, D4]
WHEN shutdown board reenergized,
- 2. MONITOR shutdown boards continuously THEN energized.
ENSURE safeguards equipment running as necessary.
- 3. RESET Phase A and Phase B.
<2
- 4. ESTABLISH control air to containment USING EA-32-1, Establishing Control Air to Containment.
- 5. STOP all BUT one CCP and PLACE in A-AUTO.
DO NOT STOP additional ECCS pumps.
- 6. CHECK RCS pressure stable or rising. GO TO E-1, Loss of Reactor or Secondary Coolant.
Page 3 of 17
ES-1.1 SQN SI TERMINATION Rev. 7 ISTEP ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 7. ISOLATE CCPIT:
- a. CLOSE inlet isolation valves FCV-63-39 and FCV-63-40.
- b. CLOSE outlet isolation valves FCV-63-26 and FCV-63-25.
- 8. ESTABLISH normal charging flow:
- a. CLOSE seal water flow control valve FCV-62-89.
- b. OPEN alternate or normal charging isolation valve FCV-62-85 or FCV-62-86.
- c. OPEN charging flow isolation valves FCV-62-90 and FCV-62-91.
- d. ESTABLISH desired charging flow USING seal water and charging flow control valves FCV-62-89 and FCV-62-93.
Page 4 of 17
ISTEP ACTIONIEXPECTED ESPONSE I RESPONSE NOT OBTAINED
- 9. CONTROL charging flow to maintain IF pressurizer level continues to drop, THEN pressurizer level.
PERFORM the following:
- a. OPEN CCPIT outlet isolation valves FCV-63-26 and FCV-63-25.
- b. OPEN CCPIT inlet isolation valves FCV-63-39 and FCV-63-40.
- c. CLOSE charging flow isolation valves FCV-62-90 and FCV-62-91.
Page 5 of 17
I STEP IACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 10. DETERMINE if SI pumps should be stopped:
- a. CHECK RCS pressure and SI flow: a. IF NO S/G is Faulted, THEN Pressure stable or rising GO TO ES-1.2, Post LOCA Cooldown and Depressurization.
Pressure greater than 1500 psig SI pump flow on FI-63-151 ZERO IF any S/G is Faulted, SI pump flow on FI-63-20 ZERO. THEN PERFORM the following:
- 1) DO NOT CONTINUE this procedure UNTIL Faulted S/G depressurization stops.
- 2) IF the criteria for stopping SI pumps can NOT be satisfied after Faulted S/G depressurization stops, THEN GO TO ES-1.2, Post LOCA Cooldown and Depressurization.
- b. STOP SI pumps and PLACE in A-AUTO.
Page 6 of 17
I STEP IACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 11. DETERMINE if RHR pumps should be stopped:
- a. CHECK RHR pumps a. IF RHR pumps aligned to containment ALIGNED to RWST. sump, THEN GO TO Step 12.
a IMN
- b. STOP RHR pumps and PLACE in A-AUTO.
- 12. MONITOR ECCS flow NOT required:
T/Cs greater than 40'F. GO TO E-1, Loss of Reactor or Secondary Coolant.
- b. Pressurizer level b. CONTROL charging flow to maintain greater than 10% [20% ADV]. pressurizer level.
IF pressurizer level can NOT be maintained, THEN PERFORM the following:
- 1) START ECCS pumps as necessary.
- 2) GO TO E-1, Loss of Reactor or Secondary Coolant.
Page 7 of 17
sTEP IACTONEXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. MONITOR if containment spray should be stopped:
- a. CHECK any containment spray pump a. GO TO Step 14.
RUNNING.
- b. CHECK containment pressure b. GO TO Step 14.
less than 2.0 psid.
- c. RESET Containment Spray.
- d. STOP containment spray pumps and PLACE in A-AUTO.
- e. CLOSE containment spray discharge valves FCV-72-2 and FCV-72-39.
Page 8 of 17
STEPIACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED
- 14. MONITOR if letdown can be established:
- a. CHECK pressurizer level a. GO TO Step 15.
greater than 20% [35% ADV].
Wr
- b. ESTABLISH excess letdown USING
- b. ESTABLISH letdown USING EA-62-3, Establishing Excess Letdown.
EA-62-5, Establishing Normal Charging and Letdown.
ADJUST controls as necessary.
- 15. CHECK VCT makeup control system:
- b. Makeup set for automatic control.
- 16. DETERMINE if CCP suction can be aligned to VCT:
- a. CHECK CCP suction a. GO TO Step 17.
ALIGNED to RWST.
- b. OPEN VCT outlet valves LCV-62-132 and LCV-62-133 and PLACE in PULL A-P-AUTO.
- c. CLOSE RWST valves LCV-62-135 and LCV-62-136 and PLACE in PULL A-P-AUTO.
1/2>
Page 9 of 17
I STEP IACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 17. DETERMINE ifsteam dump to condenser available:
- a. CHECK condenser AVAILABLE: a. USE atmospheric reliefs in AUTO and set for 84% (1005 psig).
"* C-9 CONDENSER INTERLOCK permissive LIT [M-4A, E6] IF local control of atmospheric reliefs is necessary,
"* At least one Intact S/G THEN MSIV OPEN. DISPATCH personnel to dump steam USING EA-1-2, Local Control of S/G PORVs.
GO TO Step 18.
- b. PLACE steam dumps in STEAM PRESS mode.
- 18. MAINTAIN T-hots STABLE:
"* CONTROL feed flow.
"* DUMP steam.
Page 10 of 17
ISTEP JACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED IF normal spray NOT available AND letdown
- 19. MAINTAIN pressurizer pressure stable in service, USING pressurizer heaters and normal THEN spray as necessary.
ESTABLISH auxiliary spray USING EA-62-4, Establishing Auxiliary Spray.
IF normal spray NOT available AND auxiliary spray can NOT be established, THEN USE one pressurizer PORV.
- 20. MAINTAIN Intact S/G narrow range levels:
- a. Greater than 10% [25% ADV] a. MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10% [25% ADV]
in at least one S/G.
- b. IF level in any S/G continues to rise,
- b. Between 10% [25% ADV] and 50%. THEN STOP feed flow to affected S/G.
ESTABLISH normal cooling to RCPs
- 21. CHECK RCP cooling NORMAL:
USING EA-68-2, Establishing RCP Start Conditions.
"* RCP seal injection flow.
Page 11 of 17
STEPACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. DETERMINE if RCP seal return flow should be established:
- a. ESTABLISH C0S cooling to seal water
- a. VERIFY CCS cooling to seal water heat exchanger.
heat exchanger NORMAL:
SEAL WATER HX OUTLET IF CCS cooling to seal water heat FLOW/TEMP ABNORMAL exchanger can NOT be established, alarm DARK [M-27B, A6 (A7)J. THEN GO TO Step 23.
r
- b. OPEN seal return isolation valves FCV-62-61 and FCV-62-63.
<2 ENERGIZE AC busses from offsite power
- 23. VERIFY AC busses ENERGIZED USING EA-202-1, Restoring Off-Site Power to from start busses. 6900V Shutdown Boards.
IF necessary, THEN ENSURE the diesel generators supplying the shutdown boards.
WHEN shutdown power restored, THEN ENSURE safeguards equipment running as necessary.
Page 12 of 17
ISTEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAU TION Loss of all RCP seal cooling may cause RCP seal damage and will require a TSC status evaluation prior to restarting affected RCPs.
NOT "E To optimize normal pressurizer spray capability, the preferred RCP starting order is: 2, 1, 4, 3.
- 24. MONITOR RCP Status:
- a. At least one RCP RUNNING. a. ATTEMPT to start one RCP:
- 1) IF all RCP seal cooling has previously been lost, THEN NOTIFY TSC to initiate RCP restart status evaluation.
IF an RCP can NOT be started, THEN MONITOR natural circulation USING EA-68-6, Monitoring Natural Circulation Conditions.
IF natural circulation can NOT be verified, THEN RAISE steam dump rate from Intact S/G(s).
K->
Page 13 of 17
rSTEPI ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 25. MONITOR if source range detectors should be reinstated:
- a. CHECK intermediate range flux a. GO TO Step 26.
less than 10-5% power.
- b. REINSTATE source range detectors.
- b. CHECK source range detectors REINSTATED.
- d. ENSURE audio count rate operation.
- e. RESET shutdown monitor alarm setpoints. [M13J
- f. WHEN shutdown monitor ALARM LEDs dark AND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL.
[M13]
- 26. DETERMINE if diesel generators should be stopped:
- a. VERIFY shutdown boards a. ATTEMPT to restore offsite power to shutdown boards USING EA-202-1, ENERGIZED from start busses. Restoring Off-Site Power to 6900V Shutdown Boards.
- b. STOP any unloaded diesel generators and PLACE in standby USING EA-82-1, Placing DIGs in Standby.
Page 14 of 17
ISTEPI ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I
- 27. ALIGN MSRs for hot standby:
- a. DEPRESS RESET on MSR Control Panel XX-47-3000.
- b. ISOLATE high pressure steam to MSRs:
- 1) CLOSE the following valves and VERIFY status on panel XX-1-145:
"* FCV-1-141
"* FCV-1-241
"* FCV-1-135
"* FCV-1-235
"* FCV-1-143
"* FCV-1-243
"* FCV-1-137
"* FCV-1-237
"* FCV-1-145
"* FCV-1-245
"* FCV-1-139
"* FCV-1-239.
- c. OPEN MSR starting vents and VERIFY status on panel XS-6-1.
- d. CLOSE MSR operating vents and VERIFY status on panel XS-6-3.
Page 15 of 17
ISTEPI ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 28. SHUT DOWN unnecessary plant equipment:
- MFWpumps.
- Con DI booster pumps.
- No. 3 heater drain tank pumps.
- No. 7 heater drain tank pumps.
- Condensate booster pumps.
- Hotwell pumps.
- 29. MAINTAIN plant conditions stable:
"* Pressurizer pressure
"* Pressurizer level between 20% [35% ADV] and 65%
"* RCS temperatures
"* Intact S/G narrow range levels between 10% [25% ADV] and 50%.
Page 16 of 17
ISTEPI ACTION/EXPECTED RESPONSE F RESPONSE NOT OBTAINED
- 30. MONITOR ECCS flow NOT required:
T/Cs greater than 40 0F. GO TO E-1, Loss of Reactor or Secondary Coolant.
a
- b. Pressurizer level b. CONTROL charging flow to maintain greater than 10% [20% ADV]. pressurizer level.
IF pressurizer level can NOT be maintained, THEN PERFORM the following:
- 1) START ECCS pumps as necessary.
- 2) GO TO E-1, Loss of Reactor or Secondary Coolant.
- 31. PERFORM EA-0-9, Post Trip Administrative Requirements.
- 32. GO TO appropriate plant procedure.
END Page 17 of 17
HANDOUT FOR ES-1.1 Page 1 of I STEP ACTION
- 2. MONITOR shutdown boards continuously energized.
- 2. WHEN shutdown board reenergized, RNO THEN ENSURE safeguards equipment running as necessary.
- 9. CONTROL charging flow to maintain pressurizer level.
- 12. MONITOR ECCS flow NOT required:
RCS subcooling based on core exit T/Cs greater than 400F.
Pressurizer level greater than 10% [20% ADV].
- 13. MONITOR if containment spray should be stopped:
(any containment spray pump running and containment pressure less than 2.0 psid)
- 14. MONITOR if letdown can be established:
CHECK pressurizer level greater than 20% [35% ADV].
- 18. MAINTAIN T-hots stable: (by controlling feed flow or by dumping steam)
- 19. MAINTAIN pressurizer pressure stable.
- 20. MAINTAIN Intact S/G narrow range levels between 10% [25% ADV] and 50%.
20.a. MAINTAIN total feed flow greater than 440 gpm RNO UNTIL level greater than 10% [25% ADV] in at least one S/G.
- 24. MONITOR RCP status: (at least one RCP running) 24.a. IF an RCP can NOT be started, RNO THEN MONITOR natural circulation.
- 25. MONITOR if source range detectors should be reinstated:
(IRM flux less than 10o5% power) 25f WHEN shutdown monitor ALARM LEDs dark AND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL. [M13]
- 29. MAINTAIN plant conditions stable:
"* Pressurizer pressure
"* Pressurizer level between 20% [35% ADV] and 65%
"* RCS temperatures
- Intact S/G levels between 10% [25% ADV] and 50%.
- 30. MONITOR ECCS flow NOT required:
0 RCS subcooling based on core exit TICs greater than 40 F.
Pressurizer level greater than 10% [20% ADV].
K->
FOLDOUT FOR ES-1.1 SI REINITIATION CRITERIA IF either of the following conditions occurs:
"* RCS subcooling based on core exit T/Cs less than 40'F, OR
"* Pressurizer level can NOT be maintained greater than 10% [20% ADV],
THEN START ECCS pumps as necessary.
RED PATH
SUMMARY
- 1. SUBCRITICALITY Nuclear power greater than 5%.
0
- 2. CORE COOLING Core exit T/Cs greater than 1200 F.
OR Core exit T/Cs greater than 700°F AND all RCPs stopped AND RVLIS lower range less than 40%.
- 3. HEAT SINK All S/G narrow range levels less than 10% [25% ADV]
AND Total feedwater flow less than 440 gpm.
- . -- +/-Lt.. .nnor: nn rig+O
- -..,f
- 4. PRESSURIZED T-cold drop greater than Iuu r i ISL M THERMAL AND SHOCK T-cold less than 250°F.
- 5. CONTAINMENT Containment pressure greater than 12.0 psid.
EVENT DIAGNOSTICS
"* IF both trains of shutdown boards deenergized, THEN GO TO ECA-0.0, Loss of All AC Power.
140 psig
" IF any S/G pressure dropping in an uncontrolled manner or less than AND S/G NOT isolated, THEN GO TO E-2, Faulted Steam Generator Isolation.
radiation, IF any Intact S/G has level rising in an uncontrolled manner or has abnormal THEN START ECCS pumps as necessary and GO TO E-3, Steam Generator Tube Rupture.
TANK SWITCHOVER SETPOINTS e IF CST level less than 10%,
THEN ALIGN AFW suction to ERCW.
- IF RWST level less than 27%,
THEN GO TO ES-1.3, Transfer to RHR Containment Sump.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY ABNORMAL PROCEDURE EA-62-5 ESTABLISHING NORMAL CHARGING AND LETDOWN Revision 6 QUALITY RELATED PREPARED/PROOFREAD BY: J.R.WALKER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J.A. DVORAK EFFECTIVE DATE: 11 July 02 REVISION DESCRIPTION: Revised in accordance with RT-01 0572 to correct name of organization referenced in Step 3 of Section 4.1. This is a non intent change.
1.0 PURPOSE To establish normal charging and letdown flows.
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 Entry Conditions A. E-3, Steam Generator Tube Rupture.
B. ECA-0.1, Recovery from Loss of All AC Power Without SI Required.
C. ECA-2.1, Uncontrolled Depressurization of All Steam Generators.
D. ECA-3.3, SGTR Without Pressurizer Pressure Control.
E. ES-0.1, Reactor Trip Response.
F. ES-0.2, Natural Circulation Cooldown.
H. FR-I.1, High Pressurizer Level.
I. FR-1.3,Voids in Reactor Vessel.
J. FR-P.1, Pressurized Thermal Shock.
K. AOP-l.04 Pressurizer Instrument Malfunction L. AOP-P.01, Loss of Offsite Power.
M. AOP-P.03, Loss of Unit 1 Vital Instrument Power Board.
N. AOP-P.04, Loss of Unit 2 Vital Instrument Power Board.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions A. If the accountability siren sounds, the operator should continue performing this procedure. The SM will remain aware of procedure progress and location of performing personnel.
EA-62-5 SQN ESTABLISHING NORMAL CHARGING AND LETDOWN Rev. 6 1,2 Page 3 of 9 4.0 OPERATOR ACTIONS 4.1 Section Applicability
- 1. IF normal charging flow is to be established, THEN GO TO Section 4.2. El
- 2. IF normal letdown flow is to be established, THEN GO TO Section 4.3. El r
- 3. IF high activity suspected in the RCS, THEN NOTIFY Radiological Control section to monitor plant radiological conditions as required.
El
- 4. RETURN TO procedure and step in effect. El
EA-62-5 SQN ESTABLISHING NORMAL CHARGING AND LETDOWN Rev. 6 1,2 Page 4 of 9 4.2 Establishing Normal Charging Flow
- 1. VERIFY at least one CCP RUNNING. El
- 2. CLOSE seal water flow control valve [FCV-62-891. El
- 3. OPEN charging header isolation valves:
- EFCV-62-90] El
- rFCV-62-91] El
- 4. OPEN one of the following charging isolation valves:
CHARGING ISOLATION VALVES
[ EPEN FCV-62-86 (normal charging) []
FCV-62-85 (alternate charging) []
- 5. ESTABLISH at least 60 gpm charging flow USING seal water and charging flow control valves [FCV-62-891 and rFCV-62-931. E]
- 6. ADJUST seal injection flow to each RCP to between 6 gpm and 10 gpm. El
- 7. IF automatic level control desired AND pressurizer level greater than 25%,
THEN PLACE charging flow control valve [FCV-62-931 in AUTO. El
- 8. GO TO Section 4.1, step in effect. El END OF SECTION
EA-62-5 SQN ESTABLISHING NORMAL CHARGING AND LETDOWN Rev. 6 1,2 Page 5 of 9 4.3 Establishing Normal Letdown Flow NOTE EA-62-3, Establishing Excess Letdown, may be utilized if Normal Letdown cannot be established.
- 1. IF charging flow NOT established, THEN PERFORM Section 4.2. U
- 2. VERIFY pressurizer level greater than 17%. El
- 3. ENSURE letdown orifice isolation valves CLOSED:
CLOSED VALVES LETDOWN ORIFICE ISOLATION FCV-62-72 El FCV-62-73 El FCV-62-74 IL
- 4. OPEN letdown isolation valves:
OPEN LETDOWN ISOLATION VALVES FCV-62-69 EL FCV-62-70 IL FCV-62-77 IL
EA-62-5 SQN ESTABLISHING NORMAL CHARGING AND LETDOWN Rev. 6 1,2 Page 6 of 9 4.3 Establishing Normal Letdown Flow (Continued)
NOTE Placing cooling water on the Letdown Heat Exchanger prior to restoring letdown flow should prevent TIS-62-79B/A from actuating and fully opening TCV-70-192.
- 5. PLACE [HIC-62-781 in MANUAL, AND OPEN rTCV-70-192] to - 50%. El
- 6. PLACE letdown pressure controller rPCV-62-811 in MANUAL and ADJUST output between 40% and 50%, (50%-60% open). El
- 7. ADJUST charging flow as necessary to prevent flashing in the letdown line. E]
- 8. OPEN letdown orifice isolation valves as needed:
EA-62-5 SQN ESTABLISHING NORMAL CHARGING AND LETDOWN Rev. 67 of 9 1,2 Page 4.3 Establishing Normal Letdown Flow (Continued)
NOTE Normal letdown pressure is 325 psig at normal operating temperature.
- 9. ADJUST letdown pressure controller [PCV-62-811 output to obtain desired pressure.
- 10. ADJUST letdown pressure controller [PCV-62-81i setpoint to match existing pressure.
- 11. PLACE letdown pressure controller [PCV-62-811 in AUTO.
FE NOTE Normal letdown temperature is -110°F.
- 12. ADJUST [HIC-62-78A1 to obtain desired letdown temperature, as indicated on [TI-62-78. El
- 13. PLACE [HIC-62-78A1 in AUTO. El
EA-62-5 SON ESTABLISHING NORMAL CHARGING AND LETDOWN Rev. 6 Page 8 of 9 1,2 4.3 Establishing Normal Letdown Flow (Continued)
NOTE Letdown temperature may swing due to repeated actuation of TIS-62-79B/A, which causes letdown temperature control valve TCV-70-192 to fully open.
- 14. IF necessary to stabilize letdown temperature, THEN PERFORM the following:
- a. PLACE fHIC-62-78A] in MANUAL and ADJUST controller output in OPEN direction.
El
- b. WHEN letdown heat exchanger outlet temperature is stabilized at approximately 110 0 F, THEN PLACE IHIC-62-78A1 in AUTO.
El El
- 15. ENSURE high temperature divert valve EHS-62-79A1 in DEMIN position.
- 16. ADJUST charging and letdown as necessary to maintain RCP seal injection flow and pressurizer level. El
- 17. GO TO Section 4.1, step in effect. El END OF TEXT
5.0 REFERENCES
None.
JPM #77-4AP2 Page 1 of 9 Rev. I SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 77-4AP2 Perform D/G Load Test on 1A-A D/G (Erratic Voltage)
<2 PREPARED/
REVISED BY: Date/
VALIDATED BY: Date/
APPROVED BY: Date/
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM #77-4AP2 Page 2 of 9 Rev. 1 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION AFFECTED REVISED BY:
0 New, written from #077-4AP, changed to Y 7/6/00 All JL Epperson 1A-A DG.
Updated for procedure rev., minor N 12/19/01 4,6-9 L. Pauley pen/ink changes. Validation N/A based on JPM 77-4AP.
1 Incorporated pen/ink changes; no impact N .8/21/02 4, 6-9 J P Kearney on JPM flow V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM #77-4AP2 Page 3 of 9 Rev. 1 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task:
Perform D/G Load Test on 1A-A D/G JArrAtask#: 0640020101 0640040101 0640060101 (RO)
K/A Ratings:
064A4.01 (4.0/4.3) 064A2.02 (2.7/2.9) 064A4.02 (3.3/3.4) 064A4.03 (3.2/3.3)
Task Standard:
Perform D/G Operability Test per 1-SI-OPS-082-007.A, specifically manually start and load the D/G.
Trip D/G due to erratic voltage control.
Evaluation Method: Simulator X In-Plant -
Performer:
NAME Start Time Performance Rating: SAT UNSAT Performance Time Finish Time K-Evaluator: /
SIGNATURE DATE COMMENTS
JPM #77-4AP2 Page 4 of 9 Rev. 1 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Sequenced steps identified by an "s"
- 2. Any UNSAT requires comments
ý_ý3. Acknowledge any associated alarms.
- 4. Initialize Simulator in IC: #8.
- 5. A Console operator will be required to play role of AUO on Radio.
- 6. Insert malfunction IMF EG05A to cause voltage/vars to be erratic.
- 7. Operator may request assistance during D/G start and loading at step 5 and 18. A simulator operator needs to be present to perform this timing.
- 8. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. 14 minutes Local Tools/EquipmentlProcedures Needed:
- 1. 1-SI-OPS-082-007.A, Through Section 6.1 and Appendix "C".
- 2. "Signed off' copy of entire section 4.
References:
I Reference Title Rev No.
- 1. 1-SI-OPS-082-007.A Electrical Power System Diesel Generator 28 1IA-AI
JPM Page#77-4AP2 5 of 9 Rev. I READ TO OPERATOR Directions to Trainee:
All control room steps I will explain the initial conditions, and state the task to be performed.
on other actions when shall be performed for this JPM. I will provide initiating cues and reports the objective for this job directed by you. When you complete the task successfully, you indicate to me when you understand your performance measure will be satisfied. Ensure completed your assigned task return the handout sheet assigned task. To indicate that you have I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is -57% and unit 2 is 100% RTP.
been completed on all the B
- 2. All systems are OPERABLE, except for the lA-A D/G, 0-GO-16 has Tr. equipment.
has been removed.
- 3. Maintenance has been completed on the 1A-A D/G and the clearance The D/G has been rolled and is in standby alignment using 0-SO-82-1.
- 4. and all
- 5. The AUO at the D/G building has completed Appendix A of 1-SI-OPS-082-007.A parameters are within limits.
position.
- 6. The Ul Control Room AUO has verified breaker 1932 is in the Disconnect
- 7. D/G-DAQ has been installed per Appendix J
- 8. Room fire protection is in service INITIATING CUES:
1A-A DIG, all that
- 1. The Ul US/SRO has reviewed the completed work package for the remains is to perform 1-SI-OPS-082-007.A for the PMT.
- 2. You are an extra unit operator and have been assigned to perform The PMT requires the AMBIENT MANUAL START method for testing.
3.
- 4. Notify the US when the test is complete.
K->
JPM #77-4AP2 Page 6 of 9 Rev. 1 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP/SANDAT STEP 1.: Operator obtains a copy of the appropriate procedure. SAT UNSAT NOTE: Initial conditions cover steps up to transition to App "C".
Start Time STANDARD: Operator obtains a. copy of 1-SI-OPS-082-007.A. Performance of task will start with Appendix C.
STEP 2.: Ensure 0-HS-82-18 1A-A DIG mode selector switch in the UNIT __ SAT position.
UNSAT STANDARD: 0-HS-82-18 in UNIT position on O-M-26. Green light ON.
STEP 3.: Place 1-HS-57-47 DIG 1A-A Synchronize Switch in the SYN position. __ SAT UNSAT NOTE: O-EI-82-5 and O-XI-82-3 will indicate running voltage & frequency.
Critical Step STANDARD: 1-HS-57-47 in "SYN" position on O-M-26 STEP 4. NOTIFY D/G-DAQ Operator to START the D/G-DAQ _ SAT UNSAT NOTE: Operator should coordinate the start of the D/G-DAQ just prior to DIG start actuation.
Cue Console operatorPlay role of D/G-DAQ operator: D/G-DAQ computeris running.
STANDARD: Operator notifies the D/G-DAQ operator to start the D/G-DAQ.
JPM #77-4AP2 Page 7 of 9 Rev. 1 Job Performance Checklist:
STEP/STANDARD SATIUNSAT SAT STEP 5.: Proceed with the countdown: 3,2,1, start and DEPRESS 0-HS-82-16A DG 1A-A Emergency Start Switch. UNSAT NOTE: Role play as extra operator with stop watch and start watch when 0-HS-82-16A is depressed. Critical Step STANDARD: 0-HS-82-16A momentarily depressed. Green light will go "out" and red light will come "on" above DIG mimic. [Not critical: D/G running alarm will ANN to indicate DIG > 40 rpm. Incoming voltage and frequency are verified on 0-EI-82-4 and 0-XI-82-2.]
ENSURE 1-FCV-67-66, ERCW cooling water supply valve is OPEN. SAT STEP 6.:
UNSAT STANDARD: ERCW valve i-FCV-67-66 red light comes "on" and green light goes "out' on 0-M-27A panel.
t SAT STEP 7.: RECORD the steady state values for the following:
0-EI-82-4, DG 1A-A incoming Voltage. UNSAT 0-XI-82-2, DG 1A-A incoming Frequency.
Time from stop watch.
NOTE: Volt meter will be erratic and not steady.
Cue: If operatorasks for SRO direction: Act as SRO andask for their recommendation and concur with it.
STANDARD: Operator observes D/G voltage (0-EI-82-4) is erratic and not steady.
Frequency (0-XI-82-2) is > 58.8 Hz and < 61.2 Hz RECORD Voltage Regulator Control Current. SAT STEP 8.:
UNSAT Cue: Voltage Regulator Control Currentis 1.8 dc amps.
STANDARD: Operator records Voltage Regulator Control Current.
JPM Page #77-4AP2 8 of 9 Rev. 1 Job Performance Checklist:
SAT/UNSAT STFP/STANDARD I Emergency stop Diesel Generator 1A-A using 0-HS-82-17A. SAT STEP 9.:
UNSAT NOTE: Operator may elect to do a normal stop. This will require the performance of steps 10 thru 13 to gain manual control. If Critical Step Emergency stop is used N/A JPM steps 10 thru 13.
STANDARD: Operator depresses emergency stop button for Diesel Generator 1A-A, or initiates a normal stop.
ENSURE DIG 1A-A 86 LOR red light DARK, at DIG local relay panel. _ SAT STEP 10.:
UNSAT Cue: Role Play as DIG operator- 86 LOR local red light is not LIT.
STANDARD Operator verifies red light on 86 LOR at DIG is not illuminated.
STEP 11 .: RESET 86 LOR lockout relay, on D/G local relay panel and verify reset __ SAT by amber light 0-XI-82-19 illuminated on 0-M-26.
UNSAT NOTE: When the DIG AUO is requested to reset 86LOR, the Console operator should insert MRF EGRO7 RESET to reset 86LOR and Critical Step notify operator - 86 LOR is reset.
STANDARD: 86 LOR is reset and amber light on 0-M-26 is verified LIT.
RECORD from the D/G-DAQ computer the time required to achieve __ SAT STEP 12.:
> 58.8 HZ and Ž 6800 Volts.
Cue: Time was 9.5 seconds for D/G-DAQ.
STANDARD: Operator ensures the DG accelerates to at least 900 rpm (58.8 - 61.2 Hz) and Voltage and frequency are within limit within the required 10 seconds. (Evaluator can sign for Tech Support). Operator may N/A this step due to erratic voltage reading.
JPM #77-4AP2 Page 9 of 9 Rev. 1 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP/SANDAT STEP 13.: Place 0-HS-82-14, DG lA-A Control Start-Stop Switch in the STOP SSAT position momentarily.
UNSAT Cue: To expedite the JPM, Inform operator that the DIG >40 rpm Critical Step "running light" has cleared STANDARD: Operator momentarily places 0-HS-82-14 in the STOP position, verifies red light OFF and green light ON above HS.
STEP 14.: Inform US/SRO of Emergency OR Normal stop of Diesel Generator IA- __ SAT A.
UNSAT Cue: US/SRO instructs operatorto return to his/hers normal duties until Stop Time maintenance requests assistance.
STANDARD: Operator informs US/SRO of Emergency stop of Diesel Generator 1A-A.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SURVEILLANCE INSTRUCTION I-SI-OPS-082-007.A ELECTRICAL POWER SYSTEM DIESEL GENERATOR IA-A Revision 28 QUALITY RELATED PREPARED/PROOFREAD BY: CHERYL D. MORRIS RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J.A. DVORAK EFFECTIVE DATE: 23 Aug 02 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION: Revised to incorporate RT-020103, which added a reminder to steps in appendices D and G to hold test pushbuttons until reaching the step to release them. This is a non-intent change. Also deleted Appendix J and references due to the creation of 0-MI-EDG-082-001.0, Installation and Removal of the DIG Data Acquisition (DAQ) System. Also incorporated OTOC for 2-SI-OPS-082-007.A,B to allow performing a PMT-required ambient start to fulfill a periodic non-ambient start requirement. These are intent changes. Added location for K609 relay. This change is non intent.
ý1
SQN ELECTRICAL POWER SYSTEM i1-SI-OPS-082-007.A DIESEL GENERATOR 1A-A Rev: 28 1 Page 2 of 77 TABLE OF CONTENTS Page 1 of 2 Section Title Page TABLE OF CONTENTS ................................................................................................ 2
1.0 INTRODUCTION
............................................................................................................ 4 1.1 P u rp o s e .................................................................................................................... 4 1.2 Scope ....................................................................................................................... 4 1.2.1 Operability Test to be Performed ................................................................ 4 1.2.2 Requirements Fulfilled ................................................................................. 5 1.2.3 Mode ............................................................................................................. 5 1.3 Frequency/Conditions .............................................................................................. 5
2.0 REFERENCES
............................................................................................................... 6 2.1 Performance References ....................................................................................... 6 2.2 Developmental References ...................................................................................... 6 3.0 PRECAUTIONS AND LIMITATIONS ............................................................................. 8 4.0 PREREQUISITE ACTIONS ........................................................................................ 10 4.1 Preliminary Actions ................................................................................................. 10 4.2 Measuring and Test Equipment, Parts, and Supplies ............................................. 11 4.3 Field Preparations ................................................................. 11 4.4 Approvals and Notifications .................................................................................... 12 5.0 ACCEPTANCE CRITERIA .......................................................................................... 14 6.0 PERFORMANCE ........................................................................................................... 15 6.1 Ambient Start Performance ................................................................................... 15 6.2 Non-Ambient Performance ................................................................................... 23 7.0 POST PERFORMANCE ACTIVITIES ........................................................................ 30
TABLE OF CONTENTS Page 2 of 2 Title Page Section APPENDICES APPENDIXA: lA-A DIESEL GENERATOR PRE-RUN CONDITION 31 C HE C KO UT .......................................................................................
APPENDIX B: IA-A DIESEL GENERATOR RUNNING CONDITION 37 C HE C KLIS T .......................................................................................
42 APPENDIX C: AMBIENT MANUAL START METHOD ...............................................
APPENDIX D: AMBIENT SIMULATED LOSS OF OFFSITE 45 POW ER START METHO D.................................................................
APPENDIX E: AMBIENT SI ACTUATION TEST SIGNAL 53 STA RT MET HO D ...............................................................................
57 APPENDIX F: NON-AMBIENT MANUAL START METHOD ......................................
APPENDIX G: NON-AMBIENT SIMULATED LOSS OF OFFSITE 60 POW ER START METHO D.................................................................
APPENDIX H: NON-AMBIENT SI ACTUATION TEST SIGNAL 68 START METHOD ..........................................
APPENDIX I: VERIFICATION OF DIESEL GENERATOR RETURN 72 TO STANDBY READINESS ...............................................................
76 SOURCE NOTES ............................................................................................................
ATTACHMENT ATTACHMENT 1: DIESEL GENERATOR CAPABILITY CURVE FOR CONTINUOUS DUTY
1.0 INTRODUCTION
1.1 Purpose of This Instruction provides the steps necessary to demonstrate OPERABILITY of 1A-A Diesel Generator in accordance with frequency and requirements Technical Specification Surveillance Requirements. [C.2]
with This instruction also performs monthly inspections in accordance manufacturers recommendations.
1.2 Scope 1.2.1 Operability Test to be Performed test The surveillance test to be performed in a 31 day interval staggered basis involves the following verifications: [C.2]
A. Fuel level adequate in the engine-mounted day tanks.
B. Fuel level adequate in the 7-day tank.
to the C. Fuel transfer pump starts and transfers fuel from the storage system engine mounted fuel tanks.
with startup on D. Diesel Generator (D/G) is started by one of the following signals each signal verified at least once per 124 days.
- 1. Manual
- 2. Simulated Loss of Offsite Power
- 3. SI (ESF) Actuation Test Signal equal to E. DIG starts from ambient conditions and achieves in less than or 10 seconds voltage and frequency of _>6800 volts and _>58.8 Hz and achieves a steady state voltage and frequency of 56800 volts and _<7260 volts and _ 58.8 and < 61.2 Hz. All other DIG starts for the purpose of this surveillance testing, may be preceded by an engine idle start and gradual acceleration to synchronous speed.
SQN ELECTRICAL POWER SYSTEM i-SI-OPS-082-007.A DIESEL GENERATOR IA-A Rev: 28 I Page 5 of 77 1.2.1 Operability Test to be Performed (Continued)
NOTE In accordance with Reg. Guide 1.9, the load requirement of between 3.96 MW and 4.4 MW may be reduced to Ž_2.2 MW when both units are in MODE 5 or 6. All four DIGs must be within test frequency at a load between 3.96 MW and 4.4 MW prior to either unit entering MODE 4.
F. Generator is synchronized, loaded to between 3.96 MW and 4.4 MW in
- 60 seconds and operates for Ž> 60 minutes once per 184 days.
All other loading for the purpose of this surveillance testing may be gradual to between 3.96 MW and 4.4 MW for Ž> 60 minutes.
G. DIG is realigned to provide standby power to associated shutdown board upon completion of the testing.
1.2.2 Requirements Fulfilled This Instruction fulfills the following Technical Specification (TS) Surveillance Requirements (SR):
A. SR 4.8.1.1.2.a.1 through 4.8.1.1.2.a.6 (for D/G tested).
B. SR 4.8.1.2 (Partial) (for DIG tested).
1.2.3 Mode A. Applicable Modes - All B. Performance Modes - All 1.3 Frequency/Conditions A. This test must be performed on a periodic basis at least once per 31 days.
B. This test may be performed as a Post-Maintenance-Test (PMT) to prove operability of the D/G upon work completion.
2.0 REFERENCES
2.1 Performance References A. System Instructions
- 1. 0-SO-82 (Series) Diesel Generators B. Other Surveillance Instructions
- 1. 0-SI-OPS-082-007.M, Diesel GeneratorSurveillance Frequency
- 2. SI-102 (Series), Diesel GeneratorInspections C. Maintenance Instructions
- 1. 0-MI-EDG-082-001.0, Installation and Removal of the DIG Data Acquisition (DAQ) System 2.2 Developmental References A. TVA Drawings
- 1. 45N765-1 through 5
- 2. 45N767-1 through 5 B. Technical Specifications
- 2. Surveillance Requirement 4.8.1.2 C. Regulatory Guide 1.108 D. Regulatory Guide 1.9 E. FSAR Section 8.0, ElectricalPower F. S 1-7, ElectricalPower System: Diesel Generators G. Technical Standard 04.06.07.14.03 H. RIMS L44 870227 811 (provided background data needed to generate Attachments A, B, and C capability curves).
SQN ELECTRICAL POWER SYSTEM i1-SI-OPS-082-007.A DIESEL GENERATOR 1A-A Rev: 28 1 Page 7 of 77
/
2.2 Developmental References (Continued)
I. SSP-13.3, Appendix B, AirPollution Control J. P318-0020, tab 61 Vendor manual K. Recommended Shutdown Limits for SQN DG's signed by Engine Systems Inc.
(ESI) dated 10-21-97 (VM change 5584)
3.0 PRECAUTIONS AND LIMITATIONS vents) open A. Operating the Diesel engines without air box drains (crankcase could damage the engines.
B. Operating the Diesel engine with high jacket water temperature
(> 205'F) could damage the engine.
could damage the C. Operating the Diesel engine with < 20 psi lube oil pressure engine.
extended periods of D. Operating the generator system at speeds < 850 rpm for to the time with exciter regulator in operation could cause damage exciter-regulator field.
room.
E. Fire protection system shall be available for 1A-A DIG generator should not F. In the event of a crankcase high pressure trip, the diesel Maintenance.
be restarted until a thorough checkout has been performed by to opening the top Diesel engine should be allowed to cool for two hours prior from hot oil deck cover or handhole, to prevent the possibility of an explosion vapors.
be observed G. The prestart rolling requirements of 0-SO-82 series must prestart rolling (unless waived by SM) to check for water in the cylinders. If DG room upon requirements are waived, no personnel are required in the DG start DG start as an ambient start must be performed and the required readings can be obtained in the MCR (panel O-M26-A).
not be H. In accordance with FSAR 8.3-11 more than one D/G will operated in parallel with its 6.9kV unit board at the same time.
generator local I. Care should be used when changing lamps on the diesel for rendering control panel. A short circuit in a lamp socket has the potential the diesel generator inoperable.
five minutes after J. Diesel engine exhaust stack should be monitored within or startup. Ifthe equipment is still emitting black smoke, a malfunction or misadjustment is indicated and the equipment should be readjusted shutdown for repairs as applicable. If black smoke persists and be notified.
equipment cannot be shutdown, Site Environmental shall darker Black smoke is defined for this precaution as smoke significantly than is normal from previous experience.
(CONTINUED) 3.0 PRECAUTIONS AND LIMITATIONS 43T(L) switch in test position will make the associated DIG inoperable K. Placing (TS LCO 3.8.1.1. or 3.8.1.2).
/overcurrent white light for the L. Breaker position disagreement supply breakers on the Normal, Alternate, and Emergency momentarily as the 6900V Shutdown Boards, may illuminate breaker closes.
operation in parallel mode, power M. When the diesel generator is in capacitor switching, CSST switching activities (large motor starts, synchronizing activities, etc.)
tap changer operations, generator imbalance or overcurrent may result in actuation of the phase relay.
Date 4.0 PREREQUISITE ACTIONS NOTE Throughout this Instruction where an IF/THEN statement exists, the step should be NIA if condition does not exist.
4.1 Preliminary Actions
[1] ENSURE Instruction to be used is a copy of the effective version.
[2] ENSURE Precautions and Limitations, Section 3.0, has been reviewed.
[3] IF diesel generator has been inop (tagged) for maintenance, THEN ENSURE diesel generator is in standby mode, in accordance with 0-SO-82-1. [C.3]
[4] COORDINATE performance of this test with DIG Outage Coordinator, assigned per D/G outage schedule supplied by Daily Scheduling.
(N/A if not assigned.)
are
[5] VERIFY necessary portions of all outage work/test items complete before running operability test. Coordinate with DIG Outage Coordinator or Daily Scheduling.
[6] VERIFY necessary personnel are stationed at DIG building to complete any remaining (running) requirements of other Surveillance Instructions in progress via DIG Outage Coordinator, as applicable.
[71 IF performing an Ambient Start AND use of the D/G-DAQ is desired for start timing, THEN ASSIGN Electrical Maintenance or Systems Engineering responsibility for operating the D/G-DAQ, AND NOTIFY responsible group to COMPLETE 0-MI-EDG-082-001.0, Installation and Removal of the DIG Data Acquisition (DAQ) System.
Date 4.2 Measuring and Test Equipment, Parts, and Supplies NOTE Ifperforming an ambient start, AND using the DIG DAQ for start timing, a stopwatch must be used as a backup. If the DAQ is NOT being used, two stopwatches must be used.
[1] IF performing an ambient start, OR timing of DG loading required, THEN El OBTAIN stopwatch(es).
12] IF performing Ambient Start AND use of the D/G-DAQ is desired for start timing, THEN REFERENCE 0-MI-EDG-082-001.0, Installation and Removal of the DIG Data Acquisition (DAQ) System for El listing of required M&TE.
[3] IF an Engine Cylinder Thermocouple is known or suspected to be inoperable, THEN OBTAIN a pyrometer for surface temperature El measurement from M&TE.
4.3 Field Preparations
[1] ENSURE prestart rolling requirements of 0-SO-82-1 El have been met, OR OBTAIN waiver from SM.
Prestart rolling waived for this performance.
(N/A if not waived.)
SM Signature
[2] IF SM waived prestart rolling requirements, THEN NOTIFY the Control Room Operator that the DIG room 1A-A is to be cleared of ALL personnel prior to startup of the diesel AND the DG start readings will be obtained from the MCR (panel O-M-26A).
[3] ENSURE Fire protection system is available for DIG Room lA-A.
ELECTRICAL POWER SYSTEM 1-SI-OPS-082-007.A SQN DIESEL GENERATOR 1A-A Rev: 28 Page 12 of 77 1I Date 4.4 Approvals and Notifications
[1] OBTAIN Senior Reactor Operators (SRO) approval from both units prior to beginning this surveillance.
/ i Unit 2 SRO I Date / Time Unit 2 SRO Date Time NOTE If an ambient start is required to satisfy PMT requirements, this start can be used to fulfill periodic ambient or non-ambient start requirements.
[2] PERFORM ONE of the following three substeps (N/A the other two):
[a] IF performance of this instruction is to satisfy a PMT, THEN PERFORM Section 6.1 for Ambient Start OR PERFORM Section 6.2 for Non-Ambient Start.
[b] IF the calendar date is January or July, and this is the first performance during the month, THEN PERFORM Section 6.1, Ambient Start Performance.
Date 4.4 Approvals and Notifications (cont.)
[c] IF the calendar date is February, March, April, May, June, August, September, October, November, or December, OR IF the calendar date is January or July, and this is NOT the first performance of the month, THEN PERFORM Section 6.2, Non-Ambient Performance.
[3] IF Start method requires an "SI Actuation Test Signal" THEN ENSURE Unit 1 Train "A"SSPS is in service.
U-1 SRO
Date 5.0 ACCEPTANCE CRITERIA in A. The DIG is synchronized, then loaded to between 3.96 MW and 4.4 MW less than or equal to 60 seconds. Load requirements may be reduced to
_>2.2 MW with both units in mode 5 or 6.
to B. Fuel Oil Transfer Pumps start and transfer fuel from the DIG 7-Day Tank the engine Day Tank.
C. The fuel oil in the DIG Day Tank is verified _Ž 250 gallons and the fuel oil level in the 7-Day Tanks is verified Ž_4.7 feet.
with D. The Diesel Generator (D/G) is started by one of the following signals startup on each signal verified at least once per 124 days.
- 1. Manual
- 2. Simulated Loss of Offsite Power
- 3. SI (ESF) Actuation Test Signal equal to 10 E. DIG starts from ambient conditions and achieves in less than or seconds voltage and frequency of _> 6800 volts and Ž_58.8 Hz and achieves a steady state voltage of _Ž6800 volts and < 7260 volts and frequency of
> 58.8 and _ 61.2 Hz. All other D/G starts for the purpose of this surveillance testing, may be preceded by an engine idle start and gradual acceleration to synchronous speed.
F. If specific acceptance criteria stated in the instruction steps are not met, notify the SM as soon as practical after observation_ of the noncompliance.
Date 6.0 PERFORMANCE 6.1 Ambient Start Performance Start is defined as a NOTE For purposes of this Instruction, Ambient from zero speed and DIG startup where the machine is started and jacket water.
ambient temperature conditions of lube oil 6800 volts and Ž_58.8 Hz in When started, the machine is brought to _Ž synchronized to the less than or equal to 10 seconds. Then, once 3.96 and 4.4 MW in energized shutdown board, it is loaded between once per 184 days in at least
< 60 seconds. Ambient Start is required 5.
accordance with SR 4.8.1.1.2.a.4 and for duration of test.
[1] DISPATCH an AUO to DIG building A,
[2] DIRECT DIG building AUO to perform Appendix DIG Pre-Run Condition Checkout.
THEN
[3] IF D/G-DAQ is to be used for start timing, WV ENSURE DG-DAQ has been installed.
board
[4] IF breaker E120 is installed in its shutdown compartment, THEN position.
ENSURE breaker Eno is in the DISCONNECT parameters within
[5] ENSURE Appendix A completed with all Start.
acceptable ranges for Ambient
SON ELECTRICAL POWER SYSTEM i-SI-OPS-082-007.A DIESEL GENERATOR 1A-A Rev: 28 1 Page 16 of 77 Date 6.1 Ambient Start Performance (Continued)
NOTE Steps [6], [7] and [8] choose the start method and direct the performer to the appropriate appendix.
[6] IF any of the following conditions exist:
A. Calendar date is January or July, OR B. Performance is a Post-Maintenance-Test (PMT) that requires an ambient manual start, THEN PERFORM Appendix C, Ambient Manual Start Method.
[7] IF Performance is a Post-Maintenance-Test (PMT) that requires an Ambient Simulated Loss of Offsite Power start, THEN PERFORM Appendix D, Ambient Simulated Loss of Offsite Power Start Method.
[8] IF Performance is a Post-Maintenance-Test (PMT) that requires an Ambient SI Actuation Test Signal start, THEN PERFORM Appendix E, Ambient SI Actuation Test Signal Start Method.
Date 6.1 Ambient Start Performance (Continued)
[9] PLACE i0-HS-82-18], DG 1A-A Mode Selector Switch in the PARALLEL position.
[10] ADJUST [0-HS-82-1 31, DG 1A-A Speed Control Switch to obtain a synchroscope indication of slowly rotating in the FAST. direction.
[11] ENSURE ro-HS-82-12, DG 1A-A Voltage Regulator Switch in the PULL-P-AUTO position, AND ADJUST to match incoming voltage with running voltage.
must be loaded NOTE 1 With Ambient Start being performed, the generator 1912 is closed.
between 3.96 and 4.4 MW immediately after breaker of Attachment 1 NOTE 2 During steps [13] and [14].the Load vs. VAR limits The load must be observed when loading the Diesel Generator.
reduced to requirement of between 3.96 and 4.4 MW may be
>_2.2 MW if both units are in MODE 5 and/or 6.
at the 12 o'clock NOTE 3 When closing the Diesel Generator Output Breaker of rotation of the position consideration should be given to the speed to close the syncroscope needle and the response time it takes breaker.
K->
Date 6.1 Ambient Start Performance (Continued) at NOTE 4 The following table provides an approximation of expected values various DG loading plateaus. These values shall be monitored to provide alternative M-26 indications thus ensuring proper diesel generator loading. The values given are calculated approximations and may vary due to system variables. (e.g. If amps are 370 and Mvar have been adjusted to 2.0 Mvar then MW should be approx. 4.0.)
MW Mvar Amps (O-EI-82-10A) (O-EI-82-11IA) (0-EI-82-9B) 0.5 MW 0.5 Mvar 60 Amps 1.0 MW 0.75 Mvar 100 Amps 2.0 MW 1.0 Mvar 185 Amps 3.0 MW 1.0 Mvar 260 Amps 4.0 MW 1.5 Mvar 350 Amps 4.0 MW 2.0 Mvar 370 Amps 4.2 MW 1.5 Mvar 370 Amps 4.2 MW 2.0 Mvar 385 Amps 4.4 MW 1.5 Mvar 385 Amps 4.4 MW 2.0Mvar 400Amps 4.8 MW* 1.5 Mvar 415 Amps 4.8 MVV* 2.0 Mvar 430 Amps 2 Hr rating limitations apply
[12] WHEN the Synchroscope DG lA-A ro-XI-82-11 indicates 12 o'clock position, THEN CLOSE breaker [1912] via [1-HS-57-46A1 1912 DG 1A-A to SD BD lA-A, AND START stopwatch.
NOTE Steps [13] and [14] must be completed within 60 seconds.
[13] IMMEDIATELY LOAD DIG 1A-A to Ž_1.0 MW by performing the following:
[a] PLACE [O-HS-82-131, DG lA-A Speed Control Switch in RAISE and obtain _> 1.0 MW on
[0-EI-82-10A1 DG 1A-A Megawatts. E
[b] ADJUST rO-HS-82-121, DG lA-A Voltage Regulator Switch to 0.75 MVARS Outgoing as indicated on [0-EI-82-11A, E
[c] ENSURE DG indications (MW, Mvars, and Amps) match the expected indications of Table in NOTE 4. E
[d] IF DG indications not as expected THEN NOTIFY US.
[
SQN 1
ELECTRICAL POWER SYSTEM DIESEL GENERATOR 1A-A i -SI-OPS-082-007.A Rev: 28 Page 19 of 77 Date
--1 I 6.1 Ambient Start Performance (Continued)
CAUTION Care must be taken to not exceed 4.84 MW (2-hour rating).
NOTE 1 Adjustment of MVARS may be performed simultaneously with DG loading to ensure MVARS are maintained within limits.
NOTE 2 Table in Note 4 (prior to step [12]) should be referenced to ensure proper indications during loading of DG.
[14] IMMEDIATELY LOAD D/G 1A-A to Ž 3.96 and *4.4 MW (>2.2 MW if both units in modes 5 or 6) by performing the following:
[a] PLACE ro-HS-82-131, DG 1A-A Speed Control Switch in RAISE and obtain Ž> 3.96 and < 4.4 MW on rO-EI-82-10AI DG 1A-A Megawatts. El
[b] ADJUST !O-HS-82-12, DG 1A-A Voltage Regulator Switch to Ž!0.75 and < 2.37 MVARS Outgoing as indicated on TO-EI-82-11AI DG 1A-A Megavars. []
[15] RECORD the following:
A. Loading time Seconds B. Load achieved rO-EI-82-10A1.
MW C. Time load achieved.
Time ACCEPTANCE CRITERIA: The DIG is syn chronized, then loaded to between 3.96 and 4.4 M1W in less than or equal to 60 seconds.
NOTE Appendix B Table I Running Condition Checklist provides DG operating parameters and limits which must be monitored at all times when the DG is running. DG System Inspections (Table 2) may be performed at any point after DG full load is attained. DG Running Condition data (Table 1) should be taken approximately 45 minutes after DG full load is attained.
[16] NOTIFY Diesel Generator Building assigned AUO to PERFORM Appendix B, AND PROVIDE DIG Building AUO time DIG achieved final load. (Step [15])
Date .
6.1 Ambient Start Performance (Continued) 60
[17] MAINTAIN load at predetermined test value for Ž>
minutes by adjusting ro-HS-82-131, DG 1A-A Speed Control Switch, as needed.
requirement met as follows:
[18] ENSURE at-load time RECORD time test load achieved._ _
[a] Time
[b] RECORD finish time. Time
[c] SUBTRACT [a] from [b] AND E1 RECORD results.
Min DIG lA-A operated with a load of between ACCEPTANCE CRITERIA: 3.96 and 4.4MW for Ž-60 minutes. Load requirement in may be reduced to Ž 2.2 MW with both units mode 5 or 6.
power condition.
CAUTIOIN Overshooting load drop will result in a reverse with DG NOTE Adjustment of Mvars may be performed simultaneously within limits.
unloading to ensure Mvars are maintained 1A-A
[19] UNLOAD D/G IA-A using [o-HS-82-13] DG Speed Control Switch, to-< 0.5MW while observing
[o-EI-82-10AI, DG 1A-A Megawatts.
21
[20] REDUCE reactive load to near zero via ro-HS-82-1 11 DG 1A-A Voltage Regulator Switch.
lA-A
[21] IF 1-SI-TFT-082-102.A, Functional Test of D/G Protective Relays, is to be performed, THEN COORDINATE with TPS personnel AND PERFORM 1-S I-TFT-082-102.A.
Date -
6.1 Ambient Start Performance (Continued)
[22] OPEN breaker 19121, DIG IA-A to SD BD 1A-A breaker.
[23] ENSURE D/G voltage Ž6800 and
- 7260 volts on ro-EI-82-41 AND ENSURE D/G frequency Ž!58.8 and *61.2 Hz on [O-XI-82-21.
fl of NOTE The DIG will operate at rated speed for 2 seconds upon initiation following step before decelerating back to idle speed.
[24] PLACE rO-HS-82-14, D/G 1A-A Control Start-Stop Switch in the STOP position momentarily.
[25] PLACE rO-HS-82-18, D/G Mode Selector Switch in UNIT position.
[26] NOTIFY AUO assigned to DG to obtain engine crankcase oil levels at idle speed condition per Appendix B.
[27] PLACE il-HS-57-471, Synchronize Switch in OFF position.
[28] NOTIFY Radiochemical Laboratory of need to sample engine-mounted fuel tanks (day tanks) for condensate in accordance with Technical Standard 04.06.07.14.03 and TS SR 4.8.1.1.2.b.
Date 6.1 Ambient Start Performance (Continued)
NOTE Steps [29], [30] and [31] need to be verified after 1A-A DIG is no longer running.
[29] VERIFY [0-LI-18-61111 Ž 250 gals, Diesel Generator Day Tank 1 Level (local on tank). .
Gals
[30] VERIFY ro-LI-18-76/11 Ž-250 gals, Diesel Generator Day Tank 2 Level (local on tank).
Gals
[31] ENSURE ro-LI-18-38] -4.7 ft level of fuel oil in 7-Day Tank (local at west end of D/G).
Ft
[32] PERFORM Appendix I, Verification of Diesel Generator Return to Standby Readiness.
[33] ENSURE the following RECORDED in o-SI-OPS-082-007.M:
A. DIG start.
El B. Method used.
C. Date of ambient start and due date for next El required ambient start. El D. Return-to-service time, if test method caused inoperability of DIG. (NA otherwise)
ACCEPTANCE CRITERIA: Each step [19] through [33] was completed satisfactorily and the D/G response was as prescribed.
APPENDIX C Page 1 of 3 Date.
AMBIENT MANUAL START METHOD and NOTE All steps in this Appendix refer to lA-A Diesel Generator (D/G) are performed from Main Control Room Panel 0-M-26A unless otherwise specifically noted.
E1] ENSURE iO-HS-82-181 D/G 1A-A Mode Selector Switch in the UNIT position.
[2] PLACE l1-HS-57-471 DG 1A-A Synchronize Switch in the SYN position.
NOTE 1 Close communication and coordination with field personnel is required to accomplish following step. Parts [a], [b], and [c] are to be performed such that D/G-DAQ is started just prior to DIG start actuation, if used.
is NOTE 2 A stopwatch must be used as a backup to the DIG DAQ. Ifthere any timing discrepancy between the two, the DAQ should take precedence due to its superior accuracy.
time the NOTE 3 Ifthe DIG DAQ is not used, two stopwatches must be used to DIG start.
NOTE 4 To ensure consistency and accuracy when timing DG starts the following guidelines are provided:
1 -Start stopwatch when emergency start handswitch depressed (manual start).
2 -Monitor voltage until the meter indicates > 6800 volts (voltage stabilizes before frequency).
3 -Monitor frequency until meter indicates > 58.8 Hz STOP the watch.
[3] PERFORM following to initiate DIG start signal:
[a] IF the D/G-DAQ is to be used, THEN NOTIFY D/G-DAQ Operator to START D/G-DAQ.
'-'--V
SIQN ELECTRICAL POWER SYSTEM 1-SI-OPS-082-007.A DIESEL GENERATOR 1A-A Rev: 28 I Page 43 of 77 I
APPENDIX C Page 2 of 3 Date
[b] PROCEED with countdown: 3,2,1 START.
[c] DEPRESS ro-HS-82-16A1, DG IA-A Emergency Start Switch, AND START stopwatch.
[4] VERIFY rI-FCV-67-66, ERCW cooling water supply valve is OPEN.
[5] RECORD steady state values for following:
A. ro-EI-82-41 DG 1A-A Incoming Voltage.
Reading B. ro-Xl-82-21 DG 1A-A Incoming Frequency.
Reading C. Time from Stopwatch(es):
Seconds Stopwatch ID Number Seconds Stopwatch ID Number ACCEPTANCE CRITERIA: DIG 1A-A achieves steady state generator voltage of Ž 6800 and
- 7260 volts and frequency of Ž> 58.8 Hz and
- 61.2 Hz.
NOTE Voltage Regulator Current Ammeter is in panel 1 of exciter cabinet.
[6] RECORD Voltage Regulator Control Current:
Reading ACCEPTANCE CRITERIA: Voltage Regulator Control Current between 1.0-2.5 dc amps. The voltage regulator card must be functioning properly to consider DG operable.
[7] ENSURE DIG 1A-A [86LOR1 red light NOT ILLUMINATED, at DIG local relay panel.
APPENDIX C Page 3 of 3 Date .
on NOTE Do not hold r86LOR1 in RESET position if it does not latch first attempt. Coil failure may result if relay is held in RESET position.
[8] RESET 86L-O.R Lockout Relay, on D/G local relay panel.
[9] VERIFY r86LOR1 is reset by amber light ro-XI-82-19! ILLUMINATED on 0-M-26A.
[10] IF D/G-DAQ was used, THEN RECORD following from D/G-DAQ trace:
Time required to achieve Ž>58.8 Hz and Že 6800 volts:
Seconds DG-DAQ Operator in ACCEPTANCE CRITERIA: DIG 1A-A starts from ambient condition and achieves less than or equal to 10 seconds generator voltage Ž> 6800 volts and frequency of Ž 58.8 Hz.
[11] RECORD start as ambient in O-SI-OPS-082-007.M.
112] RETURN to Section 6.1 Step [9] of this Instruction.
JPM # 34 Page 1 of 7 Rev. 7 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 34 LOSS OF SECONDARY HEAT SINK Original Signatures on File PREPARED/
REVISED BY: Date/
- Date/
VALIDATED BY:
APPROVED BY: Date/
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM # 34 Page 2 of 7 Rev. 7
- J NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION V AFFECTED REVISED BY:
S.... .. .... mI I
- w L 5 Transfer from WP. Minor enhancements. N 8/19/94 All HJ Birch Y 9/15/95 All HJ Birch 6 Incorporate Rev B changes. Chgd performance time to 6 min based on validation time.
pen/ink FR-H.1 Rev chg only N 1/16/96 4 HJ Birch N 5/13/98 4 HJ Birch pen/ink FR-H.1 Rev chg which chgd criteria loss of heat sink.
FR-H.1 Rev chg only N 8/22/00 4 SR Taylor pen/ink N 11/28/01 4,6 L. Pauley pen/ink FR-H.1 Rev change only, correct typo N 8/22/02 4,6 J P Kearney 7 Incorporated pen/ink changes
<7 V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM # 34 Page 3 of 7 Rev. 7 SEQUOYAH NUCLEAR PLANT RO/SRO K-> JOB PERFORMANCE MEASURE Task: Loss of Secondary Heat Sink JA/TA task # : 3110060601 (RO) 0100040101 (RO)
K/A Ratings:
E05EK1.2 (3.9/3.5) E05EK1.3 (3.9/4.1) E05EK2.1 (2.7/3.9)
E05EK3.1 (3.4/3.8) E05EK3.2 (3.7/4.1)
E05EK2.2 (3.9/4.2)
E05EA1.1 (4.2/4.0) E05EA1.2 (3.7/4.0)
E05EK3.3 (4.0/4.1)
E05EA2.1 (3.4/4.4) E05EA2.2 (3.0/3.3)
E05EA1.3 (3.8/4.2) 194K1.02 (3.0/3.3)
Task Standard:
Reactor Coolant System feed path established via ECCS injection and both pressurizer PORVs and BLOCK VALVES open to establish a bleed path.
Evaluation Method : Simulator X In-Plant -
Performer:
NAME Start Time Performance Time Finish Time "K-"Performance Rating: SAT_ UNSAT __
Evaluator: /
SIGNATURE DATE COMMENTS
JPM # 34 Page 4 of 7 Rev. 7 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified within the step
- 2. Sequenced steps identified by an "s"
- 3. Any UNSAT requires comments
- 4. Acknowledge any associated alarms.
& C to inop all
- 6. Activate MF ED01, to initiate a total loss of offsite power.
S/G level indicators
- 7. Activate OVERRIDES ZAOLI343A 20 (and 56, 98, 111) to hold wide range at -20%. ZAOLR343[1] 20 (and [2], [3], [4]) to hold recorder at 20%.
- 8. Acknowledge alarms and FREEZE simulator until the operator has been briefed
- 9. Console operator will role play as CRO and acknowledge/clear alarms as needed.
- 10. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. 6 mins Local Tools/Equipment/Procedures Needed:
FR-H.1, steps 5-23.
References:
Rev No.
Reference Title 1 FR-H.1 Response to Loss of Secondary Heat Sink 14 READ TO OPERATOR Directions to Trainee: control room steps shall be I will explain the initial conditions, and state the task to be performed. All when directed by you.
actions performed for this JPM. I will provide initiating cues and reports on other measure will be When you complete the task successfully, the objective for this job performance your assigned task. To indicate that you have satisfied. Ensure you indicate to me when you understand completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 has experienced a Reactor Trip due to a total loss of offsite power.
to FR-H.1, "Response
- 2. A "red path" on "Heat Sink Critical Safety Function" has directed the crew to Loss of Secondary Heat Sink".
- 3. All four S/G levels have been decreasing.
- 4. Flow to the S/Gs can NOT be established.
INITIATING CUES:
- 1. You are the OATC and the US directs you to reestablish RCS cooling.
- 2. Your are to perform FR-H.1 beginning at step 5.
- 3. Inform the US when an RCS cooling method has been established.
JPM # 34 Page 5 of 7 Rev. 7 STEP 1: Obtain copy of the appropriate procedure. SAT
\I UNSAT STANDARD: Operator obtains a copy of FR-H.1 Start Time-___
STEP 2: MONITOR heat removal capability: At least two S/G wide range levels _ SAT less than 25%. (or Pzr press less than 2335)
SUNSAT STANDARD: Operator checks LI-3-43, 56, 98 and/or LR-3-43 and determines that 1, 2, and 3 S/Gs are less than 25%.
___UNSAT previously stopped.
STANDARD: Operator determines RCPs STEP 4: GO TO Caution prior to Step 16. __ SAT S UNSAT STANDARD: Operator goes to Caution prior to Step 16.
STEP 5: ACTUATE SI. SAT UNSAT STANDARD: Operator actuates the SI from HS-63-133B on M-4 OR HS-63-133A on M-6 Critical Step STEP 6: VERIFY RCS feed path: CHECK at least one CCP OR SI pump __ SAT running, UNSAT STANDARD: Operator ensures at least one CCP as indicated by red light LIT on HS- Critical Step 62 108A or 104A (and amps indicated on EI-62-108A or 104A) OR at least one SI pump is running as indicated by red light LIT HS-63-10 or 15 (and amps indicated on EI-63-12 & 16). (not critica(items)
JPM Page#6 34 of 7 Rev. 7 SSAT STEP 7: CHECK ECCS valves ALIGNED as appropriate:
REFER TO EA-63-5, ECCS Injection Mode Alignment.
SUNSAT REFER TO ES-1.3, Transfer to RHR Cntmt Sump.
REFER TO ES-1.4, Transfer to Hot Leg Recirc.
Cue: The CRO has verified ECCS valve alignment EA-63-5.
STANDARD: Operator identifies alignment should be verified via SSAT NOTE: The next steps ESTABLISH RCS Bleed path UNSAT STEP 8: CHECK power to pressurizer PORV block valves AVAILABLE and block valves OPEN.
and FCV-68 STANDARD: Operator verifies power is on Block Valves FCV-68-332 lights ON 333 and that both Block Valves OPEN as indicated by red SAT STEP 9: OPEN pressurizer PORVs.
SUNSAT 334 OPEN by Critical Step STANDARD: Operator ensures BOTH PZR PORVs FCV-68-340 & verifies red lights "placingHS-68-340A & 334A in the open position and ON.
SAT STEP 10: CHECK RCS bleed path ADEQUATE:
Pzr PORVs OPEN SUNSAT Pzr PORV block valves OPEN were completed.
STANDARD: Operator verifies the actions of the previous steps T SSA NOTE: The following 2 steps may not be performed. The task has been SU met at this point.
STEP 11: Perform Steps 1 through 12 of E-0, WHILE continuing with this procedure.
-- .. *... mflAa4O-*,'ne Cue: The CR( will perform E-u ML I A OL-..
1 thru 12 of STANDARD: Operator notifies the US/SRO of the need to perform steps E-0 while he/she continues with FR-H.1.
JPM # 34 Page 7 of 7 Rev. 7 STEP 12: MAINTAIN RCS heat removal: _ SAT UNSAT STANDARD: Operator verifies flow thru the CCPIT on F1-63-170 and Pressurizer PORVs OPEN.
STEP 13: Inform the US/SRO when feed and bleed of the RCS has been __ SAT established.
UNSAT STANDARD: Operator informs the US/SRO when feed and bleed of the RCS has Stop Time_
been established.
End of JPM
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL FUNCTION RESTORATION PROCEDURE FR-H.1 LOSS OF SECONDARY HEAT SINK Revision 14 QUALITY RELATED PREPAREDIPROOFREAD BY: D. A. PORTER
/RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J.A. DVORAK EFFECTIVE DATE: 08 Jun 01 REVISION upon DESCRIPTION: Revised guidance on resetting Feedwater Isolation signal based change from PER 01-000597-000. Revised step 3.a RNO to incorporate ERG Rev. 1C.
HANDOUT FOR FR-H.1 Rev. 14 Page 1 of 1 STEP ACTION
- 2. MONITOR RWST level greater than 27%.
0
' h (if RCS temoerature less than 350 F)
RNO WHEN adequate RHR cooling capability established, THEN RETURN TO procedure and step in effect.
- 4. MONITOR CST level greater than 10%.
- 5. MONITOR heat removal capability.
"* Two S/G wide range levels greater than 25% [35% ADV]
"* Pressurizer pressure less than 2335 psig.
- 9. MONITOR shutdown boards continuously energized.
10.d. (if MFW flow being established and SI signal has actuated)
MAINTAIN pressurizer pressure less than 1920 psig.
ADV])
11.a. (if all S/G narrow range levels less than 10% [25%
RNO IF feed flow to at least one S/G verified, than 10% [25%ADV].
THEN MAINTAIN flow to restore narrow range level greater
- 12. MONITOR if SI NOT required:
"* RCS subcooling based on core exit T/Cs greater than 40°F
"* Pressurizer level greater than 10% [20% ADV].
13.a. (if condensate flow being established)
MAINTAIN pressurizer pressure less than 1920 psig.
13.g. WHEN condensate flow established, THEN STOP S/G depressurization.
ADV])
14.a. (if all S/G narrow range levels less than 10% [25%
RNO IF feed flow to at least one S/G verified, than 10% [25%ADV].
THEN MAINTAIN flow to restore narrow range level greater
- 21. MAINTAIN RCS heat removal:
"* ECCS flow
"* Pressurizer PORVs OPEN.
- 25. MONITOR containment spray NOT required:
"* Phase B NOT ACTUATED
"* Containment pressure less than 2.81 psid.
26.b.2) MONITOR RHR pump run time.
RNO 26.b.3 WHEN 100 minutes has elapsed, RNO THEN PERFORM the following:
pumps)
(if CCS NOT aligned to RHR heat exchangers, then stop RHR Page la of 30
HANDOUT FOR FR-H.1 Rev. 14 Page 1 of 1 ACTION STEP
- 2. MONITOR RWST level greater than 27%.
3.b. (if RCS temperature less than 3500F)
RNO WHEN adequate RHR cooling capability established, THEN RETURN TO procedure and step in effect.
- 4. MONITOR CST level greater than 10%.
- 5. MONITOR heat removal capability.
- Two S/G wide range levels greater than 25% E35%
ADV]
- Pressurizer pressure less than 2335 psig.
- 9. MONITOR shutdown boards continuously energized.
has actuated) 10.d. (if MFW flow being established and SI signal 1920 psig.
MAINTAIN pressurizer pressure less than
[25% ADV])
11 .a. (if all S/G narrow range levels less than 10%
RNO IF feed flow to at least one S/G verified, greater than 10% [25%ADV].
THEN MAINTAIN flow to restore narrow range level
- 12. MONITOR if SI NOT required:
40 0F
"* RCS subcooling based on core exit TICs greater than
"* Pressurizer level greater than 10% [20% ADV].
13.a. (if condensate flow being established)
MAINTAIN pressurizer pressure less than 1920 psig.
13.g. WHEN condensate flow established, THEN STOP S/G depressurization.
E25% ADV])
14.a. (if all S/G narrow range levels less than 10%
RNO IF feed flow to at least one S/G verified, greater than 10% [25%ADV].
THEN MAINTAIN flow to restore narrow range level
- 21. MAINTAIN RCS heat removal:
- ECCS flow
- Pressurizer PORVs OPEN.
- 25. MONITOR containment spray NOT required:
- Phase B NOT ACTUATED
- Containment pressure less than 2.81 psid.
26.b.2) MONITOR RHR pump run time.
RNO 26.b.3) WHEN 100 minutes has elapsed, RNO THEN PERFORM the following: stop RHR pumps)
(if CCS NOT aligned to RHR heat exchangers, then Page lb of 30
HANDOUT FOR FR-H.1 Rev. 14 Page 1 of 1 STEP ACTION
- 2. MONITOR RWST level greater than 27%.
3.b. (if RCS temperature less than 350'F)
RNO WHEN adequate RHR cooling capability established, THEN RETURN TO procedure and step in effect.
- 4. MONITOR CST level greater than 10%.
- 5. MONITOR heat removal capability.
"* Two S/G wide range levels greater than 25% [35% ADV]
"* Pressurizer pressure less than 2335 psig.
- 9. MONITOR shutdown boards continuously energized.
10.d. (if MFW flow being established and SI signal has actuated)
MAINTAIN pressurizer pressure less than 1920 psig.
11 .a. (if all S/G narrow range levels less than 10% [25% ADV])
RNO IF feed flow to at least one S/G verified, [25%ADV].
THEN MAINTAIN flow to restore narrow range level greater than 10%
- 12. MONITOR if SI NOT required:
0
"* RCS subcooling based on core exit TICs greater than 40 F
"* Pressurizer level greater than 10% [20% ADV].
13.a. (if condensate flow being established)
MAINTAIN pressurizer pressure less than 1920 psig.
13.g. WHEN condensate flow established, THEN STOP S/G depressurization.
14.a. (if all S/G narrow range levels less than 10% [25% ADV])
RNO IF feed flow to at least one S/G verified, [25%ADV].
THEN MAINTAIN flow to restore narrow range level greater than 10%
- 21. MAINTAIN RCS heat removal:
- ECCS flow
- Pressurizer PORVs OPEN.
- 25. MONITOR containment spray NOT required:
- Phase B NOT ACTUATED
- Containment pressure less than 2.81 psid.
26.b.2) MONITOR RHR pump run time.
RNO 26.b.3) WHEN 100 minutes has elapsed, RNO THEN PERFORM the following:
(if CCS NOT aligned to RHR heat exchangers, then stop RHR pumps)
Page 1c of 30
FR-H.1 SQN LOSS OF SECONDARY HEAT SINK Rev. 14 1.0 PURPOSE This procedure provides actions to respond to a loss of secondary heat sink in all steam generators.
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 ENTRY CONDITIONS E-0 Reactor Trip or Safety Injection:
- All S/G narrow range levels less than or equal to 10% [25% ADV]
AND Total feedwater flow to S/Gs less than equal to 440 gpm.
FR-0 Status Trees:
F-0.3, Heat Sink RED condition:
All S/G narrow range levels less than equal to 10% [25% ADV]
AND Total feedwater flow to S/Gs less than equal to 440 gpm.
3.0 OPERATOR ACTIONS Page 2 of 30
STEP ACTION/EXPECTED RESPONSE . RESPONSE NOT OBTAINED a Faulted SIG.
CAUTION Feeding an Intact or Ruptured SIG is preferred to feeding tubes, rupture The thermal stresses from feeding a Faulted SIG could resulting in a Faulted-AND-Ruptured SIG.
- 1. DETERMINE procedure applicability:
- a. GO TO Step 2.
- a. CHECK the following:
a Total feed flow less than 440 gpm due to operator action as directed by another procedure AND
- Total feed flow capability of greater than 440 gpm AVAILABLE.
- b. RETURN TO procedure and step in effect.
Page 3 of 30
<7 ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED STEP
- 3. CHECK if secondary heat sink required:
a.RTUNT poeue an tpi t.i t.
- a. RETURN TO procedure and step in ellect.
- a. RCS pressure greater than any non-Faulted S/G pressure
- b. ATTEMPT to place RHR System in
- b. RCS temperature service USING EA-74-1, Placing RHR greater than 350°F. Shutdown Cooling in Service, WHILE continuing with this procedure.
WHEN adequate RHR cooling capability established, THEN RETURN TO procedure and step in effect.
- 4. MONITOR CST level greater than 10%. USING EA-3-9, Establishing Turbine Driven AFW Flow, and EA-3-10, Establishing Motor Driven AFW Flow.
rising RCS NOTE Pressurizer pressure greater than or equal to 2335 psig (with of heat sink.
temperature and a low loop delta-T) indicates loss
- 5. MONITOR heat removal capability:
" At least two S/G wide range levels a. STOP RCPs.
greater than 25% [35% ADV]. b. GO TO Caution prior to Step 16.
" Pressurizer pressure less than 2335 psig.
Page 4 of 30
[ STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. ATTEMPT to establish AFW flow to at
- - t-,n:. t..~4.-1InA; ýArdor least one oI I11 LIn IMIL1VVI priority-- Intact, Ruptured, Faulted:
- a. CHECK S/G blowdown isolation a. CLOSE valves.
valves CLOSED.
- b. CHECK control room indications for cause of AFW failure:
"* CST level
"* AFW pump power supply
"* AFW valve alignment.
- 2) ENSURE AFW level control valves OPEN.
(Step continued on next page.)
Page 5 of 30
P XPECTEE RESPONSE NOT OBTAINED Page 6 of 30
FR-H.1 SQN LOSS OF SECONDAFZY HEAT SINK Rev. 14 I STEP I ACTION/EXPECTED RESPONSE F RESPONSE NOT OBTAINED
- 9. MONITOR shutdown boards continuously WHEN shutdown board re-energized, THEN energized.
ENSURE safeguards equipment running as necessary.
NOTE Containment pressure greater than 1.54 psid will prevent opening the FW isolation valves.
Allowing pressurizer pressure to rise above 1970 psig will reinstate automatic SI and may result in isolation of feed flow.
- 10. ESTABLISH MFW flow to at least one S/G:
- a. CHECK containment pressure a. GO TO Step 15.
less than 1.54 psid.
- b. CHECK condensate system b. START condensate system pumps IN SERVICE: as necessary.
"* Hotwell pumps IF condensate system CANNOT be placed
"* Condensate booster pumps in service,
"* Con DI booster pumps. THEN GO TO Step-15.
- c. IF SI signal has NOT actuated, THEN GO TO Substep 10.h.
9-- 7M (Step continued on next page.)
Page 7 of 30
FR-H.1 SQN LOSS OF S ECONDARY HEAT SINK Rev. 14 I STEP I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I
- 10. d. MAINTAIN pressurizer pressure [M-5]
less than 1920 psig:
- 1) CHECK letdown IN SERVICE. 1) USE one pressurizer PORV.
IF pressurizer PORV NOT available, THEN ESTABLISH auxiliary spray USING EA-62-4, Establishing Auxiliary Spray.
GO TO Step 10.e.
- 2) ESTABLISH auxiliary spray 2) USE one pressurizer PORV.
USING EA-62-4, Establishing Auxiliary Spray.
- e. BLOCK SI signals:
"* Low pressurizer pressure SI
"* Low steamline pressure SI.
- f. CHECK the following indications:
"* PRESSURIZER SI TRAINS A & B BLOCKED permissive LIT
[M-4A, B4]
"* STEAMLINE PRESS ISOL/SI BLOCK RATE ISOL ENABLE permissive LIT [M-4A, A4].
(Step continued on next page.)
Page 8 of 30
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP
- 10. g. RESET SI and CHECK the following:
"* AUTO S.I. BLOCKED permissive LIT. [M-4A, C4]
"* S.I. ACTUATED permissive DARK. [M-4A, D4].
- h. CHECK FW isolation valves OPEN. h. PERFORM the following:
- 1) CYCLE reactor trip breakers.
- 2) RESET FW isolation signal. [M-3]
- 3) CLOSE MFW regulating valves.
- 4) CLOSE MFW regulating bypass valves.
- 5) OPEN FW isolation valves.
IF FW isolation valves CANNOT be opened, THEN GO TO Step 15.
ATTEMPT to establish MFW flow to at i. GO TO Step 12.
least one S/G USING EA-2-2, Establishing Secondary Heat Sink Using Main Feedwater or Condensate System.
Page 9 of 30
[-STEP ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 11. DETERMINE if secondary heat sink restored:
- a. CHECK narrow range level a. IF feed flow to at least one S/G verified, in at least one S/G THEN greater than 10% [25% ADV]. PERFORM the following:
- 1) MAINTAIN flow to restore narrow range level greater than 10% E25% ADVI.
- 2) RETURN TO procedure and step in effect.
IF feed flow to at least one S/G NOT verified, THEN GO TO Step 12.
- b. RETURN TO procedure and step in effect.
Page 10 of 30
FR-H.14 SON LOSS OF SECONDARY HEAT SINK Rev. 14I STEP ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED
"* RCS subcooling based on core exit thermocouples greater than 40'F
"* Pressurizer level greater than 10% [20% ADV].
Page 11 of 30
F STEP I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I NOTE "* It is desirable to maintain S/G 1 or 4 capable of supplying steam to the TD AFW pump as long as possible.
reinstate automatic SI
"* Allowing pressurizer pressure to rise above 1970 psig will and may result in isolation of feed flow.
- 13. ATTEMPT to establish feed flow from condensate system:
- a. MAINTAIN pressurizer pressure [M-5]
less than 1920 psig:
- 1) CHECK letdown IN SERVICE. 1) USE one pressurizer PORV.
IF pressurizer PORV NOT available, THEN ESTABLISH auxiliary spray USING EA-62-4, Establishing Auxiliary Spray.
GO TO Substep 13.b.
- 2) ESTABLISH auxiliary spray 2) USE one-pressurizer PORV.
USING EA-62-4, Establishing Auxiliary Spray.
- b. BLOCK SI signals:
"* Low pressurizer pressure SI
"* Low steamline pressure SI.
(Step continued on next page.)
Page 12 of 30
F STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. c. CHECK the following indications:
"* PRESSURIZER SI TRAINS A & B BLOCKED permissive LIT
[M-4A, B4]
"* STEAMLINE PRESS ISOL/SI BLOCK RATE ISOL ENABLE permissive LIT [M-4A, A4].
- d. PERFORM the following:
- d. CHECK FW isolation valves OPEN.
- 1) RESET SI and CHECK the following:
"* AUTO S.I.BLOCKED permissive LIT. [M-4A, C4J
"* S.I. ACTUATED permissive DARK. [M-4A, D4]
- 2) CYCLE reactor trip breakers.
- 3) RESET FW Isolation.
- 4) OPEN FW isolation valves.
IF FW isolation valves CANNOT be opened, THEN GO TO Step 15.
(Step continued on next page.)
Page 13 of 30
RESPONSE NOT OBTAINED STEP ACTION/EXPECTED RESPONSE flow path to S/Gs e. GO TO Step 15.
- 13. e. ALIGN condensate F ,,IOI.f CAMXJ.
A ct0hlishina Secondary Heat Sink Using Main Feedwater or Condensate System.
- f. DUMP steam at maximum rate
- f. DEPRESSURIZE at least one S/G at USING Intact S/G atmospheric relief(s).
maximum rate USING steam dump to IF local control of atmospheric relief(s) is condenser UNTIL condensate flow necessary, established. THEN DISPATCH personnel to dump steam USING EA-1-2, Local Control of S/G PORVs.
IF at least one S/G CANNOT be depressurized, THEN GO TO Step 15.
- g. WHEN condensate flow established, THEN STOP S/G depressurization.
Page 14 of 30
I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 14. DETERMINE if secondary heat sink restored:
. . * ,
- S...__tz* -- --t t,*,
- a. CHECK narrow range level a. IF feed flow to at least one S/i venried, THEN in at least one S/G greater than 10% [25% ADV]. PERFORM the following:
- 1) MAINTAIN flow to restore narrow range level greater than 10% [25% ADV].
- 2) RETURN TO procedure and step in effect.
IF feed flow to at least one S/G NOT verified, THEN GO TO Step 15.
- b. RETURN TO procedure and step in effect.
Page 15 of 30
r STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 15. CHECK if secondary heat sink lost:
- Three S/G wide range levels GO TO Step 3.
less than 25% [35% ADV].
I --- MA OR
- Pressurizer pressure greater than or equal to 2335 psig due to loss of heat sink.
CAUTION Any delay in completing Steps 16 through 19 could result in fuel damage.
- 16. ACTUATE SI.
Page 16 of 30
STEP ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 17. VERIFY RCS feed path: START pumps and ALIGN valves as necessary.
- a. CHECK ECCS pump status:
IF a feed path CANNOT be established,
. At least one CCP RUNNING THEN CONTINUE attempts to establish feed flow.
OR GO TO Step 10.
& At least one SI pump RUNNING.
- b. CHECK ECCS valves ALIGNED as appropriate:
- REFER TO EA-63-5, ECCS Injection Mode Alignment.
"* REFER TO ES-1.3, Transfer to RHR Containment Sump.
"* REFER TO ES-1.4, Transfer to Hot Leg Recirculation.
- 18. ESTABLISH RCS bleed path:
- a. DISPATCH personnel to restore power to
- a. CHECK power to pressurizer PORV block valves USING EA-201-1, 480 V block valves AVAILABLE.
Board Room Breaker Alignments.
- b. OPEN block valves.
- b. CHECK pressurizer PORV block valves OPEN.
- c. OPEN pressurizer PORVs.
Page 17 of 30
F STEP I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 19. CHECK RCS bleed path ADEQUATE: PERFORM the following:
- a. OPEN reactor vessel head vent valves:
"* FSV-68-395
"* FSV-68-396
"* FSV-68-397.
- b. ALIGN available low pressure water sources to the depressurized S/G:
"* OPEN ERCW valves to AFW pump suction.
"* ALIGN HPFP to at least one Intact S/G.
IF low pressure water source CANNOT be aligned, THEN GO TO Step 20.
- c. DEPRESSURIZE at least one Intact S/G to atmospheric pressure with S/G atmospheric relief valve.
Page 18 of 30
SQN LOSS OF SECONDARY HEAT SINK FR-H.1 IO Rev. 14 ISTEP IACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 20. PERFORM Steps 1 through 12 of E-0, Reactor Trip or Safety Injection, WHILE continuing with this procedure.
- 21. MAINTAIN RCS heat removal:
- ECCS flow
- Pressurizer PORVs OPEN.
- 22. RESET Sl and CHECK the following:
- AUTO S.L. BLOCKED permissive LIT [M-4A, C4]
SS.I. ACTUATED permissive DARK [M-4A, D4].
- 23. RESET Phase A and Phase B.
- 24. ESTABLISH control air to containment USING EA-32-1, Establishing Control Air to Containment.
Page 19 of 30
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 25. MONITOR containment spray NOT required:
- a. CHECK containment pressure has a. PERFORM actions in FR-Z.1, High Containment Pressure, remained less than 2.81 psid: WHILE continuing with this procedure.
- Phase B NOT ACTUATED AND
- Containment pressure less than 2.81 psid.
Page 20 of 30
"STEP IACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED
- 26. CHECK RHR status:
- a. CHECK RHR pumps RUNNING a. GO TO Step 27.
ALIGNED
to RHR heat IF CCS CANNOT be aligned to RHR heat exchangers, THEN PERFORM the following:
- 1) RECORD RHR pump start time in Unit Narrative Log.
- 2) MONITOR RHR pump run time.
- 3) WHEN 100 minutes has elapsed, THEN PERFORM the following:
a) CHECK CCS ALIGNED to RHR heat exchangers.
b) IF CCS NOT aligned to RHR heat exchangers, THEN STOP RHR pumps.
Page 21 of 30
STEP ACTION/EXPECTED RESPONSE V RESPONSE NOT OBTAINED
,e+ khiek Z2. CONI* I IINUr"E au t-lll~.m LSoliill,/ll es secondary heat sink in at least one S/G by performing the following EAPs as necessary:
"* EA-3-10, Establishing Motor Driven AFW Flow.
"* EA-3-9, Establishing Turbine Driven AFW Flow.
"* EA-2-2, Establishing Secondary Heat Sink Using Main Feedwater.
- 28. DETERMINE if secondary heat sink restored:
- a. GO TO Step 27.
- a. CHECK narrow range level in at least one S/G greater than 10% [25% ADV].
GO TO Step 27,
- 29. CHECK RCS temperatures:
Core exit T/Cs DROPPING C RCS T-hots DROPPING.
30 VFRIFY reactor head vent valves CLOSE valves.
CLOSED.
Page 22 of 30
LOSS OF SECONDARY HEAT SINK FR-H.1 SQN Rev. 14 ISTEP ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED
-I NOTE Stopping CCPs and SI pumps on alternate trains is preferred, when possible, to maintain RCS injection flow in case one ECCS train is lost.
- 31. DETERMINE if one CCP should be stopped:
- a. CHECK two CCPs RUNNING. a. GO TO Step 32.
- b. DETERMINE required RCS subcooling from table below:
(Step continued on next page.)
Page 23 of 30
EPOS O OTIE STEP AýCTIONIEXPECTED RESPOS
- c. CHECK RCS subcooling based on c. IF T-hot greater than 340'F, 31.
core exit T/Cs greater than required THEN subcooling. GO TO Note prior to Step 34.
IF T-hot less than 3400F AND RHR pumps stopped, THEN START one RHR pump aligned for ECCS injection.
IF at least one RHR pump CANNOT be started, THEN GO TO Note prior to Step 34.
K>
- d. DO NOT STOP CCP.
- d. CHECK pressurizer level GO TO Note prior to Step 34.
greater than 10% [20% ADV].
- e. STOP one CCP.
- f. DO NOT STOP additional ECCS pumps
- f. VERIFY RCS pressure UNTIL the following conditions met:
stable or rising.
"* RCS subcooling RISING AND
"* RCS pressure stable or rising OR dropping due to cooldown.
Page 24 of 30
STEP ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 32. DETERMINE if one SI pump should be stopped:
- a. CHECK any SI pump RUNNING. a. GO TO Step 33.
- b. DETERMINE required RCS subcooling from table below:
- c. CHECK RCS subcooling based on c. IF T-hot greater than 340'F, THEN core exit T/Cs greater than required GO TO Note prior to Step 34.
subcooling.
IF T-hot less than 340°F AND RHR pumps stopped, THEN START one RHR pump aligned for ECCS injection.
IF at least one RHR pump CANNOT be started, THEN GO TO Note prior to Step 34.
rý (Step continued on next page.)
Page 25 of 30
I STEP I ACTION/EXPECTED RESPONSE F RESPONSE NOT OBTAINED
- 32. d. CHECK pressurizer level d. DO NOT STOP SI pump.
greater than 10% [20% ADV]. GO TO Note prior to Step 34.
E--, 7:ýA
- e. STOP one SI pump.
- f. VERIFY RCS pressure f. DO NOT STOP additional ECCS pumps stable or rising. UNTIL the following conditions met:
"* RCS subcooling RISING AND
"* RCS pressure stable or rising OR dropping due to cooldown.
- g. GO TO Substep 32.a Page 26 of 30
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 33. DETERMINE if normal charging should be established:
- a. DO NOT ISOLATE CCPIT.
- a. CHECK ECCS pump status: GO TO Note prior to Step 31.
"* SI pumps STOPPED
"* Only one CCP RUNNING.
- b. DO NOT ISOLATE CCPIT.
- b. CHECK RCS subcooling based on GO TO Note prior to Step 34.
core exit TICs greater than 500F.
- c. DO NOT ISOLATE CCPIT.
- c. CHECK Pressurizer level GO TO Note prior to Step 34.
greater than 10% [20% ADVI.
- d. GO TO Step 35.
Page 27 of 30
FR-H.1 SQN LOSS OF SECONDARY HEAT SINK Rev. 14 I
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE After closing a pressurizer PORV, it may be necessary to wait for RCS pressure to rise to permit stopping additional ECCS pumps in Steps 31 and 32.
- 34. CHECK RCS bleed path status:
- a. CHECK at least one pressurizer a. GO TO E-1, Loss of Reactor or PORV and associated block valve Secondary Coolant.
OPEN.
- b. CLOSE one pressurizer PORV. b. CLOSE associated block valve.
IF block valve CANNOT be closed, THEN GO TO E-1, Loss of Reactor or Secondary Coolant.
e
- c. GO TO Note prior to Step 31.
Page 28 of 30
A 'tErn I STEP I ACTION/EXPECTED RESPONSE I RESPONSE NO I US IAl
- 35. ISOLATE CCPIT:
- a. CLOSE inlet isolation valves FCV-63-39 and FCV-63-40.
- b. CLOSE outlet isolation valves FCV-63-26 and FCV-63-25.
- 36. ESTABLISH normal charging flow:
- a. CLOSE seal water flow control valve FCV-62-89.
- b. OPEN alternate or normal charging isolation valve FCV-62-85 or FCV-62-86.
- c. OPEN charging flow isolation valves FCV-62-90 and FCV-62-91.
- d. ESTABLISH desired charging flow USING seal water and charging flow control valves FCV-62-89 and FCV-62-93.
IF pressurizer PORV CANNOT be closed, THEN CLOSE associated block valve.
Page 29 of 30
I FR-H.1 SQN LOSS 0 FSECONDARY HEAT SINK Rev. 14 F STEP I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED
- 38. DETERMINE if RHR pumps should be stopped:
- a. CHECK RCS pressure: a. GO TO E-1, Loss of Reactor or Secondary Coolant.
. Greater than 180 psig e
. Stable or rising.
- b. CHECK RHR pumps b. GO TO Step 39.
ALIGNED to RWST.
rý
- c. STOP RHR pumps and PLACE in A-AUTO.
- 39. CONTROL charging flow to maintain pressurizer level.
END Page 30 of 30
JPM # 21 Page 1 of 7 Rev. 9 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 21 Respond to a Failure of PRM N-41 Original Signatures on File PREPARED/
REVISED BY: Date/
VALIDATED BY:
- Date/
APPROVED BY: Date/
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM # 21 Page 2 of 7 Rev. 9 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF 1 I V DATE PAGES AFFECTED PREPARED/
REVISED BY:
NUMBER REVISION / .,II I It t-'*I__I
.Qr~
INa OJ* Al*1 7 Transfer from WP. Minor enhancements. IN 8/94 ^'*11 8 Incorporate pen/ink chg which made cue Y 11/3/95 All HJ Birch to "cmplt AOl". Also chgd JPM due to AOP upgrade. Changed initiating cues to monitor board. Malf not already in. Chgd performance time based on validation.
N 7/16/97 4 HJ Birch pen/ink AOP Rev chg N 2/2/98 4 HJ Birch pen/ink AOP Rev chg N 10/16/98 All JP Kearney pen/ink AOP revision change had no impact.
Revised K/A ratings. Reformatted critical steps.
N 8/29/00 4 SR Taylor pen/ink AOP Rev chg only N 2/5/01 2,4 GS Poteet pen/ink pen/ink L. Pauley
-K pen/ink Step 5 chgd defeat light from off to on N 11/27/01 5,7 and added step to notify Rx Eng, added use of ARP N 8/22/02 All J P Keamey 9 Incorporated pen/ink changes i-I V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM # 21 Page 3 of 7 Rev. 9 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task:
Respond to a Failure of PRM N-41 Note: This JPM satisfies Simulator Manipulation "AA".
JA/TA task # : 3210140401 (RO) 0150050101 (RO) 0150040101 (RO)
K/A Ratings:
015A4.03 (3.8/3.9) 015A4.02 (3.9/3.6) 015A2.01 (3.5/3.9) 015A3.03 (3.9/3.9) 01 5A4.01 (3.6/3.6)
Task Standard:
Recognize failure of Power Range Monitor, N-41, defeat its control functions, and prepare for its removal from service.
Evaluation Method : Simulator X In-Plant Performer:
NAME Start Time
\ Performance Rating : SAT __ UNSAT Performance Time Finish Time Evaluator: /
SIGNATURE DATE COMMENTS 1/2>
JPM # 21 Page 4 of 7 Rev. 9 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Sequenced steps identified by an "s".
- 2. Any UNSAT requires comments.
- 3. Acknowledge any associated alarms.
- 4. Initialize simulator in IC #8.
- 5. Place one NR45 selector switch to the N-41 (P-i) position.
- 6. Approximately 1 minute after operator assumes shift, Activate MF # NIO7A @ 0%.
- 7. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. 8 mins Local Tools/Equipment/Procedures Needed:
AOP-I.01, Section 2.0 & 2.3, AR-M6-A
References:
I Reference Title Rev No.
1 AOP-l.01 Nuclear Instrument Malfunction 4
- 2. 1-AR-M6-A Reactor Protection and Safeguards 12 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 1 is operating at 57% reactor power, all controls are in AUTOMATIC.
INITIATING CUES:
- 1. You are the OATC and are to monitor the control board and respond per licensed duties to operating conditions.
- 2. Your US is currently assisting in tagging unit 1 125V spare charger.
- 3. You will be required to respond, as a reader/doer, to any abnormality that occurs.
- 4. When any required actions/procedures have been completed notify the SM.
JPM # 21 Page 5 of 7 Rev. 9 Job Performance Checklist:
STEP/STANDARD SAT1U NSAT STEP/SANDAR STEP 1: Respond to alarm on XA-M6-A window B-1 AND: SAT IF no reactor trip, PLACE rod control in Man. UNSAT Checks for dropped rod (rod bottom lights LIT or RPIs on bottom. Start Time Checks l-XX-55-5 trip status panel for tripped bistables.
STANDARD: Operator responds to alarm, places rod control in Man, checks for dropped rods, checks bistable trip status and GOTO AOP-I.01.
STEP 2: Obtains a copy of AOP-I.01 and determines the appropriate section. __ SAT UNSAT Cue: SM will evaluate Tech Specs.
STANDARD: Operator obtains a copy of AOP-l.01 and determines appropriate section to be 2.3 Place rod control in Man. SAT STEP 3:
UNSAT NOTE: The rods may have been placed in manual in Step 1.
I STANDARD: Operator place HS-85-51 10 to manual.
STEP 4: STABILIZE reactor power at current level. __ SAT UNSAT STANDARD: Operator checks other power range instruments and determines that reactor is stable.
STEP5: PLACE "UPPER SECTION" switch to failed detector, panel M-13 __ SAT (Upper Detector current comparator defeat switch).Q(XX-92-5037)
UNSAT STANDARD: Detector Current comparator "Upper Section" switch in the PRN-41 position. Channel defeat light on. Critical Step PLACE "LOWER SECTION" switch to failed detector, panel M-13 SAT STEP 6:
(Lower detector current comparator defeat switch). (XX-92-5037) UNSAT STANDARD: Detector Current comparator "Lower Section" switch in the PRN-41 Critical Step position. Channel defeat light on.
I
JPM # 21 Page 6 of 7 Rev. 9 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP/STANDARD I
- ISTEP 7: PLACE ROD STOP BYPASS switch to failed detector, panel M-13 SAT (C-2 interlock defeat switch) (XX-92-5037)
UNSAT STANDARD: Rod Stop Bypass switch in "BYPASS PRN-41" position. Critical Step STEP 8: PLACE Power Mismatch Bypass switch to failed detector, Panel M- _ SAT 13 (automatic rod control input defeat switch) (XX-92-5037)
UNSAT STANDARD: Power Mismatch Bypass switch in the "Bypass PRN-41" position.
Critical Step STEP 9: DEFEAT failed Power Range channel Using Comparator Channel __ SAT defeat switch, Panel M-1 3 (Comparator and Rate Drawer)
(XX-92-5041) __ UNSAT STANDARD : Comparator Channel Defeat switch in the N-41 position. Comparator Critical Step defeat light on.
\ /STEP 10: RESTORE T-avg to T-ref. SAT UNSAT STANDARD: Operator compares T-avg to T-ref at TR-68-2B verifies NO difference
(< 1.50 F).
STEP 11: ENSURE Nuclear Power Recorder, NR-45, to operable channel. __ SAT UNSAT STANDARD: Operator checks position of Hand Switches, 1-HS-92-5009 and 1-HS-5010. Ensures neither of these is selected for N-41 (P-1).
STEP 12: ENSURE RCS Temp AT recorder, XS-68-2B, to operable channel. __ SAT UNSAT STANDARD: Operator checks position of XS-68-2B. Ensures it is NOT selected for LOOP ONE.
JPM # 21 Page 7 of 7 Rev. 9 Job Performance Checklist:
STIFPITANDARDl SAT/UNSAT STEP/STANDARD I STEP 13: RETURN rod control to AUTO ifdesired. SAT UNSAT Cue: SM would like the rods placed back in AUTO.
STANDARD: Operator places HS-85-51 10 to AUTO.
STEP 14: CHECK reactor power greater than 75%. SAT UNSAT STANDARD: Operator verifies power less than 75% (current power is - 57%), goes to RNO and to appropriate step.
STEP 15: NOTIFY IMto remove failed power range channel from service using SAT Appendix "A" of AOP-I.01. UNSAT Cue: Role play as MSS or IM, inform operatorthat a crew will be to the MCR within the hour to perform Appendix "A" of AOP-I.01.
STANDARD: Operator communicates with IMs or MSS to request performance of Appendix "A" of AOP-I.01 for removal of N-41 from service.
STEP 16: NOTIFY Reactor Engineering to perform 0-SI-NUC-000-01 1.0, __ SAT Moveable Detector Determination of Quadrant Power Tilt Ratio.
UNSAT Cue: The SM will notify ReactorEngineering.
STANDARD: SAME.
STEP 17: Notify SM that N-41 failed, its control functions have been defeated, __ SAT Rx Eng and IMs have been notified to remove it from service.
UNSAT STANDARD: SAME. Stop Time End of JPM
8 (B-1)
Source Setpoint NC-41 U/NC-41 K SER 445 NIS POWER RANGE SER 450 HIGH NEUTRON SER 453 FLUX RATE SER 458 Positive/Negative +5%, -5% with a 2.2 High Flux Rate Bistable, second time constant NC41U, NC41K NC42U, NC42K NC43U, NC43K NC44U ,NC44K 1/4 for alarm 2/4 for trip Probable 1. One or more rods dropped (negative rate).
Causes 2. Rod ejection (positive rate).
- 3. Loss of detector voltage.
- 4. Channel in test.
Corrective [1] IF reactor trips, THEN Actions GO TO E-0, Reactor Trip or Safety Injection.
[2] IF no reactor trip, THEN
[a] PLACE 1-HS-85-5110, Rod Control Mode Selector Switch in the MANUAL position.
[b] CHECK for any rod bottom lights and/or RPI indicating dropped rod(s).
[c] CHECK 1-XX-55-5 trip status panel for any bistables that may be tripped.
[d] EVALUATE reactor trip criteria with SRO.
[3] IF power range channel failed, THEN GO TO AOP-l.01, Nuclear Instrument Malfunction.
[4] IF more than one dropped rod occursTHEN
[a] TRIP the reactor, AND
[b] GO TO Reactor Trip or Safety Injection.
[5] IF one rod has dropped, THEN GO TO AOP-C.01, Rod Control System Malfunctions.
[6] IF alarm is due to channel being tested, THEN ENSURE the rate mode switch, on the control power drawer, is placed in the RESET position and that the RATE TRIP bistable light goes out prior to test completion.
[7] EVALUATE Technical Specifications.
References 45B655-06A-0, 47W611-99,
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOI PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES AOP-I.01 NUCLEAR INSTRUMENT MALFUNCTION Revision 5 QUALITY RELATED PREPARED/PROOFREAD BY: CHERYL D. MORRIS RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J.A. DVORAK EFFECTIVE DATE: 3 Sept 02 REVISION DESCRIPTION: Revised to incorporate TSC 99-20, Engineering Expertise on Shift to clarify responsibilities of the STA. Clarified step in RNO to include one hour limit to perform shutdown margin verification. Also changed "Work Request" to "Work Order" in appendices removing Power Range Channels from service, and removed steps to attach completed appendix to WR. This is an intent revision.
AOP-I.01 SQN NUCLEAR INSTRUMENT MALFUNCTION Rev. 5 1.0 PURPOSE This procedure provides the actions necessary to mitigate source range, intermediate range, and power range instrument malfunctions.
Page 2 of 48
STEP I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.0 OPERATOR ACTIONS
- 1. EVALUATE the following Tech Specs for applicability:
"* 3.3.1.1 (3.3.1), Reactor Trip System Instrumentation
"* 3.3.2.1 (3.3.2), Engineered Safety Feature Actuation System Instrumentation
"* 3.3.3.5, Remote Shutdown Instrumentation
"* 3.3.3.7, Accident Monitoring Instrumentation
"* 3.9.2, Refueling Operations Instrumentation
"* 4.2.4.2, QPTR with one PR Channel Inoperable
- 2. DIAGNOSE the failure:
GO TO IF... SECTION PAGE Source Range Failure 2.1 4 Intermediate Range Failure 2.2 10 Power Range Failure 2.3 15 Page 3 of 48
STEP I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINE 2.3 Power Range Failure
- 1. PLACE rod control in MAN.
- 2. STABILIZE reactor power at current level.
- 3. PLACE following switches located on Detector Current Comparator drawer
[M-13, N50] in position corresponding to failed Power Range Channel:
"* Upper Section
"* Lower Section
"* Appropriate Rod Stop Bypass switch
"* Appropriate Power Mismatch Bypass switch
- 4. DEFEAT failed Power Range channel USING Comparator Channel Defeat switch:
- Comparator and Rate Drawer
[M-13, N37]
- 5. RESTORE T-avg to T-ref.
Page 15 of 48
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINE 2.3 Power Range Failure (cont'd)
- 6. ENSURE OPERABLE Power Range channel selected:
" Nuclear Power Recorder
[M-4, NR-45]
" RCS Temp AT recorder - (green pen)
[M-5, XS-68-2B]
- 7. RETURN rod control to AUTO if desired.
- 8. CHECK reactor power greater than 75%. GO TO Step 10.
- 9. NOTIFY Reactor Engineering to PERFORM O-SI-NUC-000-011.0, Moveable Detector Determination of Quadrant Power Tilt Ratio.
- 10. NOTIFY IMto remove failed power range channel from service USING appropriate Appendix:
POWER RANGE PROT APPENDIX CHANNEL CH N-41 I A N-42 II B N-43 III C N-44 IV D Page 16 of 48
STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.3 Power Range Failure (cont'd)
- 11. GO TO appropriate plant procedure.
END OF SECTION Page 17 of 48
AOP-I.01 SQN NUCLEAR INSTRUMENT MALFUNCTION Rev. 5 3.0 SYMPTOMS AND ENTRY CONDITIONS 3.1 Symptoms A. Any of the following annunciators may indicate a source range, intermediate range, or power range instrument malfunction:
PANEL XA-55-4B, NIS/ROD CONTROL A-1 SOURCE/INTERMED RANGE CH I TROUBLE A-2 SOURCE/INTERMED RANGE CH IITROUBLE B-1 SOURCE RANGE HIGH FLUX LEVEL AT SHUTDOWN B-2 IRS INTERMED RANGE HI FLUX LEVEL AT ROD WITHDRAWAL STOP B-3 NIS POWER RANGE UPPER DETECTOR HI FLUX DEVN OR AUTO DEFEAT C-3 NIS POWER RANGE LOWER DETECTOR HI FLUX DEVN OR AUTO DEFEAT D-3 IPRS NIS POWER RANGE OVERPOWER ROD WITHDRAWAL STOP D-4 COMPUTER ALARM ROD DEV AND SEQ NIS PWR RANGE TILTS E-3 NC-46B NIS POWER RANGE CHANNEL DEVIATION PANEL XA-55-4D, REACTOR FIRST OUT B-1 SOURCE RANGE FLUX LEVEL HIGH REACTOR TRIP B-2 INTERMED RANGE FLUX LEVEL HIGH REACTOR TRIP Page 18 of 48
NUCLEAR INSTRUMENT MALFUNCTION AOP"1Rev.
SON 3.1 Symptoms (cont'd)
PANEL XA-55-6A, REACTOR PROTECTION AND SAFEGUARDS B-1 NC-41U/NC-41K NIS POWER RANGE HIGH NEUTRON FLUX RATE C-1 NC-41P NIS PWR RANGE LOW SETPOINT HIGH FLUX LEVEL C-2 TS-68-2E OVERTEMP AT AUTO TURB RNBK BLK C-3 ROD WTD D-1 NC-41R NIS PWR RANGE HIGH SETPOINT HIGH FLUX LEVEL D-2 TS-68-2F OVERPOWER AT AUTO TURB RNBK BLK C-4 ROD WTD B. Deviations or unexpected indications on any of the following may indicate a nuclear instrument malfunction:
"* Indicators [M-5]:
- Source Range (level and rate)
- Intermediate Range (level and rate)
- Power Range
- Delta Flux (Al)
"* Audio Count Rate channel
" Trip status lights [XX-55-5]:
a S.R. HI FLUX
- I.R. HI FLUX
- 1.R. P6
- P.R. P8 a P.R. P10
- P.R. P9 3.2 Entry Conditions None Page 19 of 48
4.0 REFERENCES
4.1 Performance A. SI-NUC-000-038.0, Shutdown Margin B. 0-SI-NXX-000-011.0, Moveable Detector Determination C. EPIP-1, Emergency Plan Classification Matrix 4.2 Technical Specifications A. 3.3.1.1 (3.3.1), Reactor Trip System Instrumentation B. 3.3.2.1 (3.3.2), Engineered Safety Feature Actuation System Instrumentation C. 3.3.3.5, Remote Shutdown Instrumentation D. 3.3.3.7, Accident Monitoring Instrumentation E. 3.9.2, Refueling Operations Instrumentation F. 4.2.4.2, QPTR with one PR Channel inoperable 4.3 Final Safety Analysis Report A. Chapter 7.0, Instrumentation and Controls 4.4 Plant Drawings A. CCD 1(2)-5655D26, Sheets 2- 5, 8- 10 B. CCD 1(2)-47W611-99, Sheets 1 - 2, 6 C. W 1(2)-108D273, Sheets 7- 10, 23 - 24 4.5 Procedures Service A. 1(2)-S1-IXX-099-483.0, Removal of Reactor Protection System Channels from Page 20 of 48
Page 1 of 7 APPENDIX A REMOVING POWER RANGE CHANNEL N-41 FROM SERVICE NOTES:
- Tech Spec LCO 3.3.1.1 (3.3.1) is applicable in Modes 1 and 2 when this channel is removed from service.
- This is a time critical task and shall be performed without interruption.
A. Setup
- 1. RECORD the time and date the channel failed or was declared inoperable.
Date Time
- 2. OBTAIN the following approval to perform this appendix.
Unit US (SRO)
- 3. PREPARE 34 orange stickers with AOP number and date.
- 4. PLACE orange stickers on the following equipment:
PLACED ANNUNCIATORS (/
NC-41 L NUC OVERPOWER ROD STOP BYPASS [XA-55-4A, A-31 NIS POWER RANGE UPPER DETECTOR H1 FLUX DEVN OR AUTO DEFEAT IXA-55-4B3, 8-3]
NIlS POWER RANGE LOWER DETECTOR HI FLUX DEVN OR AUTO DEFEAT
'XA-55-4B3, C-3]
TS-68-2D REAC COOL LOOPS OVERTEMP AT TRIP ALERT
'XA-55-6A, A-21 TS-68-2G REAC COOL LOOPS OVERPOWER AT TRIP ALERT
[XA-55-6A, B-21 NC-41U/NC-41K NIS POWER RANGE HIGH NEUTRON FLUX RATE
[XA-55-6A, B-11 NC-41P NIS PWR RANGE LOW SETPOINT HIGH FLUX LEVEL i[XA-55-6A, C-1]
TS.-68-2E OVERTEMP AT AUTO TURB RNB3K BLK C-3 ROD W-i'D
[XA-55-6A, C-21 TS-68-2F7 OVERPOWER AT AUTO TURB RNBK BLK C-4 ROD WTD NC-41R NIS PWR RANGE HIGH SETPOINT HIGH FLUX LEVEL IXA-55-6A. D-11 (Step continued on next page)
Page 21 of 48
Page 2 of 7 APPENDIX A REMOVING POWER RANGE CHANNEL N-41 FROM SERVICE A. Setup (cont'd)
- 4. (Continued)
PLACED INDICATORS (*
XI-92-5005A, A FLUX CH-1 N-41 [M-4]
XI-92-5005C, RX POWER CH-1 N-41 [M-4]
STI-68-2B3, OTAT LOOP 1 (M-5]
TI-68-2A, OPAT LOOP 1 [M-5]
Xl-92-5005B, POWER RANGE CH I REACTOR POWER [M-13, N41A]
PLACED
- /
STATUS LIGHTS [XX-55-5]
NC41N P.R. PS NC41M P.R. P10 NC41P P.R. HI F LO SET NC41R P.R. HI PWR HI SET NC41U/K P.R. HI PWR RATE NC41S P.R. P9 TS-68-2D RC LP1 OTAT REAC TRIP TS-68-2G RC LP1 OPAT REAC TRIP TS-68-2E RG LP1 OTAT TURB RNBK TS-68-2F RC LP1 OPAT TURB RNBK PROT. SET 1 TROUBLE I (Step continued on next page)
Page 22 of 48
Page 3 of 7 APPENDIX A REMOVING POWER RANGE CHANNEL N-41 FROM SERVICE A. Setup (cont'd)
- 4. (Continued)
PLACED HAND SWITCHES 4)
HS-92-5009, NR-45 RED PEN [M4]
HS-92-5010, NR-45 BLUE PEN [M-4]
XS-68-2B, LOOP TAVG AT REC/SEL [M-5]
COMPARATOR CHANNEL DEFEAT [M-13, N37/N46]
POWER MISMATCH BYPASS [M-13, N50]
ROD STOP BYPASS [M-13, N50]
UPPER SECTION [M-13, N50]
LOWER SECTION [M-13, N50]
-V
- 5. RECORD status of the following:
CHECK (4)
TRIP STATUS LIGHTS [XX-55-5]
DARK LIT NC42R P.R. HI PWR HI SET NC42U/K P.R. HI PWR RATE NC43R P.R. HI PWR HI SET NC43U/K P.R. HI PWR RATE NC44R P.R. HI PWR HI SET NC44U/K P.R. HI PWR RATE TS-68-25D RC LP20OTAT REAC TRIP TS-68-25G RC LP2 OPAl" REAC TRIP TS-68-25E RC LP20OTAT TURB RNBK TS-68-25F RC LP20OPAT TURB RNBK (Step continued on next page)
Page 23 of 48
NUCLEAR INSTRUMENT MALFUNCTION AOP-I.01 SQN Rev. 5 Page 4 of 7 APPENDIX A REMOVING POWER RANGE CHANNEL N-41 FROM SERVICE A. Setup (cont'd)
- 5. RECORD status of the following: (cont'd)
TRIP STATUS LIGHTS [XX-55-5] CHECK (4)
DARK LIT TS-68-44D RC LP3 OTAT REAC TRIP TS-68-44G RC LP3 OPAT REAC TRIP TS-68-44E RC LP3 OTAT TURB RNBK TS-68-44F RC LP3 OPAT TURB RNBK TS-68-67D RC LP4 OTAT REAC TRIP TS-68-67G RC LP4 OPAT REAC TRIP TS-68-67E RC LP4 OTAT TURB RNBK TS-68-67F RC LP4 OPAT TURB RNBK
- 6. VERIFY Steps 1 through 5 COMPLETE.
CAUTIONS:
- If any of the status lights in Step 5 are LIT, completion of this Appendix will initiate a reactor trip signal.
- Completion of this Appendix will trip the bistables that supply Ch I inputs to the following:
"*Overpower rod stop
"*OTAT turbine runback
"*OPAT turbine runback
"*P-7
"*P-8
"*P-9
"*P-10
- 7. NOTIFY Unit Operator to VERIFY current plant status allows removing this power range channel from service.
UO Initials Page 24 of 48
V I
SQN I
NUCLEAR INSTRUMENT MALFUNCTION AOP-I.01 Rev. 5 Page 5 of 7 APPENDIX A REMOVING POWER RANGE CHANNEL N-41 FROM SERVICE B. Removal of Channel N-41 from Service
- 1. NOTIFY Unit Operator that Channel I of OTAT AND OPAT will be placed in TRIPPED condition. []
- 2. PLACE the following manual bistable trip switches (at R-2) in TRIP:
a TS/411C (OTAT reactor trip) / cv
- TS/411D (OTAT turbine runback/block rod withdrawal)
CV
- TS/411G (OPAT reactor trip) cv
- TS/4111H (OPAT turbine runback/block rod withdrawal) cv
- 3. VERIFY the following TRIP LEDs on Eagle 21 Test Panel LIT:
"* TB/411C
"* TB/411D
"* TB/411G
"* TB/411H El
- 4. NOTIFY Unit Operator to VERIFY the following trip status lights LIT [XX-55-5]: []
"* TS-68-2D RC LPI OTAT REAC TRIP
"* TS-68-2G RC LP1 OPAT REAC TRIP
"* TS-68-2E RC LP10TATTURB RNBK
"* TS-68-2F RC LP1 OPAT TURB RNBK Page 25 of 48
Page 6 of 7 APPENDIX A REMOVING POWER RANGE CHANNEL N-41 FROM SERVICE B. Removal of Channel N-41 from Service (cont'd)
- 5. NOTIFY Unit Operator that power range channel N-41 will be placed in TRIPPED condition. E]
- 6. REMOVE control power fuses from front of POWER RANGE A CH I drawer [M-13, XX-92-5027]. I cv
- 7. NOTIFY Unit Operator to VERIFY the following trip status lights LIT [XX-55-5]: El
"* NC41N P.R. P8
"* NC41M P.R. P10
"* NC41P P.R. HI F LO SET
"* NC41R P.R. HI PWR HI SET
"* NC41U/K P.R. HI PWR RATE
"* NC41S P.R. P9
- 8. VERIFY power range channel N-41 removed from service.
Page 26 of 48
SQN NUCLEAR INSTRUMENT MALFUNCTION AOP-I.O1 Rev. 51 Page 7 of 7 APPENDIX A REMOVING POWER RANGE CHANNEL N-41 FROM SERVICE C. Completion
- 1. OBTAIN current time from Unit Operator.
- 2. RECORD current time and date.
Date Time
- 3. NOTIFY Operations that Power Range Channel N-41 has been removed from service.
Unit US (SRO)
- 4. INITIATE a Work Order (WO) for Power Range Channel N-41.
WO Number
- 5. PREPARE a copy of this completed appendix and forward to the MIG Manager. El Page 27 of 48
JPM #65 Page 1 of 13 Rev. 6 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 65 Re-establishment of CNTMT Pressure Control Following High Pressure Conditions Original Signatures on File PREPARED/
REVISED BY: Date/
- Date/
VALIDATED BY:
Date/
APPROVED BY:
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM #65 Page 2 of 13 Rev. 6 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION AFFECTED REVISED BY:
5 Revised to incorporate changes in Y 9/16/98 All JP earney 0-SO-30-8. Reformatted critical steps.
SO-30-8 revision had no impact 7/15/99 All S.R. Taylor pen/ink 8/15/00 4,6,7 SR Taylor pen/ink Revised to incorporate changes in 0-SO-30-8. Updated Rev level.
0-SO-30-8 Rev chg. and corrected minor 01/04/01 All W. R. Ramsey pen/ink format errors 09/05/01 All W. R. Ramsey pen/ink 0-SO-30-8 Rev chg.
8/20/02 All J P Kearney 6 Incorporated penAnk changes; revised to the latest revision of 0-SO-30-8; no impact on JPM flow 9/17/01 ALL SR Taylor pen/ink Deleted Steps 32, 33, and 34 for returning EAM bistables to normal. These steps were deleted from the SO in REV 12.
Also changed instructions and step 40 (previously 43) appropriately.
5-.-.--, 1 V - Specify if the JPM change will require another Validation (Y or N).
See cover sheet for criteria.
\,1
JPM #65 Page 3 of 13 Rev. 6 SEQUOYAH NUCLEAR PLANT RO/SRO S'JOB PERFORMANCE MEASURE Task:
Re-establishment of CNTMT Pressure Control Following High Pressure Condition JA/TA task #: 00601801 (RO)
K/A Ratings:
103A1.01 (3.7/4.1) 103A4.01 (3.2/3.3) 2.1.31 (4.2/3.9) 103A4.09 (3.1/3.7) 2.1.20 (4.3/4.2)
Task Standard:
Vent the containment pressure down to normal range (within -0.1 to +0.3 psig) and then place the containment automatic Pressure Control System in service.
Evaluation Method : Simulator X In-Plant Performer:
NAME Start time Performance Rating: SAT UNSAT Performance Time Finish time Evaluator: /
SIGNATURE DATE COMMENTS
JPM #65 Page 4 of 13 Rev. 6 SPECIAL INSTRUCTIONS TO EVALUATOR:
/ 1. Sequenced steps identified by an "s"
- 2. Any UNSAT requires comments
- 3. Acknowledge any associated alarms.
- 4. Initialize Simulator in IC #91 or IC: #10 with steps 5,6 below.
- 5. IMF CH01A, CHOI B, CH01 C, CH01 D at 15, to fail the containment pressure indicators at - 1.4 psid.
IOR ZAOPDIR30133.5 to put PDIR-30-133 upscale. IOR ZAOPDI30133 4.5 to put PDI-30-133 near top scale.
- 6. CLOSE FCV-30-46, 47, 48 and FREEZE simulator until turnover completed.
- 7. Note: A console operator will be needed for JPM step 21.
- 8. View Cntmt Ventilation diagram to see when FCV-30-54 is open. When the operator begins venting containment delete malfunctions CHOIA, B, C, & D to return cntmt press to normal. AND Delete overrides on PDIR-30-133 & PDI-30-133.
- 9. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR 25 min Local Tools/Equipment/Procedures Needed:
0-SO-30-8 Sections 3.0, 4.0, 5.1, 5.2, and 7.2
References:
Reference Title Rev No.
A. tainment Pressure Control Co-n-30-8 13 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 1 is in Mode 1 recovering from an Air Line break in containment. The air leak was discovered on a section of the header that allowed isolation without affecting any equipment.
During isolation efforts, cntmt pressure increased to approx. 1.5 psid.
INITIATING CUES:
- 1. The US directs you, the Unit 1 CRO, to vent containment using the normal flow path to within normal operating limits.
- 2. After venting, return Containment Vacuum Control to NORMAL.
- 3. Inform the US when Containment has been vented and the Vacuum Control system is aligned NORMAL.
JPM #65 Page 5 of 13 Rev. 6 Job Performance Checklist:
ST*PISTANflARD SATMUNSAT STEP/STANDARD I OBTAIN the appropriate procedure SAT STEP 1.
UNSAT STANDARD: Operator obtains a copy of 0-SO-30-8, starting with Section 5.2. Start Time STEP 2.: ENSURE power checklist complete for the appropriate unit. __ SAT UNSAT Cue: Power checklist 1-30-8.02 is complete with NO deviations.
STANDARD: Operator checks configuration log to ensure power checklist 1-30-8.02 is complete.
STEP 3.: ENSURE that the check valve portion of the containment SAT vacuum relief assembly is capable of closing by observing UNSAT monitor lights on panel XX-55-9C (panel M-9).
STANDARD: Operator checks XX-55-9C to ensure valves are closed, green lights ON.
I STEP 4.: NOTIFY the US/SRO that the EAM will be placed in the SAT Adverse Cntmt condition for venting containment and UNSAT EVALUATE LCO 3.6.6.
Cue: Play role of SRO, State you will evaluate the LCO.
STANDARD: Operator informs the US/SRO that the EAM will be placed in the Adverse Cntmt condition for venting containment and addresses LCO 3.6.6.
STEP 5.: IF the EAM is not in the Adverse Cntmt condition, THEN: __ SAT PLACE the EAM in the Adverse Cntmt condition by depressing the ACTUATE button in each rack as follows. __ UNSAT STANDARD: Operator recognizes that the EAMs are in the Adverse Cntmt condition (verifies the blue lights are ON above the NR S/G level indicators, and verifies XA-55-3C window 30 illuminated) and N/As this step.
JPM #65 Page 6 of 13 Rev. 6 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 6.: VERIFY Radiochemical Laboratory has a current weekly SAT performance of 0-SI-CEM-030-410.1.
UNSAT Cue: SI-410.1 has been completed and signedby the SRO and Rad Chem Supervisor.
STANDARD: Operator verifies SI-410.1 and approved by SRO and Radiochemical Laboratory Supervisor approval.
STEP 7.: IF the noble gas count rate for the lower containment radiation SAT monitor has increased by more than 50% since the last sample time, THEN TRANSMIT the release permit to the Chem Lab to UNSAT obtain another (noble gas and tritium) set of samples.
Cue: SI-410.1 data shows RM-90-106 Gas = 4.0 E3 STANDARD: Operator looks at RM-90-106 and determines that conditions have not changed by 50% and N/As this step.
STEP 8.: ENSURE that the Shield Building Annulus Vacuum Control __ SAT System is in service and maintaining a negative 5.0 inches of H2 0 as indicated on M-9 PDI-30-126 or PDI-30-127 OR EGTS __ UNSAT in service OR EGTS testing in progress.
STANDARD: Operator obtains reading from PDI-30-126 or 127 on panel M-9, OR if EGTS is in service verifies filter bank AP is between 1 and 7 inches water.
STEP 9.: VERIFY no abnormal or unexplainable radiation levels exist __ SAT inside containment.
UNSAT STANDARD: Operator checks RM-90-106 and 112 for abnormal radiation levels in containment.
STEP 10O.: VERIFY that no containment vent isolation signal exists. __ SAT UNSAT STANDARD : Operator checks XA-55-6C windows C5 & C6 to verify that a cntmt vent isolation signal is not present.
JPM #65 Page 7 of 13 Rev. 6 Job Performance Checklist:
SAT/UNSAT Q*TIrDITA lflARfrl QTEP/SAKIDAR SAT STEP 11.: ENSURE at least ONE of the following radiation monitors in service for the appropriate unit: UNSAT
"* U-1 Containment 1-RM-90-130
"* Purge Exhaust Monitors 1-RM-90-131
"* U-2 Containment 2-RM-90-130
"* Purge Exhaust Monitors 2-RM-90-131 STANDARD: Operator verifies the RM-90-1 30 or 131 is in service.
i VERIFY that all personnel have been evacuated from the SAT STEP 12.:
annulus and that all doors are closed. UNSAT Cue: Role play as NSS or Rad Con and verify all personnelare out of the annulus and the doors are closed.
STANDARD: Operator calls Nuclear Security or Rad Con and verifies that all personnel have been evacuated from the annulus and that all doors are closed.
/ STEP 13.: ENSURE at least one of the following radiation monitors in service for the appropdate unit:: UNSAT AB Vent: 0-RM-90-1 01 B Upper Compartment: 1-RM-90-112 A, B 2-RM-90-112 A, B Lower compartment: 1-RM-90-106 A, B 2-RM-90-106 A, B STANDARD: Operator verifies the absence of applicable instrument malfunction alarms on 0-M-12 and block switch for RM-90-1 01 is in the off position.
LOG time in 1-SI-OPS-030-286.0 SAT STEP 14.:
UNSAT NOTE: SI-286 is NOT available on the simulator, it will be sufficient for the operator to address logging of the time in the SI.
STANDARD: Operator logs time in SI-286.
JPM Page#658 of 13 Rev. 6 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD using STEP 15.: IF aligning the lower compartment purge isolation valves the _NORMAL flow path THEN PERFORM steps [a] thru [f].
NOTE: This step will be satisfied in steps 16 thru 19.
STANDARD: None SAT STEP 16.: ENSURE FCV-30-37 is CLOSED.
UNSAT STANDARD: Operator verifies green light ON for FCV-30-37 SAT STEP 17.: ENSURE FCV-30-40 is CLOSED.
UNSAT STANDARD: Operator verifies green light ON for FCV-30-40 SAT STEP 18.: OPEN FCV-30-14 & 56 with HS-30-14 and VERIFY FCV-30-14 UNSAT
& 56 OPEN 1 and verifies red STANDARD: Operator places HS-30-14 in the OPEN positionplaces HS-30-14 lights ON FCV-30-14 & 56 indicator lights and in the A-AUTO position.
Critical Step SAT STEP 19.: OPEN FCV-30-15 & 57 with HS-30-15 and VERIFY FCV-30-15 UNSAT
& 57 OPEN.
and verifies red STANDARD: Operator places HS-30-15 in the OPEN position lights ON indicating lights for FCV-30-15 & 57 and places position. Critical Step HS-30-15 in the A-AUTO using SAT STEP 20.: IF aligning the lower compartment purge isolation valves UNSAT the Alternate flow path THEN PERFORM steps [a] thru [h].
flow path is STANDARD: Operator should NA this step since the NORMAL being used.
JPM #65 Page 9 of 13 Rev. 6 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD STEP/STANDARD I STEP 21.: OPEN Annulus exhaust isolation valve FCV-30-54 with SAT HS-30-54.
UNSAT NOTE: View Cntmt Ventilation diagram to see when FCV-30-54 is open.
When operator opens FCV-30-54 delete malfunctions Critical Step CH01A, B, C, & D AND delete override ZAOPDIR30133.
and ZAOPDi30133 (These can be deleted by clearing MALF
& OVRD tables)
STANDARD: Operator opens FCV-30-54 with HS-30-54. Verifies valve open by observing red light ON.
STEP 22.: IF the Annulus Vacuum Control System is in service and the __ SAT standby Annulus Vacuum Control Fan is available, THEN START the standby Annulus Vacuum Control Fan. _ UNSAT STANDARD: Operator starts the standby Annulus Vacuum Control Fan STEP 23.: IF a high radiation alarm occurs on any of the following __ SAT Radiation monitors, THEN UNSAT CUE: Radiation levels remain normal during venting operation STANDARD: Operator addresses step and potential for action required if radiation levels increase.
WHEN containment vent is completed, THEN perform [Section 7.2]. _ SAT STEP 24.:
UNSAT NOTE: JPM steps 25 through 31 will satisfy section 7.2 of procedure. Critical Step STANDARD: Operator monitors containment pressure by observing Pdl-30-133. When pressure differential within -0.1 and +0.3 psig, then go to Section 7.2.
JPM Page#65 10 of 13 Rev. 6 Job Performance Checklist:
STEPISTANDARD SAT/UNSAT SAT f STEP 25.: IF both Annulus Vacuum Control Fans are running, THEN STOP one of the Annulus Vacuum Control Fans. SUNSAT STANDARD: Operator stops one of the Annulus Vacuum Control Fans SAT STEP 26.: PLACE HS-30-14 in the CLOSED position.
UNSAT CUE: When requestedperform IVof 30-14 & 56 closed position.
Critical Step STANDARD: Operator places HS-30-14 in the closed position and Verifies FCV-30-14, -56 are closed, green light ON their respective indicating lights. Should request independent verification of action.
SAT STEP 27.: PLACE HS-30-15 in the CLOSED position SUNSAT CUE: When requestedperform IV of 30-15 & 57 closed position.
Critical Step STANDARD: Operator places HS-30-15 in the closed position and Verifies FCV-30-15, -57 are closed, green light ON their respective indicating lights. Should request independent verification of action.
SAT STEP 28.: IF Lower Compartment Purge Isolation Valves are aligned through the ALTERNATE flow path, THEN... UNSAT STANDARD: Operator should NA this step since the NORMAL flow path was used to vent containment.
SAT STEP 29.: CLOSE the Annulus Exhaust isolation valve FCV-30-54 with HS-30-54 UNSAT STANDARD: Operator places HS-30-54 in the closed position and verifies Critical Step green light ON.
JPM #65 Page 11 of 13 Rev. 6 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 30.: RESTORE the Annulus Vacuum Pressure Control SAT per 0-SO-65-1 Section 8.1.
UNSAT CUE.: Another operatorwill restore Annulus Vacuum Controlper 0-SO-65-1.
STANDARD: Operator addresses restoration of Annulus Vacuum Pressure Control per 0-SO-65-1.
STEP 31.: LOG time in 1-SI-OPS-030-286.0. __ SAT UNSAT NOTE: SI-286 is NOT available on the simulator, it will be sufficient for the operator to address logging of the time in the SI.
STANDARD: Operator logs the time that the containment isolation valves were closed in SI-286.
NOTE: The following steps are from 0-SO-30-8, section 5.1. __ SAT Cue: May requirereminderof initialconditions and requested __ UNSAT actions to coach operatorto perform section 5.1.
STEP 32.: ENSURE power checklist 1-30-8.01 complete for U1.
Cue: Power checklist 1-30-8.01 is complete with NO deviations.
STANDARD: Operator verifies power checklist is complete.
K->
JPM #65 Page 12 of 13 Rev. 6 Job Performance Checklist:
- TrDIRTANflARfl SAT/UNSAT STEP/STANDARD I VERIFY the following: SAT STEP 33.:
[1] Cntmt Vacuum Relief Check valve 30-571 CLOSED by UNSAT position indicator lights ZS-30-46B, C, D GREEN and ZS-30 46A OFF.
[2] Cntmt Vacuum Relief Check valve 30-572 CLOSED by position indicator lights ZS-30-47B, C, D GREEN and ZS-30 47A OFF.
[3] Cntmt Vacuum Relief Check valve 30-573 CLOSED by position indicator lights ZS-30-48B, C, D GREEN and ZS-30 48A OFF.
STANDARD: Operator verifies the above indications STEP 34.: OPEN FCV-30-46 by placing HS-30-46A and B (panel M-9) in __ SAT OPEN position.
__UNSAT STANDARD: Operator places HS-30-46A AND HS-30-46B in the OPEN position, verifies red light on HS-30-46A ON. Critical Step STEP 35.: PLACE HS-30-46A and B in the P-AUTO position. __ SAT SUNSAT NOTE: Perform IVs as requested for remainder of steps.
Critical Step STANDARD: Operator places both HSs in the P-AUTO position.
STEP 36.: OPEN FCV-30-47 by placing HS-30-47A and B (panel M-9) in __ SAT OPEN position.
UNSAT STANDARD: Operator places HS-30-47A AND HS-30-47B in the OPEN position, verifies red light on HS-30-47A ON. Critical Step STEP 37.: PLACE HS-30-47A and B in the P-AUTO position. __ SAT UNSAT STANDARD: Operator places both HSs in the P-AUTO position.
Critical Step
JPM #65 Page 13 of 13 Rev. 6 Job Performance Checklist:
SATIUNSAT QT*P IS TAIN fl A fl QTEP/STANDARD I OPEN FCV-30-48 by placing HS-30-48A and B (panel M-9) in SAT STEP 38.:
OPEN position. UNSAT STANDARD: Operator places HS-30-48A AND HS-30-48B in the OPEN position, Critical Step verifies red light on HS-30-48A ON.
PLACE HS-30-48A and B in the P-AUTO position. SAT STEP 39.:
UNSAT STANDARD: Operator places both HSs in the P-AUTO position.
Critical Step INFORM the US/SRO that the containment has been vented __ SAT STEP 40.:
and that the automatic pressure control system has been placed back in service. __ UNSAT STANDARD: Operator informs the US/SRO that the containment has been vented and that the automatic pressure control system has been placed back in service. Stop Time_._
/
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION O-SO-30-8 CONTAINMENT PRESSURE CONTROL Revision 13 QUALITY RELATED PREPARED/PROOFREAD BY: CHERYL D. MORRIS RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J.A. DVORAK I,
LEVEL OF USE: CONTINUOUS USE EFFECTIVE DATE: 14 Aug 02 REVISION DESCRIPTION: Revised to incorporate RT-020067, which added the containment purge radiation monitors as required to be operable during containment venting. This is an intent change.
TABLE OF CONTENTS Page 1 of 2 Section Title Page TABLE OF CONTENTS ............................................................................................... 2
1.0 INTRODUCTION
............................................................................................................ 4 1.1 Purpose .................................................................................................................... 4 1.2 Scope ....................................................................................................................... 4
2.0 REFERENCES
............................................................................................................... 4 2.1 Perform ance References ..................................................................................... 4 2.2 Developm ental References ................................................................................... 4 3.0 PRECAUTIONS AND LIMITATIONS ............................................................................ 5
/ 4.0 PREREQUISITE ACTIONS ........................................................................................... 6 5.0 STARTUPISTANDBY READINESS ............................................................................ 7 5.1 Placing Containment Automatic Vacuum Control in Service .................................. 7 5.2 Placing Containment Pressure Relief System in Service ...................................... 10 6.0 NORMAL OPERATION ................................................................................................ 19 7.0 SHUTDOW N .................................................................................................................. 20 7.1 Removing Containment Automatic Vacuum Control from Service .......................... 20 7.2 Removing Containment Pressure Relief System from Service ............................... 21 8.0 INFREQUENT OPERA TION ....................................................................................... 23 9.0 RECORDS ..................................................................................................................... 23
r SQN 1,2 CONTAINMENT PRESSURE CONTROL 0-S0-30-8 Rev: 13 Page 3 of 23 TABLE OF CONTENTS Page 2 of 2 Section Title ATTACHMENT ATTACHMENT 1: POWER CHECKLIST 1-30-8.01 ATTACHMENT 2: POWER CHECKLIST 2-30-8.01 ATTACHMENT 3: POWER CHECKLIST 1-30-8.02 ATTACHMENT 4: POWER CHECKLIST 2-30-8.02
SQN 0-SO-30-8 CONTAINMENT PRESSURE CONTROL Rev: 13 1,2 Page4 of 23
1.0 INTRODUCTION
1.1 Purpose This Instruction provides the steps necessary for the operation of the Containment Pressure Control System.
1.2 Scope A. Containment Automatic Vacuum Control B. Containment Pressure Relief
2.0 REFERENCES
2.1 Performance References A. 1(2)-SI-OPS-030-286.0 2.2 Developmental References A. Technical Specification
- 1. 3.6.1.4
- 2. 3.6.1.9
- 3. 3.6.3
- 4. 3.6.6
- 1. 45N630-8 thru 11
- 2. 45N703-30-1 thru 4
- 3. 47W610-30-1 and 2
- 4. 47W611-30-1 and 3
- 5. 47W866-1
SQN 0-SO-30-8 CONTAINMENT PRESSURE CONTROL Rev: 13 1,2 Page 5 of 23 3.0 PRECAUTIONS AND LIMITATIONS A. A vacuum of -5.0 inches of water should be maintained in the Shield Building Annulus.
B. The differential pressure of the containment atmosphere with respect to the Shield Building Annulus atmosphere should NOT exceed 0.3 psi or drop below -0.1 psi.
C. The ice condenser doors should be monitored closely during all manipulations of the containment pressure relief valves. A slight imbalance in pressure between the upper and lower compartments will cause the doors to open (lower compartment > upper compartment pressure).
D. In the event, a high radiation alarm occurs on the Auxiliary Building Vent Monitor (0-RM-90-101) or Containment radiation monitors (RM-90-106 or 112),
rFCV-30-14/561 and [FCV-30-151571 must be isolated or initiate a containment vent isolation signal.
E. The Containment Pressure Relief Valves must NOT be opened unless either the Annulus has been cleared of personnel or the RADCON Shift Supervisor has waived the requirement to clear personnel from the Annulus.
F. Releases made in between containment sample times can be initiated without a sample provided the lower containment radiation monitor noble gas countrate has NOT increased by more than 50 percent of the release package's current sample countrate.
SON o-SO-30-8 CONTAINMENT PRESSURE CONTROL Rev: 13 1,2 Page 6 of 23 Unit Date 4.0 PREREQUISITE ACTIONS NOTE Throughout this Instruction, where an IFITHEN statement exists, the step should be N/A if the stated condition does NOT exist.
[1] ENSURE the Instruction to be used is a copy of the effective version.
[2] ENSURE the Precaution and Limitation Section 3.0 have been reviewed.
[3] INDICATE below which performance section of this Instruction will be used and the reason for its performance.
E] 5.0 STARTUP/STANDBY READINESS El 6.0 NORMAL OPERATIONS El 7.0 SHUTDOWN El 8.0 INFREQUENT OPERATION REASON:
Unit Date.
5.0 STARTUP/STANDBY READINESS 5.1 Placing Containment Automatic Vacuum Control in Service NOTE 1 The containment design negative pressure differential with respect to the annulus atmosphere is 0.5 psi. The check valve if portions of the automatic vacuum relief valves are set to open the differential pressure of the containment atmosphere with respect to the Shield Building annulus atmosphere is -0.1 psi as read on rPDI-30-1331 on panel M-9. This allows the annulus to relieve into the containment.
NOTE 2 The Containment Vacuum Relief Valves shall be in service when in mode 1-4 (LCO 3.6.6.1 Unit I or LCO 3.6.6 Unit 2).
NOTE 3 rFCV-30-461, FCV-30-471, and rFCV-30-481 will close automatically on high containment pressure of Ž-1.5 psig as sensed by 2 out of 3 of either Train A or Train B pressure switches30-46A, 30-46B,30-47A, 30-47B, or 30-48A,30-48B.
[1] ENSURE Power Checklist complete for the appropriate unit. (N/A checklist NOT applicable.)
Initials I Unit 1 I Power Checklist 1-30-8.01 I Unit 2 Power Checklist 2-30-8.01
Unit Date 5.1 Placing Containment Automatic Vacuum Control in Service (Continued)
NOTE The following chart may be used as an indication of check valve position during performance of the following steps. Full open light indications for Containment Vacuum Relief Check Valves are the same as > 60% open light indications.
CHECK VALVE POSITION CLOSED OPEN OPEN
< 60% > 60%
Zone A OFF OFF RED Switch B GREEN OFF OFF Light C GREEN OFF OFF Indication D GREEN OFF OFF
[2] VERIFY Containment Vacuum Relief Check Valve 130-5711 CLOSED by the position indicator lights below (panel M-9):
INDICATOR LIGHT ZS-30-46A OFF ZS-30-46B GREEN ZS-30-46C GREEN ZS-30-46D GREEN
[3] VERIFY Containment Vacuum Relief Check Valve
[30-5721 CLOSED by the position indicator lights below (panel M-9):
INDICATOR LIGHT ZS-30-47A OFF ZS-30-47B GREEN ZS-30-47C GREEN ZS-30-47D GREEN
Unit Date.
5.1 Placing Containment Automatic Vacuum Control in Service (Continued)
[4] VERIFY Containment Vacuum Relief Check Valve 130-573 CLOSED by the position indicator lights below (panel M-9):
INDICATOR LIGHT ZS-30-48A OFF ZS-30-48B GREEN ZS-30-48C GREEN ZS-30-48D GREEN
[5] OPEN rFCV-30-461 by placing fHS-30-46A1 and rHS-30-46B] (panel M-9) in the OPEN position.
[6] PLACE rHS-30-46A1 in the P-AUTO position. 1st IV
[7] PLACE rHS-30-46B] in the P-AUTO position. 1st IV
[8] OPEN [FCV-30-47] by placing rHS-30-47A1 and rHS-30-47B1 (panel M-9) in the OPEN position. 1st IV
[9] PLACE rHS-30-47A1 in the P-AUTO position. 1 st IV
[10] PLACE [HS-30-47B] in the P-AUTO position. 1st IV
[11] OPEN [FCV-30-48] by placing rHS-30-48A1 and [HS-30-48B1 (panel M-9) in the OPEN position. 1st IV
[12] PLACE [HS-30-48A] in the P-AUTO position. 1 st IV
[13] PLACE [HS-30-48B1 in the P-AUTO position. 1st IV END OF TEXT
Unit Date 5.2 Placing Containment Pressure Relief System in Service NOTE I The Containment Pressure Relief System will be placed in service when differential pressure of the containment atmosphere with respect to the Shield Building annulus atmosphere reaches or is expected to reach 0.3 psi as read on rPDI-30-1331 on panel M-9.
NOTE 2 During normal operations, the Containment Pressure Relief Valves are closed.
[1] ENSURE Power Checklist complete for the appropriate unit.
(N/A checklist NOT applicable.)
Initials Unit 1 Power Checklist 1-30-8.02 Unit 2 Power Checklist 2-30-8.02
[2] ENSURE that the check valve portion of the containment vacuum relief assembly is capable of closing by observing monitor lights on panel M-9.
[3] IF the Unit is in Modes 1, 2, or 3, THEN NOTIFY the US (SRO) that the Environmental Allowance Monitor (EAM) will be placed in the Adverse Containment condition for venting containment.
[4] EVALUATE entry into LCO 3.6.6 Vacuum Relief Lines.
Unit Date_
5.2 Placing Containment Pressure Relief System in Service (Continued)
NOTE The EAM pushbuttons are located inside the back panel on racks 1, 5, 11, and 12 in the Auxiliary Instrument Room. Key is on the #116 key ring for Unit 1 and #117 key ring for Unit 2.
[5] IF the Unit is in Modes 1, 2, or 3, THEN PERFORM the following:
[a] IF the EAM is NOT in the Adverse Containment condition, THEN PLACE OR DIRECT AUO to PLACE the EAM in the Adverse Containment condition by depressing the ACTUATE button in each rack as follows:
_ _ _Initials Rack 1 XS-30-45F Rack 5 XS-30-44F Rack 11 XS-30-43F Rack 12 XS-30-42F
SQN O-SO-30-8 CONTAINMENT PRESSURE CONTROL Rev: 13 1,2 Page 12 of 23 Unit Date_
5.2 Placing Containment Pressure Relief System in Service (Continued)
[b] ENSURE blue purge/vent operation permissive lights illuminated for each steam generator (Located above the S/G NR level indicators on panel M-4).
Initials S/G Level Adverse Setpoint, Prot Set I XI-3-203 illuminated S/G Level Adverse Setpoint, Prot Set IF XI-3-204 illuminated Set III S/G Level Adverse Setpoint, Prot XI-3-205 illuminated Setpoint, Prot Set IV S/MG Level Adverse illuminated Xl-3-206
[c] VERIFY window 30 "Steam Gen Level Adverse
-> Setpoint" illuminated on XA-55-3C.
[6] IF the Unit is in Modes 1-4, THEN
[a] VERIFY Radiochemical Laboratory has a current weekly performance of 0-SI-CEM-030-410.1 in progress.
[bi IF the noble gas countrate for the lower containment radiation monitor has increased by more than 50 percent since last sample time, THEN TRANSMIT the release permit to the Chemistry Laboratory to obtain another (noble gas and tritium) set of samples.
Unit Date 5.2 Placing Containment Pressure Relief System in Service (Continued)
NOTE The Containment Pressure Relief System duct and dampers are part of the Containment Purge System. 0-SO-30-3 must be referenced to determine dampers that remain closed during release of containment pressure to the Annulus.
[7] ENSURE that the Shield Building Annulus Vacuum Control System is in service and maintaining a negative 5.0 inches of water pressure as indicated on M-9, rPDI-30-126] or
[PDI-30-1271 or EGTS in service or EGTS testing in progress.
[8] VERIFY NO abnormal or unexplainable radiation levels exist inside containment.
[9] VERIFY that NO containment vent isolation signal exists.
[10] ENSURE at least ONE of the following radiation monitors in service for the appropriate unit:
RADIATION MONITOR I/S U-1 Containment 1-RM-90-130 E Purge Exhaust Monitors 1-RM-90-131 El U-2 Containment 2-RM-90-130 Li Purge Exhaust Monitors 2-RM-90-131 El NOTE Step [11] may be N/A if RADCON Shift Supervisor has waived this requirement and his approval has been documented in the Operator's Daily Journal.
[11] VERIFY that all personnel have been evacuated from the Annulus and that all doors are closed.
SQN 0-SO-30-8 CONTAINMENT PRESSURE CONTROL Rev: 13 1,2 Page 14 of 23 Unit Date 5.2 Placing Containment Pressure Relief System in Service (Continued)
NOTE SM may N/A step [12] if Tech Spec conditions are being met.
[12] ENSURE at least one of the following radiation monitors in service for the appropriate unit:
RADIATION MONITOR I/S AB Vent O-RM-90-1 01 B El Upper Compartment 1-RM-90-112 A & B El 2-RM-90-112 A & B El Lower compartment 1-RM-90-106 A & B El 2-RM-90-106 A & B El
[13] IF the Unit is in Modes 1-4, THEN LOG time in 1(2)-SI-OPS-030-286.0.
SQN O-SO-30-8 CONTAINMENT PRESSURE CONTROL Rev: 13 1,2 Page 15 of 23 Unit Date 5.2 Placing Containment Pressure Relief System in Service (Continued)
CAUTION In modes 1-4, only one set of purge supply and/or exhaust lines shall be used to vent containment.
NOTE 1 [FCV-30-14/561 and rFCV-30-15/571 or fFCV-30-371 and FFCV-30-401 may be used to vent containment to the Annulus.
rFCV-30-37] and [FCV-30-401 are used as an alternate flow path.
NOTE 2 Swapover to backup pressure control is expected during containment venting when differential pressure between Annulus and Aux Bldg is
< - 4.5 inches of H20. On Unit 1, 1-PCO-65-93 will close and 1-PCO-65-94 will open to place backup pressure controller 1-PDIC-65-48 in service. On Unit 2, 2-PCO-65-96 will close and 2-PCO-65-95 will open to place backup pressure controller 2-PDIC-65-1 in service.
[14] IF aligning the lower compartment purge isolation valves using the NORMAL flow path, THEN PERFORM steps [a] through [f].
[a] ENSURE rFCV-30-371 CLOSED. El
[b] ENSURE rFCV-30-401 CLOSED. El
[c] OPEN [FCV-30-141 and rFCV-30-561 with rHS-30-141. 11
[d] VERIFY rFCV-30-141 and rFCV-30-56]
are OPEN. El
[e] OPEN rFCV-30-151 and [FCV-30-571 with 'HS-30-1 5. El
[f] VERIFY [FCV-30-151 and rFCV-30-571 are OPEN. El
Unit Date 5.2 Placing Containment Pressure Relief System in Service (Continued)
[15] IF aligning the lower compartment purge isolation valves using the ALTERNATE flow path, THEN PERFORM steps [a] through [h].
[a] ENSURE rFCV-30-141 CLOSED. E]
[b] ENSURE [FCV-30-56 CLOSED. 11
[c] ENSURE rFCV-30-151 CLOSED. El
[d] ENSURE rFCV-30-571 CLOSED. El
[e] OPEN rFCV-30-37] with rHS-30-371. El
[f] VERIFY [FCV-30-371 is OPEN. El
[g] OPEN [FCV-30-401 with [HS-30-401 El
[h] VERIFY [FCV-30-401 is OPEN. El
[16] OPEN Annulus exhaust isolation valve rFCV-30-541 with rHS-30-54]. El
Unit Date 5.2 Placing Containment Pressure Relief System in Service (Continued)
NOTE 1 Venting containment with both Annulus Vacuum Control Fans should take approximately 15 minutes.
NOTE 2 The following step is N/A if EGTS is in service during the containment vent.
[17] IF the Annulus Vacuum Control System is in service AND the standby Annulus Vacuum Control Fan is available, THEN START the standby Annulus Vacuum Control Fan.
[18] IF a high radiation alarm occurs on any of the following Radiation monitors, AB Vent 0-RM-90-101B Upper 1-RM-90-112 A & B Compartment 2-RM-90-112 A & B Lower 1-RM-90-106 A & B Compartment 2-RM-90-106 A & B Containment 1-RM-90-130 Purge Exhaust 1-RM-90-131 Monitors 2-RM-90-130 2-RM-90-131 THEN:
[a] ENSURE the following CLOSED:
DAMPER 1 ST IV FCV-30-14/56 FCV-30-15/57 FCV-30-37 FCV-30-40
SQN o-SO-30-8 CONTAINMENT PRESSURE CONTROL Rev: 13 1,2 Page 18 of 23 Unit Date 5.2 Placing Containment Pressure Relief System in Service (Continued)
[b] IF dampers can not be closed, THEN MANUALLY INITIATE a containment vent isolation signal in accordance with
!,2-SO-88-1 (Containment Vent Isolation).
[19] WHEN the containment vent is completed, THEN PERFORM Section 7.2 END OF TEXT
I SQN 1,2 CONTAINMENT PRESSURE CONTROL 0-SO-30-8 Rev: 13 Page 20 01f23 Unit Date 7.0 SHUTDOWN 7.1 Removing Containment Automatic Vacuum Control from Service
[1] CLOSE 'FCV-30-46] by placing FHS-30-46A1 and THS-30-46B1 (panel M-9) in the CLOSE position.
[2] PLACE rHS-30-46A1 in the P-AUTO position.
[3] PLACE rHS-30-46B1 in the P-AUTO position.
14] CLOSE rFCV-30-471 by placing rHS-30-47A1 and jHS-30-47B]
(panel M-9) in the CLOSE position.
[5] PLACE rHS-30-47A1 in the P-AUTO position.
[6] PLACE rHS-30-47B1 in the P-AUTO position.
[7] CLOSE [FCV-30-48 by placing [HS-30-48A] and [HS-30-48B1 (panel M-9) in the CLOSE position.
[8] PLACE rHS-30-48A1 in the P-AUTO position.
[9] PLACE rHS-30-48B1 in the P-AUTO position.
[10] IF the normal pressure control isolation dampers rl-PCO-65-931 OR [2-PCO-65-961 are CLOSED, THEN PERFORM Restoration of Normal Annulus-Vacuum Pressure Control section of O-SO-65-1 to reopen dampers.
END OF TEXT
Unit Date 7.2 Removing Containment Pressure Relief System from Service
[1] IF both Annulus Vacuum Control Fans are running, THEN STOP one of the Annulus Vacuum Control Fans.
1st IV
[2] IF Lower Compartment Purge Isolation Valves are aligned through the NORMAL flow path, THEN PERFORM steps [a] through [f].
[a] PLACE rHS-30-141 in the CLOSED position. 17
[b] PLACE rHS-30-151 in the CLOSED position. El
[c] VERIFY rFCV-30-14] CLOSED.
1st IV
[d] VERIFY [FCV-30-56 CLOSED.
1st IV
[e] VERIFY [FCV-30-151 CLOSED.
1st IV
[f] VERIFY rFCV-30-57] CLOSED.
1st IV
[3] IF Lower Compartment Purge Isolation Valves are aligned through the ALTERNATE flow path, THEN PERFORM steps [a] through [d].
[a] PLACE rHS-30-371 in the CLOSED position. El
[b] PLACE rHS-30-401 in the CLOSED position.
E]
[c] VERIFY fFCV-30-371 CLOSED.
1st IV
[d] VERIFY [FCV-30-401 CLOSED.
1st IV
Unit Date 7.2 Removing Containment Pressure Relief System from Service (Continued)
[4] CLOSE the Annulus Exhaust Isolation Valve rFCV-30-541 with IHS-30-541.
1st IV
[5] RESTORE Normal Annulus Vacuum Pressure Control on the affected unit per 0-SO-65-1 Section 8.1.
[6] IF the Unit is in Modes 1-4, THEN LOG time in 1(2)-SI-OPS-030-286.0.
1st IV END OF TEXT
8.0 INFREQUENT OPERATION None 9.0 RECORDS Completed copies of the attachments shall be placed in the appropriate Unit's Status file. All sections will be sent to Operations Superintendent Secretary after completion.
JPM # 14AP Page 1 of 7 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 14AP Control Room Inaccessibility (Fire in the Spreader Room)
Original Signatures on File PREPARED/
REVISED BY: Date/
VALIDATED BY:
- Date/
APPROVED BY: Date/
(Operations Training Manager)
CONCURRED: ** Date/
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM # 14AP Page 2 of 7 Rev, 0 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION AFFECTED REVISED BY:
0 New Y 8/19/02 All J P Kearney V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM # 14AP Page 3 of 7 Rev. 0 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task:
Control Room Inaccessibility (Fire In the Spreader Room)
JAITA task # : 0000680501 (RO)
K/A Ratings:
06SAA1.23 (4.3/4.4)
Task Standard:
Unit 1 MCR has been abandoned per AOP-C.04 for an Appendix R fire in the spreading room.
Evaluation Method : Simulator X In-Plant Performer:
NAME Start Time Performance Rating: SAT _ UNSAT Performance Time Finish Time Evaluator: /
SIGNATURE DATE COMMENTS
JPM # 14AP Page 4 of 7 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Sequenced steps identified by an "I"
- 2. Any UNSAT requires comments
- 3. Initialize in IC # 10 with all controls aligned normally.
- 4. FREEZE the simulator until the operator has been briefed.
- 5. Provide an additional board operator as CRO to handle the actions of ES-0.1 while the OATC addresses the actions of AOP-C.04.
- 6. Ensure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. 8 mins Local Tools/Equipment/Procedures Needed:
AOP-C.04, Section 2.0 & 2.1.
References:
SReference Title Rev No.
A. AOP-C.04 Control Room Inaccessibility 5 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. 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. Ensure you indicate to me when you understand your assigned task.
To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 1 is at 100% power.
A fire is in progress in the Control Building spreading room. The SM has declared an Appendix R fire and has decided to abandon the control room.
INITIATING CUES:
You are the Unit 1 OATC and are to perform the required actions of AOP-C.04 to abandon the main control room.
Inform the US when you are prepared to leave the main control room.
JPM # 14AP Page 5 of 7 Rev. 0 Job Performance Checklist:
STEPISTANDARD SAT/UNSAT STEP 1.: Obtains a copy of the appropriate procedure. SAT UNSAT STANDARD: Operator obtains AOP-C.04, Section 2.0 and determines that section 2.1 will be required to address abandoning the control room. Start Time__
STEP 2.: ENSURE reactor tripped. SAT SUNSAT STANDARD: Operator TRIPS the Reactor and VERIFIES reactor tripped by:
Reactor trip breakers open Bypass breakers open or disconnected Critical Step Neutron flux dropping.
STEP 3.: ENSURE MSIV and MSIV bypass valve handswitches in CLOSE. __ SAT STANDARD: The operator places (4) HSs for MSIV in the closed position and verifies Red light OFF and Green and Blue light ON.
Critical Step STEP 4.: IF abandoning MCR due to Appendix R fire, THEN ALIGN the __ SAT following switches:
- PLACE one CCP in STOP/PULL TO LOCK. __ UNSAT Cue: SM has declaredan Appendix R fire in the spreadingroom.
Critical Step STANDARD: The operator places HS for the 1A CCP in Stop/PTL.
STEP 5.: IF abandoning MCR due to Appendix R fire, THEN ALIGN the __ SAT following switches:
- PLACE pressurizer PORV handswitches in CLOSE position. __ UNSAT STANDARD: The operator places pressurizer PORV handswitches in CLOSE Critical Step position.
STEP 6.: IF abandoning MCR due to Appendix R fire, THEN ALIGN the __ SAT following switches:
- PLACE pzr spray controllers in MANUAL and ADJUST output to __ UNSAT zero.
Critical Step STANDARD: The operator places pzr spray controllers in MANUAL and adjusts output to zero.
JPM Page #614APof 7 Rev. 0 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD SSAT STEP 7.: IF abandoning MCR due to Appendix R lire, THEN ALIGN the SUNSAT following switches:
in CLOSE
- PLACE S/G atmospheric relief valve handswitches position.. Critical Step handswitches in STANDARD The operator places S/G atmospheric relief valve CLOSE position.
SS AT ALIGN the STEP B.: IF abandoning MCR due to Appendix R fire, THEN SUNSAT following switches:
MANUAL and
.PLACE S/G atmospheric relief valve controllers in ADJUST output to zero. Critical Step relief valve controllers in STANDARD: The operator places S/G atmospheric MANUAL and adjusts output to zero.
-- SAT STEP 9.: PLACE RCP handswitches in STOP/PULL TO LOCK SUNSAT in STOP/PULL TO LOCK.
STANDARD: The operator places RCP handswitches Critical Ste_
SAT CLOSE/PULL-TO-LOCK.
STEP 10.: PLACE TD AFW LCV handswitches in SUNSAT handswitches in STOP/PULL TO STANDARD: The operator places TD AFW LCV Critical Step LOCK.
-- SAT STEP 11.: ENSURE the following handswitches placed in TRIP: [1-M-151 UNSAT
- t%I . flfA
- U-I-lO 0-HS-103-205I - u +
I 0 -H S 2 0 5 Cr itical St ep in TRIP.
STANDARD: The operator places handswitches the Main Control Room" _ SAT STEP 12.: ANNOUNCE "Unit I Reactor trip, abandoning UNSAT USING PA System.
that the unit has been tripped and STANDARD: Operator announces over the P.A. abandoned. He should repeat that the Main Control Room is being the message a second time.
JPM # 14AP Page 7 of 7 Rev. 0 Job Performance Checklist:
STFPlSTANDARD SAT/UNSAT STEP/STANDARD I SAT STEP 13.: ENSURE the following items are taken to the Auxiliary Control Room when Main Control Room is evacuated: UNSAT flow prints radios CUE: Unit 2 operatorreported they will take these prints and the radios with them.
STANDARD: Operator ensures the flow prints and radios are taken to the ACR.
STEP 14.: EVACUATE Main Control Room. __ SAT UNSAT CUE: When Operatorreports or starts to leave tell him JPM is complete. Stop Time_
STANDARD: Operator reports to the US he is ready to abandon the MCR or starts to leave MCR.
I TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOI PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM Revision 5 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: I A 1fl\/flPAK
ý-f JA DVORAK EFFECTIVE DATE: 28 June 02 REVISION DESCRIPTION: Deleted actions associated with spurious opening of 2-FCV-63-72 and -73. These actions are no longer necessary for Unit 2 following completion of DCN D21153A. Revised checklists 5 and 6 as a result of PERs 02-003510-000 and 02-003550-000. Deleted or delayed various transfer switch manipulations which are not needed. Added guidance on monitoring RWST level locally.
Deleted unnecessary substep in Checklists 3 & 4 which repositioned CCP aux oil pump interlock bypass switch.
This is an intent revision.
SQN SHUTDOWN FROM AUXILIARY CONTROL ROOM AOP-C.04 Rev. 5 1.0 PURPOSE This procedure provides actions necessary for Control Room abandonment, plant cooldown from the Auxiliary Control Room, and return to Main Control Room operation. This AOP may be used to transfer control to ACR on one unit or both units.
This procedure is relied upon for Appendix R Safe Shutdown for Control Building fires.
Page 2 of 174
K SQN STEP SHUTDOWN FROM AUXILIARY CONTROL ROOM ACTIONIEXPECTED RESPONSERESPONSE NOT OBTAINED AOP-C.04 Rev. 5 2.0 OPERATOR ACTIONS CAUTION A major fire in spreading room could result in collapse of the MCR floor.
If entering this AOP for a spreading room fire, both units should abandon the MCR.
- 1. DETERMINE required actions:
GO TO IF... SECTION PAGE Abandoning the Main Control Room 2.1 4 Performing Plant Cooldown from Auxiliary Control Room 2.2 28 Returning to Main Control Room operation 2.3 43 END OF SECTION C
Page 3 of 174
SHUTDOWN FROM AUXILIARY CONTROL ROOM 5 AOPCRev.
SQN STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINE 2.1 Control Room Abandonment
- 1. ENSURE reactor TRIPPED: [M-4] IF reactor CANNOT be tripped from MCR, THEN
"* Reactor trip breakers OPEN DISPATCH operator to perform one of the following:
"* Reactor trip bypass breakers OPEN or DISCONNECTED " OPEN reactor trip breakers and MG set output breakers locally.
"* Neutron flux DROPPING [AB el. 759 MG Set Room]
" OPEN breakers to MG sets locally.
[TB, 480V Unit Boards]
-7.
Page 4 of 174
STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 Control Room Abandonment (cont'd)
- 3. IF abandoning MCR due to Appendix R fire, THEN ALIGN the following switches:
- PLACE one CCP in STOP/PULL TO LOCK.
PLACE pressurizer PORV handswitches in CLOSE position.
PLACE pzr spray controllers in MANUAL and ADJUST output to zero.
- PLACE S/G atmospheric relief valve handswitches in CLOSE position.
PLACE S/G atmospheric relief valve controllers in MANUAL and ADJUST output to zero.
- 4. PLACE RCP handswitches in STOP/PULL TO LOCK. [M-5]
Page 5 of 174
RESPONSE NOT OBTAINED STEP ACTIONIEXPECTED RESPONSE-2.1 Control Room Abandonment (cont'd) valves The following step trips shunt trip breakers for thermal barrier isolation NOTE on both units and various ERCW and CCS valves.
- 6. ENSURE the following handswitches placed in TRIP: [1-M-15]
0O-HS-13-204 0O-HS-13-205
- 7. ANNOUNCE"Unit Reactor trip, abandoning the Main Control Room" USING PA System.
emergency.
NOTE Radio use is allowed in ACR during an
- 8. ENSURE the following items are taken to Auxiliary Control Room when Main Control Room is evacuated:
"* flow prints
"* radios
- 9. EVACUATE Main Control Room on affected unit(s).
Page 6 of 174
JPM #99AP Page 1 of 6 Rev. 4 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 99AP Locally Align 1B-B CCS Pump to Supply the B Train Header Original Signatures on File PREPARED/
REVISED BY: Date/
VALIDATED BY: Date/
APPROVED BY: Date/
(Operations Training Manager)
CONCURRED: ** Date/
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM #99AP Page 2 of 6 Rev. 4 2 NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBERj REVISION I AFFECTED REVISED BY:
3 Chgd to AP since one MOV will not N 8/14/96 All HJ Birch operate electrically, must open manually.
Incorp previous pen/inks which added cues to step 2,4,5 and chgd performance time based on requal performance 0-SO-70-1 Rev chg only 8/11/97 4 HJ Birch pen/ink step 2 chg light from green to red in cue 9/22/97 5 HJ Birch per requal feedback.
0-SO-70-1 Rev chg only 2/2/98 4 HJ Birch Requal comment - No HS in MCR. Chg 5/13/98 4 HJ Birch cue to MOV bd pen/ink SO-70-1 revision had no impact. Revised 9/25/98 All JP Kearney K/A ratings. Reformatted critical steps.
pen/ink SO-70-1 revision update only 10/16/98 4 JP Kearney pen/ink SO-70-1 revision update only 9/21/99 4 SR Taylor pen/ink SO-70-1 revision update only 8/29/00 4 SR Taylor pen/ink SO-70-1 rev. Update 12/4/01 4 L. Pauley 4 Incorporated pen/ink changes; revised to 8/21/02 ALL J P Kearney recent revision of 0-SO-70-1; no impact on JPM flow V - Specify if the JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM #99AP Page 3 of 6 Rev. 4 SEQUOYAH NUCLEAR PLANT AUO/RO/SRO JOB PERFORMANCE MEASURE Task:
Locally Align 1B-B CCS Pump to Supply the B Train Header JA/TA TASK #:0080060101 (RO) 0080010104 (AUO)
K/A Ratings:
008A2.01 (3.3/3.6) 008A4.01 (3.3/3.1) 008A4.06 (2.5/2.5)
Task Standard:
Perform local (manual) alignment of the 1 B-B pump to supply the B train CCS header.
Evaluation Method : Simulator In-Plant X Performer:
NAME Start Time Performance Rating: SAT UNSAT Performance Time Finish Time Evaluator: /
SIGNATURE DATE COMMENTS
JPM #99AP Page 4 of 6 Rev. 4 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 11. Sequenced steps identified by an "s"
- 2. Any UNSAT requires comments
- 3. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. Local 13 mins Tools/Equipment/Procedures Needed:
0-SO-70-1 Section 8.3, step 5c ("Initia" steps that had been completed)
References:
Title Rev No.
- 1. 0-SO-70-1 Component Cooling Water System B Train 23 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. I will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Both units are operating at full power.
- 2. The C-S CCS pump tripped on over current, WCG has been notified to initiate maintenance.
- 4. The 1 B-B CCS pump is aligned for standby but the control switches have been placed in the PULL TO LOCK position.
INITIATING CUES:
- 1. You are the U1 Aux. Bldg. AUO, the U2 CRO has directed you to complete alignment of the 1 B-B CCS pump to supply the B train header per 0-SO-70-1, Section 8.3 step 5c.
- 2. 0-FCV-70-34 will NOT operate from the MOV Bd, you are to close this FCV locally as well as align the manual valves. Valves 1-FCV-70-64, 1-FCV-70-74, 1-FCV-70-26, and 1-FCV-70-27 have been opened from the MOV Bd.
JPM #99AP Page 5 of 6 Rev. 4 Job Performance Checklist:
sTEP/STANnARD SAT/UNSAT sTEP/SANDAT
/- STEP 1: Operator obtains a copy of the procedure. SAT UNSAT STANDARD: Operator obtains a copy of 0-SO-70-1, to perform Sections 8.3, step 5c Start Time I
STEP 2: CLOSE O-FCV-70-34 1A-A and 1 B-B suction crosstie. SAT UNSAT NOTE: Valve is located on the mezzanine above the CCS pumps directly in front and to left of the access ladder. Critical Step Cue: If operatorgoes to the MOV Bd OR the local controlswitch to operatethe valve, state: RED light only (local: No movement in valve)
Cue: HW turned several times in the CW directionand is now snug, position indicatoris pointing at CLOSED.
STANDARD: Operator locates 0-FCV-70-34, engages manual operation lever, turns HW in CW direction until snug and verifies position indicator pointing at CLOSED.
t STEP 3: CLOSE 1-70-507 1A-A and 1 B-B discharge crosstie. SAT UNSAT NOTE: Valve is located on the 2nd level of the mezzanine above the CCS pumps approx. 10 ft to the right of the ladder.
Critical Step Cue: HW turnedseveral times in the CW direction and is now snug. Pointeris pointing to CLOSED position.
STANDARD: Operator locates 1-70-507 turns HW in CW direction until snug.
STEP 4: Open 1-FCV-70-64, 70-74, 70-26, and 70-27. __ SAT Cue: Report valves have been opened per initiatingcues. __ UNSAT STANDARD: Valves opened per initiating cues.
K->
JPM #99AP Page 6 of 6 Rev. 4 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 5: VERIFY open 1-70-503B, CCS Pump 1B-B suction. __ SAT UNSAT Cue: Handwheel moves CW, but will not move CCW, Indicator points to open.
STANDARD: Operator locates 1-70-503B and verifies valve open by no movement of handwheel in CCWdirection.
STEP 6: VERIFY open 1-70-505B, CCS Pump 1 B-B discharge. __ SAT UNSAT Cue: Handwheel moves CW, but will not move CCW, Indicator points to open.
STANDARD: Operator locates 1-70-505B and verifies valve open by no movement of chain operated handwheel in CCW direction and pointer indication open.
STEP 7: Inform the U2 CRO that the 1B-B CCS pump is aligned to supply SAT the B train CCS header.
UNSAT STANDARD: Operator informs the U2 CRO that the 1B-B CCS pump is Stop Time aligned to supply the B train CCS header.
Date 8.3 Swapping 1B-B CCS Pump from A Train to B Train and Back Again NOTE 1 It is desirable to swap "B" pump for unit not supplying SFP HXs NOTE 2 LCO's 3.4.1.4, 3.5.2, 3.6.2.1, 3.7.3, 3.7.12, and 3.9.8.2 should be evaluated by SRO.
[1] VERIFY SRO has EVALUATED LCO's mentioned in note above. El
[2] IF CCS HX WA1 and 1A2 is in service, THEN VERIFY CCS Pump 1A-A RUNNING.
[3] ENSURE CCS Pump 13B-B is STOPPED AND PULL-TO-LOCK NOTE U-2 will need to supply CCS to SFP HX.
[4] IF U-1 is supplying CCS to SFP HXs, THEN GO TO 1-SO-70-1 to align U-2 to supply CCS to SFP HXs, AND RETURN to Step [5].
Date 8.3 Swapping 1B-B CCS Pump from A Train to B Train and Back Again (Continued)
CAUTION Power may be placed on Appendix R valves to operate them; however, time this is done as well as time power is removed must be recorded in UO daily journal. When power is placed on the valve, maintain an operator at the breaker. If a fire develops in the plant, position the valve as required and open the breaker
[5] PERFORM the following to align CCS Pumps 1 B-B and C-S in parallel:
[a] CLOSE the following breakers on 480V MOV Bd 11B2-B (Appendix R valves):
VALVE FUNCTION COMPT INITIALS Suction Header Isol Between CCS liC O-FCV-70-34 Pumps 1A-A and 1B-B Suction Header Isol Between CCS 10E 1-FCV-7_0-64 Pumps 1B-B and C-S 10E 1I-FCV-70-74 Suction Header Isol Between 1 B-B and 14A 14A C-S Pumps
-FCV7O-26 CCS Pumps 1A-A and 1B-B Discharge 13B Crosstie to C-S Outlet Isol 1-FCV-70-27 CCS Pumps 1A-A and 1B-B Discharge 13C ICrosstie to C-S Outlet Isol
[b] PLACE the following transfer switches (located on 480V MOV bd. 1B2-B), to the "AUX" position:
VALVE TRANSFER SWITCH POSITION COMPT INITIALS 0-FCV-70-34 O-XS-70-34 AUX 11 C 1-FCV-70-64 1-XS-70-64 AUX 10E 1-FCV-70-74 1-XS-70-74 AUX 14A 1-FCV-70-26 1-XS-70-26 AUX 13B 1-FCV-70-27 1-XS-70-27 AUX 13C
SQN 0-SO-70-1 COMPONENT COOLING WATER SYSTEM Rev: 23 0,1,2 "B" TRAIN Page 41 of 109 Date 8.3 Swapping 11B-B CCS Pump from A Train to B Train and Back Again (Continued)
[c] PLACE the following in required position:
VALVE FUNCTION POSITION INITIALS Between CCS CLOSED 0-FCV-70-34 Suction 0-FCV-70-34_
Header Pumps 1A-A andIsol 1B-B CLOSED 1-70-507 Discharge Header Sectionalizing Valve CLOSED CLOSED Between CCS Pump 1A-A and 1B-B Suction Header Isol Between CCS 1-FPumps 1-B-B and C-SOPEN CCS OPEN I -FCV-70-74 1-FCV-70-74_ Suction Header Pumps 1B-B C-SBetween andIsol OPEN 1-FCV-70-26 CCS Pumps IA-A and 1 B-B Discharge OPEN Crosstie to C-S Outlet Isol 1 FCV70-27 CCS Pump 1A-A and 1B-B Discharge OPEN Crosstie to C-S Outlet Isol 1-70-503B CCS Pump 1B-B Suction OPEN 1-70-505B CCS Pump 1B-B Discharge OPEN
[6] START CCS Pump 11B-B with [1-HS-70-38A1 AND VERIFY control switch returns to A-AUTO.
[7] IF CCS Pump C-S is to be removed from service, THEN PERFORM the following:
[a] STOP CCS Pump C-S with appropriate control switch (NIA the other):
CONTROL INITIALS 2-HS-70-51A-S (Norm.)
1-HS-70-51A-S (Alt.)
[b] PLACE the applicable control switch in PULL-TO-LOCK.
Date 8.3 Swapping IB-B CCS Pump from A Train to B Train and Back Again (Continued)
NOTE If developed head is outside required range, adjustments should be made to change flow rate accordingly. Suction pressure (read locally) should be that of running pump. Discharge pressure also read locally for both pumps.
[8] PERFORM the following to ensure running pumps' developed head is within required range (N/A if not running):
[a] CALCULATE developed head:
Discharge - Suction Developed Pressure 0-PI-70-49 Pressure 0- PI-70-50 (Pmp C -S) Head Discharge - Suction = Developed Pressure 0-PI-70-36 Pressure 1-PI-70-37 (Pmp 183- B) Head
[b] ENSURE developed head is > 76 psig, but
- < 100 psig.
[9] OPEN the following breakers on 480V RX MOV Bd 1B2-B (Appendix R va Ives):
VALVE COMP INITIALS 0-FCV-70-34 11C 1st IV 1-FCV-70-64 10E 1st IV 1-FCV-70-74 14A 1st IV 1-FCV-70-26 13B 1st IV 1-FCV-70-27 13C 1st IV
Date 8.3 Swapping 1B-B CCS Pump from A Train to B Train and Back Again (Continued)
[10] PLACE the following transfer switches (located on 480V MOV bd.
1B2-B), to the "NORMAL" position:
VALVE TRANSFER SWITCH POSITION COMPT INITIALS 0-FCV-70-34 O-XS-70-34 NORMAL 11 C 1st IV 1-FCV-70-64 1-XS-70-64 NORMAL 10E 1st IV 1-FCV-70-74 1-XS-70-74 NORMAL 14A 1st IV 1-FCV-70-28 NORMAL 136 1st IV 1-XS-70-26 1-XS-70-27 NORMAL 13C 1 1-FCV-70-27 1St IV
[11] ENSURE the following hand switches (located on 480V MOV bd. 1B2-B), to the "NORMAL" position:
VALVE HAND SWITCH POSITION COMPT INITIALS 0-FCV-70-34 0-HS-70-34C NORMAL 11C 1st IV 1-HS-70-64C NORMAL 10E 1 1 -FCV-70-64 1St IV 1-HS-70-74C NORMAL 14A s 1 -FCV-70-74 1st IV 1 -FCV-70-26 1-HS-70-26C NORMAL 13s 1st IV 1-FCV-70-27 1-HS-70-27C NORMAL 13C I
Date 8.3 Swapping 1B-B CCS Pump from A Train to B Train and Back Again (Continued)
NOTE The C-S pump is powered from 2B2-B 480 shutdown board (Normal) which also powers Vital Inverters. Due to momentary voltage transient associated with starting C-S CCS pump, Vital Inverter abnormal alarms may be received for Vital Inverter 1-IV and 2-IV.
Consideration should be given to the status of work in other channels (i.e. rack or NIS work) when starting C-S CCS pump.
[12] WHEN pump alignment is to be returned to normal, THEN PERFORM the following:
[a] IF CCS Pump C-S is not running and is desired to be in operation, THEN START pump with appropriate control switch AND VERIFY Control switch returns to A-AUTO (N/A the other):
CONTROL INITIALS 2-HS-70-51A-S (Norm.)
1-HS-70-51A-S (Alt.)
[b] STOP CCS Pump 1B-B with rl-HS-70-38A1, AND ENSURE control switch in PULL-TO-LOCK.
NOTE Ifdeveloped head is outside required range, adjustments should be made to change flow rate accordingly. Suction and discharge pressure for C-S pump are read locally.
[c] PERFORM the following to ensure C-S pump's developed head is within required limits (N/A if pump NOT running):
[1] CALCULATE developed head:
Discharge - Suction = Developed Pressure O-PI-70-49 Pressure 0 - PI 70 - 50 Head
F SQN 0-SO-70-1 COMPONENT COOLING WATER SYSTEM Rev: 23 0,1,2 "B" TRAIN Page 45 of 109 Date 8.3 Swapping 1 B-B CCS Pump from A Train to B Train and Back Again (Continued)
[2] ENSURE developed head is >76 psig, but < 100 psig.
CAUTION Power may be placed on Appendix R valves to operate them; however, time this is done as well as time power is removed must be recorded in UO daily journal. When power is placed on the valve, maintain an operator at the breaker. If a fire develops in the plant, position the valve as required and open the breaker
[d] CLOSE the following breakers on Rx MOV Bd. 1B2-B (Appendix R valves):
VALVE FUNCTION COMPT INITIALS Between CCS 110 O-FCV-70-34 Suction Pumps 1A-AHeader andIsol 1B-B 11C 1-FCV-70-64 Suction Header Isol Between CCS 10E 10E Pumps 1B-B and C-S Suction Header Isol Between CCS 1-FCV-70-74 Pumps 1B-1 and C-S14A 1-FCV-70-26 CCS Pumps 1A-A and 1B-B to C-S 13B Outlet Isol 13B 130 I1-FCV-70-27 CCS Pumps 1B-B
,to C-S Outlet Isol Discharge Crosstie 13C
[e] PLACE the following transfer switches (located on 480V MOV bd. 11B2-B), to the "AUX" position:
VALVE TRANSFER SWITCH POSITION COMPT INITIALS 0-FCV-70-34 0-XS-70-34 AUX 11C 1-FCV-70-64 1-XS-70-64 AUX 10E 1-FCV-70-74 1-XS-70-74 AUX 14A 1-FCV-70-26 1-XS-70-26 AUX 13B 1-FCV-70-27 1-XS-70-27 AUX 13C
Date 8.3 Swapping 1B-B CCS Pump from A Train to B Train and Back Again (Continued)
[f] PLACE the following in required position to return CCS Pumps 1B-B and C-S to normal alignment:
VALVE FUNCTION POSITION INITIALS Suction Header Isol Between CCS Pumps 1B-B and C-S CLOSED 1st IV 1-FCV-70-64 Suction Header Isol Between CCS Pumps 1B-B and C-S CLOSED 1st IV 1-FCV-70-74 CCS Pumps 1A-A and 1B-B Discharge Crosstie to C-S Outlet Isol CLOSED 1st IV 1-FCV-70-26 CCS Pumps 1A-A and 1B-B CLOSED 1st IV l-FCV-70-27 Discharge Crosstie to C-S Outlet Isol Suction Header Isol Between CCS Pumps 1A-A and 1B-B OPEN 1st IV 0-FCV-70-34 K->
Discharge Header Sectionalizing Valve Between CCS Pump lA-A and 1-70-507 1B-B OPEN 1st IV
[g] PLACE the following transfer switches (located on 480V MOV bd. 1 B2-B), to the "NORMAL" position AND VALVE TRANSFER SWITCH POSITION COMPT INITIALS 0-FCV-70-34 O-XS-70-34 NORMAL 11C 1st IV 1-FCV-70-64 1-XS-70-64 NORMAL 10E 1st IV 1-FCV-70-74 I-XS-70-74 NORMAL 14A 1St 1-FCV-70-26 1 -XS-70-26 NORMAL 13B Ist NORMAL 13C s 1-FCV-70-27 l-XS-70-27 1St IV N-,
Date 8.3 Swapping IB-B CCS Pump from A Train to B Train and Back Again (Continued)
[h] ENSURE the following hand switches (located on 480V MOV bd. 1B2-B), to the "NORMAL' position:
VALVE HAND SWITCH POSITION COMPT f INITIALS 0-FCV-70-34 0-HS-70-34C NORMAL 11C 1st IV 1-FCV-70-64 1-HS-70-64C NORMAL 10E 1st IV 1-FCV-70-74 1-HS-70-74C NORMAL 14A 1st IV 1-FCV-70-26 1-HS-70-26C NORMAL 13B
-A 1st IV 1-FCV-70-27 1-HS-70-27C NORMAL 13C I 1st IV
[i] OPEN the following breakers on 480V Rx MOV Bd. 1 B2-B (Appendix R valves):
VALVE COMPT INITIALS 0-FCV-70-34 11C 1st IV 1-FCV-70-64 10E 1st IV 1-FCV-70-74 14A 1st IV 1-FCV-70-26 13B 1st IV 1-FCV-70-27 13C 1st IV
Date 8.3 Swapping 11B-B CCS Pump from A Train to B Train and Back Again (Continued)
[13] ENSURE CCS Pump 1B-B control switch returns to A-AUTO rl-HS-70-38A1. El
[14] IF SFP HX will be realigned to U-i, THEN GO TO 1-SO-70-1. 11 END OF TEXT
JPM # 42 Page 1 of 12 Rev 12 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM # 42 Placing Vital Inverter 1-11 Back in Service Following Maintenance Original Signatures on File PREPARED/
REVISED BY: Date/
- Date/
VALIDATED BY:
APPROVED BY: Date/
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
- Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM # 42 Page 2 of 12 Rev 12
-' NUCLEAR TRAINING REVISION/USAGE LOG REVISION DESCRIPTION OF V DATE PAGES PREPARED/
NUMBER REVISION I AFFECTED REVISED BY:
11 Revised to rev 23 of 0-SO-250-2 which utilizes Y 08/07/0 ALL WR Ramsey the Spare inverter 0-11 as operable replacement 1 for 1-11 or 2-11 Inverters pen/ink 0-SO-250-2 Rev 24 update only N 8/21/01 4 WR Ramsey 12 Revised based on changes to 0-SO-250-2 Y 9/4/02 All J P Kearney V - Specify if the JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM # 42 Page 3 of 12 Rev 12 SEQUOYAH NUCLEAR PLANT AUOIUO/SRO JOB PERFORMANCE MEASURE Task:
Placing Vital Inverter 1-lI Back in Service Following Maintenance JAiTA task #: 0620030104 (AUO)
K/A Ratings:
062000 A2.03 (2.9/3.4) 000057 EA2.17 (3.1/3.4) 062000 A2.10 (3.0/3.3) 000057 G6 (3.5/3.8) 062000 G9 (3.2/3.3) 000057 EA1.01 (3.7/3.7) 194001 A1.02 (4.1/3.9)
Task Standard:
120V ac Vital Instrument Board "1-11" powered from 120V ac Vital Inverter "1-11".
Evaluation Method : Simulator In-Plant X Performer:
NAME Start Time Performance Rating: SAT __ UNSAT__ Performance Time Finish Time Evaluator: /
SIGNATURE DATE COMMENTS
JPM # 42 Page 4 of 12 Rev 12 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Sequenced steps identified by an "s"
- 2. Any UNSAT requires comments
- 3. SM approval will be required to enter the "Trip Hazard Zone" in the Vital Battery Rm and Vital Inverter area.
- 4. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. Local 55 minutes Tools/Equipment/Procedures Needed:
0-SO-250-2, Section 8.10
References:
I Reference Title Rev No.
- 1. 0-SO-250-2 120V AC Vital Instrument Power System 35 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Both units are operating at power (MODE 1) and maintenance on 120V ac Vital Inverter 1-11 has been completed.
Inverter "1-11" is currently shutdown and out of service with its respective 120V AC Vital Instrument Power Board "1-11" supplied from its alternate supply, Inverter 0-11, in accordance with 0-SO-250-2.
INITIATING CUES:
- 1. Maintenance has cleaned and inspected the 120V AC Vital Inverter "1-11"
- 2. The Unit 1 SRO has directed you, the Control Room AUO to return the 120V AC Vital Inverter "1-41" to service and align it to 120V AC Vital Instrument Board 1-11 per 0-SO-250-2 section 8.10.
- 3. Inform the Unit 1 SRO when 120V AC Vital Instrument Board 1-11 has been realigned to its normal supply.
JPM # 42 Page 5 of 12 Rev 12 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 1.: Obtain copy of the appropriate procedure. __ SAT UNSAT STANDARD: Operator obtains a copy of SO-250-2 Section 8.10 Start Time NOTE: If operator asks, acknowledge that a Concurrent Verifier __ SAT would be present during performance of this S.O. (For JPM purposes have him continue as if a CV was present) __ UNSAT STEP 2.: VERIFY 120V AC Vital Instrument Board 1-11 is ENERGIZED by observing transfer switch 1-SW-250-NE-E in ALTERNATE position and normal board voltage on 1-EI-250-NE-E.
Cue: Board voltage is NORMAL and the transferswitch is in the ALTERNATE position. Voltage is 123VAC.
STANDARD: Operator identifies Vital Instrument Board 1-11 and verifies board voltage normal and the transfer switch in the ALTERNATE position.
STEP 3.: ENSURE 120V AC Vital Inverter 1-1l DC supply breaker __ SAT 1-BKRC-250-KF /326-E on 125V DC Vital Battery Board II is in ON position. ___ UNSAT Cue: Breaker 326 is in the ON ,UP, position.
STANDARD: Operator identifies breaker 326 on 125V Vital Batt Bd II and ensures it is in the ON, UP, position.
STEP 4.: ENSURE f0-BCTB-250-DM/9A-B1, 120V AC Vital Inverters 1-11 & __ SAT 2-11 CLOSED at 480 V SDBD 11B2-B compt. 9A.
UNSAT Cue: Breakeris in the closed position.
STANDARD: Operator verifies breaker is closed.
STEP 5.: IF 1-11Inverter is NOT already in service, THEN ENSURE all breakers SAT on 120V AC Vital Inverter 1-11 are OFF UNSAT NOTE Per initiating cues, the inverter is not in service.
Cue: As each breaker is addressedstate "The breakerswitch is in the OFF, down position.
STANDARD: Operator identifies each breaker on Vital Inverter 1-11 and ensures it is in the OFF, down, position.
JPM # 42 Page 6 of 12 Rev 12 Job Performance Checklist:
SAT/UNSAT STEP/STANDARD STEP/STANDARD I STEP 6.: ENSURE [1-BKRA-250-KS/11-EI, 120V AC Vital Inverter 1-11 SAT Disconnect Bkr ON at 480V AC Vital Disconnect Panel II, el. 749 Aux Bldg. UNSAT Cue: After operatorsimulatesplacing the disconnctbreakerin the ON, cue him the breakeris in the ON position Critical Step STANDARD: Operator places [1-BKRA-250-KS/11-El in the ON position.
PRESS AND HOLD precharge pushbutton [1-HS-250-QN/S4-E]. __ SAT STEP 7. S:
Verify PRE-CHARGE light is lit.
UNSAT Cue: The pre-chargelight is lit.
Critical Step STANDARD: Operator identifies 1-11 Vital Inverter and presses the PRECHARGE pushbutton and verifies pre-charge light is LIT.
PLACE BATTERY INPUT breaker [1-BKR-250-QN/B1-E] In ON __ SAT STEP 8. S:
position.
UNSAT NOTE: After the PB is released the capacitors begin to discharge.
Waiting more than 5 seconds after the PB is released could cause high charging currents that could blow the Inverter fuses making the Inverter Inop.
Cue: Breaker handle is in the ON, up, position.
STANDARD: Operator places the Battery input circuit breaker on Vital Inverter Critical Step cabinet 1-11 in the ON, up, position.
STEP 9. S: RELEASE precharge pushbutton [1-HS-250-QN/S4-E]. - SAT Cue: The pre-chargelight is lit. __ UNSAT STANDARD: Operator releases pre-charge button. Critical Step STEP 10.: PLACE [1-BKRA-250-QN/B301-E1, AC Input To Rectifier Bkr in __ SAT ON position.
UNSAT Cue: Breaker handle is in the ON position.
Critical Step STANDARD: Operator places the breaker in the ON position.
JPM #42 Page 7 of 12 Rev 12 Job Performance Checklist:
STEPISTANDARD SATMUNSAT STEP 11.: ENSURE [1-HS-250-QN/S5-E] Remote sync switch on 1-11 SAT Inverter in OFF position.
UNSAT Cue: Remote sync switch on 1-11 Inverter is in OFFposition.
STANDARD: Operator verifies the Remote sync switch on 1-11 Inverter in OFF position..
STEP 12.: ENSURE [1-BKRA-250-QN/B701-E1, AC Input To Isolimiter Bkr __ SAT in ON position.
UNSAT Cue: After operatorsimulates placing[1-BKRA-250-QN/B701-El, AC Input To IsolimiterBkr in the ON position, cue him/her that it is ON.
STANDARD: Operator places the [1-BKRA-250-QN/B701-E], AC Input To Critical Step Isolimiter Bkr in ON position STEP 13.: ENSURE [1-BKRA-250-QN/B4-EI, Bypass Source AC Input Bkr __ SAT in ON position.
UNSAT Cue: After operatorsimulates[1-BKRA-250-QN/B4-E0, Bypass Source AC Input Bkr in the ON position, cue him/her that it is ON.
STANDARD: Operator [1-BKRA-250-QN/B4-E], Bypass Source AC Input Bkr Critical Step in the ON position.
STEP 14.: PLACE [1-BKRA-250-QN/B2-Ei, Inverter Output Bkrin ON SAT position.
UNSAT Cue: After operatorsimulates [1-BKRA-250-QN/B2-Ei, Inverter Output Bkr in ON position.the ON position, cue him/herthat it is ON.
STANDARD: Operator places [1-BKRA-250-QN/B2-E1, Inverter Output Bkr in Critical Step the ON position.
JPM # 42 Page 8 of 12 Rev 12 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 15.: ENSURE [1-HS-250-QN/S1-El Manual Bypass Sw is in the __ SAT INVERTER TO LOAD position.
UNSAT Cue: After operatorsimulates [1-HS-250-QN/S1-EY Manual Bypass Sw in the INVERTER TO LOAD position, cue him/her that it is in the LOAD position.
STANDARD: Operator places [1-HS-250-QN/S1-El Manual Bypass Sw in the Critical Step INVERTER TO LOAD position.
STEP 16.: PRESS Hl-HS-250-QN/S201 -E1, Inverter To Load Pushbutton AND __ SAT VERIFY "Inverter Supplying Load" light ON and "Bypass Source UNSAT Supplying Load" light OFF.
Cue: "Inverter Supplying Load"light ON and "Bypass Source Supplying Load" light OFF STANDARD: Operator presses ri -HS-250-QN/S201-E1, Inverter To Load Critical Step Pushbutton and verifies "Inverter Supplying Load" light ON and "Bypass Source Supplying Load" light OFF STEP 17.: PERFORM the following on Annunciator Pnl 1: __ SAT
- 1. PLACE i1-HS-250-QN/S2-El, AN1 Annunciator Disable Sw in ON. UNSAT
- 2. PRESS button A (Acknowledge)
- 3. PRESS button R (Reset).
Cue: After operatorsimulatesplaces [1-HS-250-QN/S2-E1, ANI Annunciator Disable Sw in ON, cue him/her that it is in the ON position.
STANDARD: Operator places [1-HS-250-QN/S2-E1, ANI Annunciator Disable Sw ON; presses button A (Acknowledge); and presses button R (Reset).;
STEP 18.: PERFORM the following on Annunciator Pnl 2: SAT
- 1. PLACE [1-HS-250-QN/S3-El, AN2 Annunciator Disable Sw in ON. UNSAT
- 2. PRESS button A (Acknowledge).
- 3. PRESS button R (Reset).
Cue: After operatorsimulates places [1-HS-250-QN/S3-EI, AN2 AnnunciatorDisable Sw in ON, cue him/her that it is in the ON position.
STANDARD: Operator places [1-HS-250-QN/S3-E1, AN2 Annunciator Disable Sw ON; presses button A (Acknowledge); and presses button R (Reset).
JPM # 42 Page 9 of 12 Rev 12 Job Performance Checklist:
STEP/STANDARD SATIUNSAT STEP 19.: ENSURE alarms clear in the MCR (1-XA-55-1C, windows B-6 and B-7) SAT Cue: As the CRO, acknowledge that the alarms are clear. UNSAT STANDARD: Operator calls the MCR to determine the alarms are clear.
STEP 20.: IF [INVERTER OUTPUT1 voltage is < 120.6 volts or> 126.5 volts OR __ SAT frequency is < 59.4 Hz or > 60.6 Hz, THEN NOTIFY Electrical Maintenance for support. __ UNSAT Cue: A C OUTPUT voltage is 121 volts and frequency is 60 Hz.
STANDARD: Operator checks AC OUTPUT voltage and frequency to ensure within required limits.
STEP 21.: PLACE I1-HS-250-QN/S6-E1, Remote Sync switch on 1-11 Vital __ SAT Inverter to SYNC OUT position.
UNSAT Cue: After operatorsimulates placing [1-HS-250-QN/S5-E1, Remote Sync switch on 1-11 Vital Inverterto SYNC OUT position, cue him/her that it is in the SYNC OUT position.
STANDARD: Operator places [1-HS-250-QN/S5-E1, Remote Sync switch on 1-11 Vital Inverter to the SYNC OUT position. Critical Step STEP 22.: ENSURE [0-HS-250-QW/SW4-E1 Remote Sync Input Switch, in UNIT 1 __ SAT Position. UNSAT Cue: After operatorsimulates placing [O-HS-250-QW/SW4-E, Remote Sync Input Switch, in the UNIT 1 Position,cue him/herthat it is in the Unit I position. Critical Step STANDARD: Operator places [0-HS-250-QW/SW4-E1 Remote Sync Input Switch, in the UNIT 1 Position STEP 23.: ENSURE [0-HS-250-QW/SW5-E1, Remote Sync Light Switch, in SAT UNIT 1 position.
UNSAT Cue: After operatorsimulates placing [O-HS-250-QW/SWS-El Remote Sync Input Switch, in the UNIT I Position,cue him/her that it is in the Unit I position. Critical Step
' STANDARD: Operator places [0-HS-250-QW/SW5-E1 Remote Sync Input Switch, in the UNIT 1 Position
JPM # 42 Page 10 of 12 Rev 12 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 24.: VERIFY In Sync light LIT on 1-11 Inverter.. __ SAT UNSAT Cue: In Sync light LIT STANDARD: Operator verifies In Sync light LIT.
STEP 25.: VERIFY 120V AC Vital Instrument Power Board 1-11 amber [NOR __ SAT SUPPLY AVAILl light LIT. UNSAT Cue: 120VAC Vital Instrument Power Board 1-11 amber [NOR SUPPLY AVAIL? light LIT.
STANDARD: Operator verifies 120V AC Vital Instrument Power Board 1-11 amber
[NOR SUPPLY AVAIL] light LIT.
STEP 26.: VERIFY 120V AC Vital Instrument Power Board 1-11 blue sync __ SAT light LIT to show Inverter 0-Il is in synchronism.
UNSAT Cue: 120VAC Vital InstrumentPower Board 1-Il blue sync light LIT.
STANDARD: Operator verifies 120V AC Vital Instrument Power Board 1-11 blue sync light LIT.
STEP 27.: OPERATE 120V AC Vital Instrument Board 1-11 Transfer switch __ SAT 1-SW-250-NE-E to NORMAL position.
UNSAT NOTE: Switch must travel 150-1800 for breaker to close (This is past the NORMAL position indication).
Cue: Transferswitch is aligned to the NORMAL (Verticao position. Critical Step STANDARD: Operator identifies the transfer switch on the 1-11 Vital Instrument Power Distribution Board and rotates the switch swiftly to the normal position.
JPM # 42 Page 11 of 12 Rev 12 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 28.: VERIFY 120V AC Vital Instrument Board 1-11 voltage remains __ SAT stable on the voltmeter 1-EI-250-NE-E.
UNSAT Cue: Board voltage is stable.
STANDARD: Operator checks board voltmeter to verify voltage is stable.
STEP 29.: PLACE [1-HS-250-QN/SS-E], Remote Sync Switch on 1-11 __ SAT Inverterto OFF position UNSAT Cue: After operatorsimulatesplacing [1-HS-250-QN/S5-Ei, Remote Sync Switch on 1-41 Inverterto the OFFposition, cue him/her that it is in the OFFposition.
STANDARD: Operator places r1-HS-250-QN/S5-E1, Remote Sync Switch on 1-11 Inverter to OFF position.
STEP 30.: ENSURE r0-HS-250-QW/SW4-E1 Remote Sync Input Switch, in OFF __ SAT Position. UNSAT Cue: After operatorsimulatesplacing [O-HS-250-QW/SW4-Ei Remote Sync Input Switch to the OFFposition, cue him/her that it is in the OFFposition.
STANDARD: Operator places [rO-HS-250-QW/SW4-E1 Remote Sync Input Switch to OFF position.
STEP 31.: ENSURE [0-HS-250-QW/SW5-E1, Remote Sync Light Switch, in OFF __ SAT position. IUNSAT Cue: After operatorsimulates placing[O-HS-250-QW/SWS-Ei Remote Sync Light Switch to the OFFposition, cue him/her that it is in the OFFposition.
STANDARD: Operator places [rO-HS-250-QW/SWS-E1 Remote Sync Light Switch to OFF position.
JPM # 42 Page 12 of 12 Rev 12 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 32.: ENSURE ro-HS-250-QW/SW3-El Remote Alarm Switch in OFF. __ SAT Cue: After operatorsimulates placing[O-HS-250-QW/SW3-EI Remote __ UNSAT Alarm Switch to the OFFposition, cue him/her that it is in the OFFposition.
STANDARD: Operator places ((0-HS-250-QW/SW4-E1 Remote Alarm Switch to OFF position.
STEP 33.: ENSURE alarms clear in the MCR (1-XA-55-1 C, window B-6 and B-7). __ SAT Cue: As the CRO, acknowledge the alarms are clear. __ UNSAT STANDARD: Operator contacts the main control room to determine alarm light status.
STEP 34.: Inform the Unit 1 SRO that the 1-11 Vital Inverter is back in SAT service and that the 1-11 Vital Power Board is back on the NORMAL supply from the 1-11 Inverter. UNSAT Cue: If asked, Vital Inverter 0-11 will be removed from service by the on-coming shift.
Stop Time__
STANDARD: Operator informs the Unit 1 SRO that the 1-11 Vital Inverter is back in service and that the 1-11 Vital Power Board is back on the NORMAL supply from the 1-11 Inverter. (Only lacks IV)
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION O-SO-250-2 120 VOLT AC VITAL INSTRUMENT POWER SYSTEM Revision 35 QUALITY RELATED PREPARED/PROOFREAD BY: CHERYL D. MORRIS RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J.A. DVORAK EFFECTIVE DATE: 30Apr 02 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION: Revised to incorporate stage 42 of DCN D20071A, which removed steps to contact MEG to verify voltage differential between line-side normal and alternate feeders is less than 20 volts prior to synchronizing normal and alternate feeders to 2-1 and 2-111120v AC Vital Instrument Power Boards.
These are intent changes.
SQN 120 VOLT AC VITAL INSTRUMENT 0-s0-250-2 POWER SYSTEM Rev: 35 0 Page 2 of 158 TABLE OF CONTENTS Page 1 of 4 Section Title Page TABLE O F CO NTENTS ................................................................................... 2 1.0 INTRODUCTIO N ............................................................................................. 6 1.1 Purpose ...................................................................................................... 6 1.2 Scope ......................................................................................................... 6
2.0 REFERENCES
................................................................................................ 6 2.1 Perform ance References ........................................................................... 6 2.2 Developm ental References ........................................................................ 6 3.0 PRECA UTIO NS A ND LIM ITATIO NS .............................................................. 7 4.0 PREREQ UISITE ACTIO NS ............................................................................. 9 5.0 STA RTUP/STA NDBY READINESS ................................................................ 10 5.1 Energizing 120 Volt AC Vital Instrument Power Board 1-1 .................................... 10 5.2 Energizing 120 Volt AC Vital Instrument Power Board 1-11 ................................... 14 5.3 Energizing 120 Volt AC Vital Instrument Power Board 1-111 .................................. 18 5.4 Energizing 120 Volt AC Vital Instrument Power Board 1-IV ................................. 22 5.5 Energizing 120 Volt AC Vital Instrument Power Board 2-1 ................................... 26 5.6 Energizing 120 Volt AC Vital Instrument Power Board 2-11 .................................. 30 5.7 Energizing 120 Volt AC Vital Instrument Power Board 2-111 .................................. 34 5.8 Energizing 120 Volt AC Vital Instrument Power Board 2-IV ................................. 38 5.9 Startup of Vital Inverter 1-1 and Isolimiter Transfer ............................................... 42 5.10 Startup of Vital Inverter 1-11 and Isolimiter Transfer .............................................. 44 5.11 Startup of Vital Inverter 1-111 and Isolimiter Transfer ............................................. 46 5.12 Startup of Vital Inverter 1-IV and Isolimiter Transfer ............................................. 47 5.13 Startup of Vital Inverter 2-1 and Isolimiter Transfer ............................................... 50 5.14 Startup of Vital Inverter 2-11 and Isolimiter Transfer .............................................. 52 5.15 Startup of Vital Inverter 2-111 and Isolimiter Transfer ............................................. 54 5.16 Startup of Vital Inverter 2-IV and Isolimiter Transfer ............................................. 56
SQN 120 VOLT AC VITAL INSTRUMENT 0-SO-250-2 POWER SYSTEM Rev: 35 0 Page 3 of 158 TABLE OF CONTENTS Page 2 of 4 Section Title Page 6.0 NORMAL OPERATION .................................................................................. 58 7.0 SHUTDOW N.................................................................................................... 59 8.0 INFREQUENT OPERATION ......................................................................... 60 8.1 Removing Inverter 1-1 From Service and Placing Vital AC Instrument Power Board 1-1 on Alternate Supply .................................. 60 8.2 Removing Inverter 1-11 From Service and Placing Vital AC Instrument Power Board 1-11 on Alternate Supply ................................ 63 8.3 Removing Inverter 1-111 From Service and Placing Vital AC Instrument Power Board 1-111 on Alternate Supply .............................. 66 8.4 Removing Inverter 1-IV From Service and Placing Vital AC Instrument Power Board 1-IV on Alternate Supply ............................. 69 8.5 Removing Inverter 2-1 From Service and Placing Vital AC Instrument Power Board 2-1 on Alternate Supply ................................ 72 8.6 Removing Inverter 2-11 From Service and Placing Vital AC Instrument Power Board 2-11 on Alternate Supply ................................ 75 8.7 Removing Inverter 2-111 From Service and Placing Vital AC Instrument Power Board 2-111 on Alternate Supply ............................... 78 8.8 Removing Inverter 2-IV From Service and Placing Vital AC Instrument Power Board 2-IV on Alternate Supply ............................. 81 8.9 Returning Inverter 1-1 to Service and Returning Vital AC Instrument Power Board 1-1 to Normal Supply ..................................... 84 8.10 Returning Inverter 1-11 to Service and Returning Vital AC Instrument Power Board 1-11 to Normal Supply .................................... 89 8.11 Returning Inverter 1-111 to Service and Returning Vital AC Instrument Power Board 1-111 to Normal Supply .................................. 95 8.12 Returning Inverter 1-IV to Service and Returning Vital AC Instrument Power Board I-IV to Normal Supply .................................... 100 8.13 Returning Inverter 2-1 to Service and Returning Vital AC Instrument Power Board 2-1 to Normal Supply ....................................... 105 8.14 Returning Inverter 2-11 to Service and Returning Vital AC Instrument Power Board 2-11 to Normal Supply ...................................... 110 8.15 Returning Inverter 2-111 to Service and Returning Vital AC Instrument Power Board 2-111 to Normal Supply ..................................... 115
SQN 120 VOLT AC VITAL INSTRUMENT O-SO-250-2 POWER SYSTEM Rev: 35 0 Page 4 of 158
/
TABLE OF CONTENTS Page 3 of 4 Section Title Page 8.16 Returning Inverter 2-IV to Service and Returning Vital AC Instrument Power Board 2-IV to Normal Supply ..................................... 120 8.17 Transfer of Inverter Normal Power Supply To Bypass Power Supply (Manual or Auto) for 1-1 Vital Inverter ................................................................... 125 8.18 Transfer From Bypass Power Supply to Inverter Normal Power Supply (Manual or Auto) for 1-1 Vital Inverter .................................................................. 126 8.19 Transfer of Inverter Normal Power Supply To Bypass Power Supply (Manual or Auto) for 1-11 Vital Inverter .................................................................. 127 8.20 Bypass Transfer From Power Supply to Inverter Normal Power Supply (Manual orAuto) for 1-11 Vital Inverter ................................................................. 128 8.21 Transfer of Inverter Normal Power Supply To Bypass Power Supply (Manual or Auto) for 1-111 Vital Inverter .................................................................. 129 8.22 Transfer From Bypass Power Supply to Inverter Normal Power Supply (Manual orA uto) for 1-111 Vital Inverter ................................................................. 130 8.23 Transfer of Inverter Normal Power Supply To Bypass Power Supply (Manual or Auto) for 1-IV Vital Inverter ................................................................. 131 8.24 Transfer From Bypass Power Supply to Inverter Normal Power Supply (Manual or Auto) for 1-IV Vital Inverter ................................................................ 132 8.25 Transfer of Inverter Normal Power Supply To Bypass Power Supply (Manual or Auto) for 2-1 Vital Inverter ................................................................... 133 8.26 Transfer From Bypass Power Supply to Inverter Normal Power Supply (Manual or Auto) for 2-1 Vital Inverter .................................................................. 134 8.27 Transfer of Inverter Normal Power Supply To Bypass Power Supply (Manual or Auto) for 2-11 Vital Inverter ...................................... 135 8.28 Bypass Transfer From Power Supply to Inverter Normal Power Supply (Manual or Auto) for 2-11 Vital Inverter ................................................................. 136 8.29 Transfer of Inverter Normal Power Supply To Bypass Power Supply (Manual or Auto) for 2-111 Vital Inverter .................................................................. 137 8.30 Transfer From Bypass Power Supply to Inverter Normal Power Supply (Manual or Auto) for 2-111 Vital Inverter ................................................................. 138 8.31 Transfer of Inverter Normal Power Supply To Bypass Power Supply (Manual or Auto) for 2-IV Vital Inverter ................................................................. 139 8.32 Transfer From Bypass Power Supply to Inverter Normal Power Supply (Manual or Auto) for 2-IV Vital Inverter ................................................................ 140
'*8.33 Energizing Spare120V AC Vital Inverter 0-1 ................................................... 141
SQN 0
120 VOLT AC VITAL INSTRUMENT POWER SYSTEM TABLE OF CONTENTS o-sO-250-2 Rev: 35 Page 5 of 158 H
Page 4 of 4 Section Title Page 8.34 Energizing Spare 120V AC Vital Inverter 0-11 ................................................. 144 8.35 Energizing Spare 120V AC Vital Inverter 0-111 ................................................ 147 8.36 Energizing Spare 120V AC Vital Inverter 0-IV ................................................ 150 8.37 Removing Spare 120V AC Vital Inverter 0-1 From Service ................................ 153 8.38 Removing Spare 120 V AC Vital Inverter 0-11 From Service .............................. 154 8.39 Removing Spare 120V AC Vital Inverter 0-111 From Service .............................. 155 8.40 Removing Spare 120V AC Vital Inverter O-IV From Service .............................. 156 9.0 RECORDS ................................................................................................................. 157 SOURCE NOTES ....................................................................................................... 158 ATTACHMENTS ATTACHMENT 1: POWER CHECKLIST 0-250-2.01 ATTACHMENT 2: POWER CHECKLIST 0-250-2.02 ATTACHMENT 3: POWER CHECKLIST 0-250-2.03 ATTACHMENT 4: POWER CHECKLIST 0-250-2.04 ATTACHMENT 5: POWER CHECKLIST 0-250-2.05 ATTACHMENT 6: POWER CHECKLIST 0-250-2.06 ATTACHMENT 7: POWER CHECKLIST 0-250-2.07 ATTACHMENT 8: POWER CHECKLIST 0-250-2.08 ATTACHMENT 9: POWER CHECKLIST 0-250-2.09 ATTACHMENT 10: POWER CHECKLIST 0-250-2.10 ATTACHMENT 11: POWER CHECKLIST 0-250-2.11 ATTACHMENT 12: POWER CHECKLIST 0-250-2.12 ATTACHMENT 13: POWER CHECKLIST 0-250-2.13 ATTACHMENT 14: POWER CHECKLIST 0-250-2.14 ATTACHMENT 15: POWER CHECKLIST 0-250-2.15 ATTACHMENT 16: POWER CHECKLIST 0-250-2.16 ATTACHMENT 17: POWER CHECKLIST 0-250-2.17 ATTACHMENT 18: POWER CHECKLIST 0-250-2.18 ATTACHMENT 19 POWER CHECKLIST 0-250-2.19 ATTACHMENT 20 POWER CHECKLIST 0-250-2.20 ATTACHMENT 21 POWER CHECKLIST 0-250-2.21
SON 120 VOLT AC VITAL INSTRUMENT O-SO-250-2 POWER SYSTEM Rev: 35 0 Page 6 of 158
1.0 INTRODUCTION
1.1 Purpose This Instruction provides the steps necessary for normal operation of the 120 Volt AC Vital Instrument Power System.
1.2 Scope This Instruction provides the precautions and actions necessary for energizing the vital instrument power boards from their inverters, transferring vital instrument power boards to and from alternate supply and shutdown and startup of the vital inverters.
2.0 REFERENCES
2.1 Performance References A. Instructions
- 1. 0-SO-250-1, 125VDC Vital Power System.
2.2 Developmental References A. TVA Drawings
- 1. 45N700-1
- 2. 45N700-2
- 3. 45N706-1 through 6
- 4. 45N708-1 and 2
- 5. 45N709-2, 3, and 4 B. Technical Specification (TS) Requirements
- 1. 3.8.2.1
- 2. 3.8.2.2
- 3. 3.8.2.3
- 4. 3.8.2.4
SQN 120 VOLT AC VITAL INSTRUMENT 0-SO-250-2 POWER SYSTEM Rev: 35 0 Page 7 of 158
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2.2 Developmental References (Continued)
C. FSAR Sections
- 1. 8.1
- 2. 8.2
- 3. 8.3 D. Surveillance Instructions
- 1. 1-SI-OPS-000-003.W, Weekly Shift Log.
- 2. 2-SI-OPS-000-003.W, Weekly Shift Log.
- 3. O-PI-OPS-000-037.0, Control Room AUO Duty Station Shift Relief and Round Sheets.
3.0 PRECAUTIONS AND LIMITATIONS A. Failure to observe all posted radiation control requirements may result in unnecessary radiation absorbed dose.
B. The sync signal must be on prior to transferring the vital Instrument Power Board feed, via the transfer switch, to ensure the two supply voltages are in synchronism.
C. In an abnormal situation when the vital Instrument Power Board is deenergized because of a loss of power the sync signal does not have to be on to reenergize the board from the alternate supply.
D. Prior to placing an inverter in service the logic circuit must be allowed to warm for greater than one minute.
E. Prior to removing from service or returning to service Vital Inverter 1-IV or 2-IV the Control Rod Drive System for the affected unit shall be placed in manual rod control. This is to prevent inadvertent rod motion during the Vital Inverter/Board transfer operation. Note that rod control system alarms may occur during the transfer operation. (REF. SQ993258PER)
F. Breakers and switches located on the Vital Inverters must be verified latched when they are closed. The latching should be verified by listening and feeling for the clicking of the latch locking into place and by verifying that the breaker or switch is in the full "ON" position. [Ref- PER 00-004710-000]
SQN 120 VOLT AC VITAL INSTRUMENT 0-SO-250-2 POWER SYSTEM Rev: 35 0 Page 8 of 158
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3.0 PRECAUTIONS AND LIMITATIONS (cont.)
G. The static switch on the vital inverters will automatically transfer from the inverter to the isolimiter if a failure occurs. The Auto Retransfer feature of the Vital Inverters Static Switch will automatically return to the "inverter to load" position following a 10 second time delay if inverter output voltage returns to normal.
H. Spare Inverters cannot be used to supply Unit 1 Vital Instrument Power Boards and Unit 2 Vital Instrument power boards simultaneously.
SQN 120 VOLT AC VITAL INSTRUMENT O-SO-250-2 POWER SYSTEM Rev: 35 a Page 9of 158 Date 4.0 PREREQUISITE ACTIONS NOTE Throughout this Instruction where an IF/THEN statement exists, the step should be N/A'd if the stated condition does not exist.
[1] ENSURE Instruction to be used is a copy of the effective version.
[2] ENSURE Precautions and Limitations Section 3.0, has been reviewed.
[3] ENSURE all protective grounds are removed before energizing boards or inverters which have been held under a clearance.
[4] ENSURE exact replacement or acceptable substitute is used when replacing fuses, in accordance with OPDP-7.
[5] ENSURE inverter areas are reasonably clean and free of obstructions for adequate ventilation of the inverter.
[6] INDICATE below which performance section of this Instruction will be used.
El 5.0 STARTUP/STANDBY READINESS E] 6.0 NORMAL OPERATION E1 7.0 SHUTDOWN LI 8.0 INFREQUENT OPERATION REASON:
SQN 120 VOLT AC VITAL INSTRUMENT 0-SO-250-2 POWER SYSTEM Rev: 35 0 Page 10of 158 Date 5.0 STARTUP/STANDBY READINESS 5.1 Energizing 120 Volt AC Vital Instrument Power Board 1-1
[1] ENSURE Power Checklist 0-250-2.01 has been performed.
NOTE Steps [2] through [6] are performed in 125V DC Vital Battery Board Room I, el 734', AB.
[2] ENSURE all the load breakers on 120V AC Vital Instrument Power Board 1-1 are in OFF position.
[3] ENSURE 120V AC Vital Instrument Power Board 1-1 disconnect switch [1-DS-250-NC-D1 is in OFF position.
[4] ENSURE 120v Ac Vital Instrument Power Board 1 -I transfer switch rl-SW-250-NC-D1 is in NORMAL Position.
[5] VERIFY 125V DC Vital Battery Board I is in service by observing board voltage of - 135 volts on its bus voltmeter ro-EI-250-KE3-DI.
[6] ENSURE 120V AC Vital Inverter 1-I DC supply breaker rl-BKRC-250-KE/326-DI on 125V DC Vital Battery Board I is in ON position.
[7] ENSURE ro-BCTB-250-DJ/9A-A1, 120V AC Vital Inverters 1-1 &2-1 CLOSED at 480V SDBD 1A1-A compt. 9A.
NOTE Steps [8] through [22] are performed at or near 120V AC Vital Inverter 1-1 on el 749', AB, West Wall.
[8] ENSURE all breakers on 120V AC Vital Inverter 1-I are in OFF position.
Date 8.10 Returning Inverter 1-11 to Service and Returning Vital AC Instrument Board 1-11 to Normal Supply (Continued)
NOTE Precharge pushbutton should continue to be depressed until battery input breaker is closed.
[6] IF the 1-II Inverter is NOT in service, THEN
[a] PERFORM the following to connect the battery to the inverter:
- 1. PRESS AND HOLD r1-HS-250-QN/S4-E1, Precharge Pushbutton
- 2. VERIFY rPRE-CHARGE1 light is LIT.
- 3. PLACE rl-BKRC-250-QN/B1-E1, Battery Input Bkr in ON position.
- 4. RELEASE r1-HS-250-QN/S4-E, Precharge Pushbutton 1st cv
[b] PLACE rl-BKRA-250-QN/B301-E], AC Input To Rectifier Bkr in ON position.
1st cv
[c] ENSURE rl-HS-250-QNIS5-E1 Remote sync switch on 1-11 Inverter in OFF position.
1st CV
[d] ENSURE rl-BKRA-250-QN/B701-E1, AC Input To Isolimiter Bkr in ON position.
1st cv
[e] ENSURE r"-BKRA-250-QNIB4-E] Bypass Source AC Input Bkr in ON position.
1st cv If] PLACE rl-BKRA-250-QNIB2-E1, Inverter Output Bkr in ON position.
1st CV
[g] ENSURE r1-HS-250-QN/S1-E1 Manual Bypass Sw is in the INVERTER TO LOAD position.
1st cv
SQN 120 VOLT AC VITAL INSTRUMENT 0-SO0-250-2 POWER SYSTEM Rev: 35 0 Page 91 of 158 Date 8.10 Returning Inverter 1-11 to Service and Returning Vital AC Instrument Board 1-11 to Normal Supply (Continued)
[h] PRESS rl-HS-250-QN/S201-E1, Inverter To Load Pushbutton AND VERIFY "Inverter Supplying Load" light ON and "Bypass Source Supplying Load" light OFF.
[i] PERFORM the following on Annunciator Pnl 1:
- 1. PLACE rl-HS-250-QN/S2-E1, AN1 Annunciator Disable Sw in ON.
- 2. PRESS button A (Acknowledge)
- 3. PRESS button R (Reset).
[j] PERFORM the following on Annunciator Pnl 2:
- 1. PLACE rl-HS-250-QN/S3-E1, AN2 Annunciator Disable Sw in ON.
- 2. PRESS button A (Acknowledge).
- 3. PRESS button R (Reset).
[k] ENSURE alarms clear in the MCR (1-XA-55-IC, windows B-6 and B-7)
[7] IF rINVERTER OUTPUT] voltage is < 120.6 volts or > 126.5 volts OR frequency is < 59.4 Hz or > 60.6 Hz, THEN NOTIFY Electrical Maintenance for support.
[8] PLACE r1-HS-250-QN/S5-E1, Remote Sync switch on 1-11 Vital Inverter to SYNC OUT position.
1st cv NOTE Steps [9] and [10] are performed at the 0-11 Vital Inverter.
[9] ENSURE [0-HS-250-QW/SW4-E1 Remote Sync Input Switch, in UNIT 1 Position.
[10] ENSURE r0-HS-250-QW/SW5-E, Remote Sync Light Switch, in UNIT 1 position.
[11] VERIFY In Sync light LIT on 1-11 Inverter.
I SQN 120 VOLT AC VITAL INSTRUMENT 0-S0-250-2 POWER SYSTEM Rev: 35 A
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Page 92 of 158 I
I Date 8.10 Returning Inverter 1-11 to Service and Returning Vital AC Instrument Board 1-11 to Normal Supply (Continued)
[12] VERIFY 120V AC Vital Instrument Power Board 1-1l amber
[NOR SUPPLY AVAILl light LIT. /
1st cv
[13] VERIFY 120VAC Vital Instrument Power Board 1-11 blue sync light LIT to show Inverter 0-11 is in synchronism. /
1st CV CAUTION Approximately 1500 - 1800 of rotation is required to operate the transfer switch; it will "snap" once its spring is charged.
NOTE The transfer switch on 120V AC Vital Instrument Power Board 1-11 is a make before break switch. If both sources (NOR-ALT) are energized and in synchronism a bumpless transfer should occur.
[14] OPERATE transfer switch rl-SW-250-NE-E1 to NORMAL position.
1st CV
[15] VERIFY 120VAC Vital Instrument Power Board 1-11 voltage remains stable on voltmeter rl-EI-250-NE-E1.
[16] PLACE rl-HS-250-QN/S5-E1, Remote Sync Switch on 1-11 Inverter to OFF position.
1st CV
SON 120 VOLT AC VITAL INSTRUMENT O-SO-250-2 POWER SYSTEM Rev: 35 0 Page 93 of 158 Date 8.10 Returning Inverter 1-11 to Service and Returning Vital AC Instrument Board 1-11 to Normal Supply (Continued)
NOTE Steps [17] through [19] are performed at the 0-111 Vital Inverter.
[17] ENSURE ro-HS-250-QW/SW4-E1 Remote Sync Input Switch, in OFF Position.
[18] ENSURE F0-HS-250-QW/SW5-E, Remote Sync Light Switch, in OFF position.
[19] ENSURE rO-HS-250-QW/SW3-E1 Remote Alarm Switch in OFF.
[20] ENSURE alarms clear in the MCR (1-XA-55-1C, window B-6 and B-7).
S QN 120 VOLT AC VITAL INSTRUMENT 0-SO-250-2 POWER SYSTEM Rev: 35 0 Page 94 of 158 Date 8.10 Returning Inverter 1-11 to Service and Returning Vital AC Instrument Board 1-11 to Normal Supply (Continued)
[21] INDEPENDENTLY VERIFY the following breakers:
BKR ID/DESCRIPTION POSITION IV 120V AC Vital Inverter 1-11 Supply Bkr. iO-BCTB-250-DM/9A-B1 CLOSED (480V SDBD 1B2-B, Cmpt. 9A) 120V AC Vital Inverter 1-11 480V Disconnect Bkr ON
[1-BKRA-250-KS/11-E] (el. 749 Aux Bldg)
[22] IF desired, THEN REMOVE 120v Vital Inverter 0-11 from service USING section 8.38 of this procedure.
END OF TEXT
JPM 201 RAPI Page 1 of 6 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM 201 RAP1 LOCAL ISOLATION OF CHARGING with LOCAL CONTROL OF SEAL INJECTION FLOW Original Signatures on File PREPARED/
REVISED BY: Date/
- Date/
VALIDATED BY:
APPROVED BY: Date/
(Operations Training Manager)
- Date/
CONCURRED:
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
"* Operations Concurrence required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM 201 RAP1 Page 2 of 6 Rev. 0 NUCLEAR TRAINING REVISION/USAGE LOG DESCRIPTION OF V DATE PAGES PREPARED/
REVISION NUMBER REVISION {AFFECTED REVISED BY:
0 New Y 8/31/2002 M11l * -rt:al i*Y I __I1 V - Specify ifthe JPM change will require another Validation (Y or N).
See cover sheet for criteria.
JPM 201RAP1 Page 3 of 6 Rev. 0 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE MEASURE Task: Local Isolation Of Charging With Local Control Of Seal Injection Flow JA/TA task #: 3010070401(RO) 3010070402(SRO)
K/A Ratings: 2.4.27 (3.0/3.5) 2.1.30 (3.9/3.4) 067AA2.16 (3.3/4.0) 067AK3.04 (3.3/4.1) 004A4.08 (3.8/3.4) 004A4.11 (3.4/3.3)
Task Standard: Locally isolate Charging With Local Control Of Seal Injection Flow Evaluation Method: Simulator In-Plant X
=======
Performer:
NAME Start Time Performance Rating: SAT UNSAT Performance Time Finish Time Evaluator:
SIGNATURE DATE COMMENTS
JPM 201 RAP1 Page 4 of 6 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Sequenced steps identified by an "s"
- 2. Any UNSAT requires comments
- 3. Task should begin in the SM office.
- 4. Supply the operator with a copy of AOP-N.08 (appropriate section), when he is given initial conditions and cues.
- 5. Insure operator performs the following required actions for SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. 12 mins Tools/EquipmentlProcedures Needed:
AOP-N.01, Appendix R Fire Safe Shutdown, Appendix B (Do not give operator until discussion of equipment in JPM step 1 is complete.
SCBAs, portable lanterns, radio (These items are simulated. The operator should be able to explain where they are located)
References:
SReference Title Rev No.
A. AOP-N.08 Appendix R Fire Safe Shutdown 1 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 2 has experienced an Appendix R Fire located in area 734-A24, 6.9 KV Shutdown Board Rm B.
- 2. The operating crew has entered AOP-N.08, section 2.44.
- 3. The AUOs are in the SM's office with SCBAs, portable lanterns, and radios prepared to be dispatched as directed by the MCR.
INITIATING CUES:
- 1. You are an AUO located in the SM office and been directed to locally isolate Unit 2 charging and throttle seal injection flow using Appendix B of AOP-N.08.
- 2. Inform the US/CRO when charging has been isolated.
- 3. This is a time critical JPM. Timing will start when the evaluator provides you with AOP N.08, Appendix B.
JPM 201RAP1 Page 5 of 6 Rev. 0 OBTAIN radio, SCBA, and portable lantern. SAT
.STEP 1.:
UNSAT NOTE Evaluator should complete the discussion of where the operator may obtain a radio, SCBA, and portable lantern before providing the Critical step operator AOP-N.08, Appendix B. The time critical step begins in the SM's office when the operator is given Appendix B.
Start Time_
Cue Ask operatorwhere these items may be obtained.
Time operator STANDARD: Operator should be able to explain where he can obtain these items. given App B SCBAs available for operator use are located in the MCR Chart cabinets.
STEP 2.: Proceed to AB el. 669 Pen Rm __ SAT Cue: If operatorattempts to open fire doorto the 6.9KV Shutdown __ UNSAT Board Room B, inform the operatorthe door is hot to the touch.
STANDARD: Operator proceeds to AB el. 669 Pen Rm. via a route other than through the 6.9KV Shutdown Board Room B. Critical Step STEP 3.: ISOLATE charging header by closing one of the following: __ SAT
- VLV-62-539, Reach rod in AB el. 669 Pen Rm __ UNSAT Cue: When the operatorattempts to close the first valve, inform him/her Time to isolate that it does not move. After operatorsimulates closing the charging second valve, inform him that the valve on its closed seat.
min.
STANDARD: Close either 2-VLV-62-537, Reach rod in AB el. 669 Pen Rm, OR 2-VLV-62-539, Reach rod in AB el. 669 Pen Rm. Critical step timing starts after discussion of where radio, SCBA, and portable lantern may Time Critical This step must be completed within 10 minutes of being be located. Step and AP is isolated.
given Appendix B. Operator notifies US/CRO that charging Critical Step
JPM 201 RAP1 page 6 of 6 Rev. 0 IF MCR directs throttling seal injection flow THEN THROTTLE one SAT STEP 4.:
of the following valves to control pressurizer level and seal UNSAT injection flow:
"* VLV-62-535, CCP B-B Room, or
"* VLV-62-536, CCP B-B Room NOTE A step ladder and valve cheater will be required for this step. An EOI ladder is outside 1B-B or 2B-B CCP Room.
Cue: As the CRO, direct the operatorto throttle 2-VLV-62-535-or 2-VLV 62-536 until the valve is approximately half closed.
STANDARD: Throttle 2-VLV-62-535-or 2-VLV-62-until the valve is approximately half Critical Step closed.
STEP 5.: NOTIFY US/CRO that Appendix B of AOP-N.08 is complete. __ SAT STANDARD: CRO notified. __ UNSAT Stop Time End of JPM
APPENDIX R FIRE SAFE SHUTDOWN AOP-N.08 SQN Rev I
Page 1 of 1 APPENDIX B LOCAL ISOLATION OF CHARGING WITH LOCAL CONTROL OF SEAL INJECTION FLOW CAUTION This is a TIME CRITICAL TASK. Step 3 must be completed within 10 minutes.
NOTE Ifthe accountability siren sounds, operator should continue performing this appendix. The SM should be aware of task assignments and personnel locations.
- 1. IDENTIFY applicable unit:
"* Unit I
"* Unit 2
- 2. OBTAIN radio and SCBA (if conditions warrant). El NOTE If fire is near Aux Bldg center stairs, operator should enter Aux Bldg via el. 690 Radcon portal.
- 3. ISOLATE charging header by closing one of the following:
VALVE LOCATION CLOSED 4 VLV-62-537 Reach rod in AB el. 669 Pen Rm El VLV-62-539 Reach rod in AB el. 669 Pen Rm El NOTE Step ladder and valve cheater will be required for following step.
EOI ladder outside 1B-B or 2B-B CCP Room should be used.
- 4. IF MCR directs throttling seal injection flow THEN THROTTLE one of the following valves to control pressurizer level and seal injection flow:
VALVE LOCATION THROTTLED4 VLV-62-535 CCP B-B Room El VLV-62-536 CCP B-B Room El Page 1128 of 1199