ML110060583
| ML110060583 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/04/2010 |
| From: | Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LR-N10-0355 S1.OP-IO.ZZ-0006(Q), Rev 33 | |
| Download: ML110060583 (48) | |
Text
PSEG Internal Use Only Page 1 of 1 PSEG NUCLEAR L.L.C.
SALEM/OPERATIONS S1.OP-IO.ZZ-0006(Q) REV. 33 HOT STANDBY TO COLD SHUTDOWN USE CATEGORY: I Biennial Review Performed: Yes ____ No ____ NA T DCP Packages and Affected Document Numbers incorporated into this revision: None The following OTSCs were incorporated into this revision: None REVISION
SUMMARY
The following changes are incorporated to provide additional clarification and
[70103122]
guidance regarding the RCS draining process to ensure expected level response is obtained, and is in response to SAP Order 70090887, Unintended Reduction in RCS Inventory.
Removed PZR level bands of 100 - 105% and 80 - 86% from the associated steps.
The information is to be obtained using information previously reviewed and approved in Exhibit 1 of this procedure and S2.OP-IO.ZZ-0006(Q):
C Changed Step 5.1.60 CAUTION (second bullet), to read The expected PZR COLD CAL level value in SPDS (U1LT0462S) in a water solid condition is <105%. An indicated level of $105% is highly suspect. Maintenance is to be notified to troubleshoot the apparent failure of the instrument whenever the indicated value is not as expected.
C Changed Step 5.1.60.B to read; ENSURE PZR COLD CAL Level in SPDS (U1LT0462S) is indicating <105% (Refer to EQACE 70090500).
C Added Step 5.1.60.C ENSURE PZR COLD CAL Level in SPDS (U1LT0462S) is indicating as expected. Refer to Exhibit 1, Pressurizer Level Channels, for channel behavior based on pressurizer water temperature.
C Changed NOTE at Step 5.1.60.H to read; Refer to Exhibit 1, Pressurizer Level Channels, for channel behavior based on pressurizer water temperature.
IMPLEMENTATION REQUIREMENTS Effective Date:
February 4, 2010 None
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 1 of 47 Rev. 33 HOT STANDBY TO COLD SHUTDOWN TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE................................................................ 2 2.0 PREREQUISITES.......................................................... 2 3.0 PRECAUTIONS AND LIMITATIONS......................................... 3 4.0 EQUIPMENT/MATERIAL REQUIRED........................................ 8 5.0 PROCEDURE............................................................. 9 5.1 Hot Standby to Cold Shutdown......................................... 9 5.2 Completion And Review............................................. 35 6.0 RECORDS............................................................... 36
7.0 REFERENCES
............................................................ 36 ATTACHMENTS RCS Makeup Source................................................ 39 Pressurizer Cold Calibrated Level Indication (LI-462)...................... 40 Completion Sign-Off Sheet........................................... 42 EXHIBITS Exhibit 1 Pressurizer Level Channels........................................... 44
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 2 of 47 Rev. 33 1.0 PURPOSE 1.1 To provide the instructions necessary to transition from Hot Standby (Mode 3) to Cold Shutdown (Mode 5).
2.0 PREREQUISITES
___ 2.1 IF the cooldown is required to comply with a TSAS, THEN SM/CRS REFER to ECG for the appropriate event classification and reporting requirements.
___ 2.2 NOTIFY Chemistry of impending plant cooldown and the need to sample the RCS IAW SC.CH-TI.ZZ-0544(Q), Reactor Startup, Shutdown, and
>15% Power Change Surveillance Requirement.
___ 2.3 IF cooldown to Mode 5 is anticipated, THEN, as directed by Chemistry, PLACE the CVCS Cation Bed OR standby CVCS Mixed Bed Demineralizer in service IAW S1.OP-SO.CVC-0012(Q),
CVCS Demineralizer - Normal Operation, to begin delithiating the RCS.
___ 2.4 ENSURE all Shutdown and Control Rods are fully inserted.
___ 2.5 ADJUST RCS and Pressurizer boron concentrations as required to maintain adequate Shutdown Margin during the cooldown.
The RCS and Pressurizer boron concentrations are to be maintained above the minimum Shutdown Margin requirement during the cooldown.
___ 2.6 IF additional BAST volume is required to support RCS boration during cooldown, THEN ALIGN Unit 2 BAST to Unit 1 BAST IAW S1.OP-SO.CVC-0005(Q),
Boric Acid Solution Preparation And Transfer.
___ 2.7 NOTIFY Maintenance of the following:
S1.IC-FT.RCP-0070(Q), 1PT403 RCS Hot Leg Pressure Channel II and S1.IC-FT.RCP-0071(Q), 1PT405 RCS Hot Leg Pressure Channel I, will be required prior to placing POPS in service IAW T/S 4.4.9.3.1 and prior to RCS cooldown to #312°F S1.IC-ST.RHR-0014(Q), RHR Interlock and Alarm Verification, will be required when RCS pressure is <375 psig and prior to placing RHR in service IAW T/S 4.5.2.i
___ 2.8 NOTIFY the Shift Operations Manager to provide direction for applicability of performing S1.OP-ST.SJ-0020(Q), Periodic Leakage Test - RCS Pressure Isolation Valves.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 3 of 47 Rev. 33 3.0 PRECAUTIONS AND LIMITATIONS
___ 3.1 This procedure does not duplicate or override any precautions and limitations referenced in approved operating procedures during the cooldown process. Steps are provided in this procedure to ensure conditions are satisfied prior to Mode changes IAW Administrative and Technical Specifications requirements.
___ 3.2 At least one Source Range Channel, OHA E-13, SR HI FLUX AT S/D, and the Audio Count Rate Channel should be OPERABLE anytime the reactor is shutdown.
___ 3.3 13 Charging Pump flow path shall be aligned to Unit 2 OR the pump shall be C/T when 11 or 12 Safety Injection Pump is capable of injection into the core with RCS temperature #312°F with the Reactor Vessel Head installed.
[C0565]
___ 3.4 2CV462, CHARGING CROSS TIE MOV may spuriously open due to a hot short in its power cable or control circuit during a fire on Unit 2. The design basis for Unit 1 POPS may be challenged with the additional charging flow from Unit 2.
For this reason, 2CV464, CHARGING CROSS TIE ISOLATION VALVE is to be CLOSED when Unit 1 RCS temperature is #312°F.
___ 3.5 RCS dilutions are allowed IAW S1.OP-SO.CVC-0006(Q),
Boron Concentration Control, provided:
RCS is maintained above the Cold Shutdown Boron Concentration IAW S1.RE-RA.ZZ-0016(Q), Curve Book.
CVCS Makeup Control System is returned to at least the Cold Shutdown boron concentration value IAW S1.RE-RA.ZZ-0016(Q), Curve Book.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 4 of 47 Rev. 33
___ 3.6 The following requirements are applicable to heatup or cooldown and plotted IAW S1.OP-TM.ZZ-0001(Q), RCS Pressure/Temperature Curves:
3.6.1 Pressurizer Insurge/Outsurge (WCAP 14950):
During normal RCS heatup and cooldown evolutions, some plant operating practices induce pressurizer insurge and outsurge cycles. These cycles can introduce additional fatigue loading to the lower end of the pressurizer when the temperature difference between the RCS and PZR is significant.
Existing plant instrumentation cannot be relied upon to detect the occurrence of this condition.
During Pressurizer cooldown evolutions, the Pressurizer Surge Line temperature should be monitored to ensure an outsurge and relatively stable temperature is maintained.
Pressurizer Surge Line temperature should trend with the saturation temperature in the Pressurizer. Pressurizer Surge Line temperature trending away from the saturation temperature and towards RCS Hot Leg temperature is an indication of an insurge.
To minimize Pressurizer insurge during RCS cooldown, Charging flow should be adjusted to offset the change in RCS volume while maintaining Pressurizer Level relatively constant. Another strategy would be to maximize Pressurizer Spray flow while maintaining Pressurizer Level relatively constant.
The pre-job brief should discuss factors that may have a significant impact on pressurizer insurge and outsurge cycles. Factors such as, Pressurizer Heater capacity, RCS heatup / cooldown rates and Charging / Letdown flow adjustments can all contribute to undesirable pressurizer insurge and outsurge cycles. The use of human performance reduction tools should also be discussed.
When a Pressurizer insurge that causes a >100°F step change in PZR surge line temperature is identified:
C Efforts should be made to allow the water to reach equilibrium temperature prior to initiating an outsurge.
C A Notification directed to Engineering is to be initiated for evaluation IAW WCAP 14950.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 5 of 47 Rev. 33 3.6.2 T/S Surveillance 4.4.9.1.1: The Reactor Coolant System pressure and temperature (except the pressurizer) shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations with:
A maximum heatup of 100°F in any one hour period.
A maximum cooldown of 100°F in any one hour period.
A maximum cooldown of 50°F in any one hour period when RCS temperature is <200°F.
A maximum temperature change of #5°F in any one hour period during hydrostatic testing operations.
3.6.3 T/S Surveillance 4.4.9.2: The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.
The spray water temperature differential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during auxiliary spray operation with:
A maximum heatup of 100°F in any one hour period.
A maximum cooldown of 200°F in any one hour period.
A maximum spray water temperature differential of 320°F.
3.6.4 Cooldown step changes should be limited to <25°F/hour. A step change is considered a large temperature change within a few minutes followed by essentially constant temperature for the balance of the hour. This is considered good operating practice (DES-DEF-90-01584).
3.6.5 RCS shrinkage will occur during RCS cooldown. Sufficient pressurizer inventory should be established prior to initiating RCS cooldown activities. At least 12,067 gallons of makeup water will be needed to cooldown from 547°F to 350°F and an additional 6,790 gallons will be needed to cooldown to 200°F.
Additionally, the 45 gpm letdown orifice and RCS makeup source from the RWST may be used to maintain a relatively constant pressurizer level.
3.6.6 During a Cooldown/Depressurization, Letdown flow will decrease as RCS Pressure drops. 13 Charging Pump linkage adjustment OR 1CV55 Low Flow control should be made ready prior to reaching this condition to preclude a rapidly increasing pressurizer level.
3.6.7 As RCS cooldown progresses, the maximum cooldown rate provided by the Steam Dump System drops significantly as RCS temperature approaches 400°F.
3.6.8 The cooldown rate provided by the Steam Dump System is affected by changes in Condenser backpressure. For example, starting a vacuum pump increases the steam flow through the system and increases the RCS cooldown rate.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 6 of 47 Rev. 33
___ 3.7 The automatic isolation time of <5 seconds for MSIVs pertains to the OPERABILITY of the MSIVs in Modes 1-3 per the requirements of T/S 3.7.1.5. S/R 4.7.1.5 states that each MSIV is demonstrated OPERABLE in Modes 1-3 by verifying full closure within 5 seconds when tested pursuant to T/S 4.0.5. Thus, the closure time pertains to main steam line isolation, not containment isolation.
T/S 3.6.3.1 pertains to operability of the containment isolation valves in Modes 1-4.
The main steam isolation valves (MSIVs) fulfill their containment isolation function as remote-manual containment isolation valves. The automatic closure of the MSIVs is NOT required for containment isolation due to having a closed system inside containment.
[80045103]
___ 3.8 When a MSIV is being relied upon as a remote-manual valve and either of the following conditions exist, the MSIV is inoperable IAW T/S 3.6.3.1:
With secondary side steam pressure <118 psia (Tavg <340°F)
AND the hydraulic actuator is NOT capable of closing the valve, or With secondary steam side pressure $118 psia (Tavg $340°F) and S1.OP-ST.MS-0003(Q) has NOT been performed within the last 92 days, AND the hydraulic actuator is NOT capable of closing the valve.
If either of the above conditions exist, the Mechanical Shaft Locking Device(s) is to be installed to secure the MSIV(s) in the closed position to comply with T/S 3.6.3.1.b.
___ 3.9 When a MSIV is being relied upon as a remote-manual valve and the valve hydraulic actuator is NOT capable of closing the valve, the MSIV is inoperable IAW T/S 3.6.3.1.
___ 3.10 The Post-Fire Safe Shutdown Equipment Administrative Controls, action level requirements are to be implemented should the MSIVs be closed in Step 5.1.35 or 5.1.36, IAW OP-SA-108-115-1001, Operability Assessment And Equipment Control Program
[80067063].
___ 3.11 The preferred method for RCS cooldown is by using the
[CAPR 70010788]
Steam Dump System in the Main Steam Pressure Control Mode. Operations Manager approval is required to utilize the MS10, Atmospheric Steam Relief Valves for normal cooldown OR normal RCS temperature control. This requirement does NOT supersede the authority of a licensed operator to use the MS10 valves to control RCS temperature in abnormal situations where the preferred heat sink is NOT available or inadequate.
___ 3.12 RCS cooldown via 11-14MS10 requires close monitoring of steam pressures to preclude inadvertent SI from Steam Generator differential pressure.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 7 of 47 Rev. 33
___ 3.13 Chemistry is to be notified whenever steam is released from the Steam Generators to the atmosphere by way of any MS10, S/G Safety valve, or steam driven AFP exhaust.
Chemistry will need to know the duration of the steam release as well as the affected Steam Generator(s). With this information, Chemistry can calculate the radioactive material concentration in the steam relative to that in the steam generator water IAW the ODCM section for Secondary Side Radioactive Gaseous Effluents and Dose Calculation. [70028596]
___ 3.14 The ability to reduce Reactor Coolant System or Steam Generator metal temperature is hindered when RCS water inventory is reduced. As a result of this, upcoming outage activities, such as the removal of S/G primary manway covers, should be reviewed prior to reducing RCS water inventory.
[70034006]
___ 3.15 In Modes 1-3, 2/3 S/G Level Channels at #14% on any Steam Generator is considered an ESF Actuation regardless of AFW Pump status [70027485]. For this reason, 11-14 S/G narrow range levels are to be maintained $28% during the RCS cooldown.
The RCS cooldown rate is to be reduced when any S/G is <28% narrow range level.
The RCS cooldown is to be suspended when any S/G is #24% narrow range level.
RCS cooldown may recommence when all S/G narrow range levels are >28%.
[70067944]
___ 3.16 Cold Shutdown Testing (CST) requirements as described in ER-AA-321, Administrative Requirements for Inservice Testing [70039673]:
All due and overdue Cold Shutdown Testing procedures are required to be performed during a Refueling Outage prior to returning the plant to operation.
Cold Shutdown Testing is also required when the plant is placed in Mode 5 from Mode 4 (Mode 5 being the trigger) for reasons other than Refueling Outage. It is NOT the intent of the Inservice Testing Program to hold the plant in cold shutdown in order to complete Cold Shutdown Testing, however, it is the intent to complete as many tests as possible on a good-faith basis.
The Station Planning Operations scheduler will schedule testing based on a Cold Shutdown, Refueling and Extended Outage testing list provided by the IST Program Engineer. Scheduled testing is to be started no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching Mode 5 and is to continue until the plant is ready for Mode 4 entry at which time any in-progress 4.0.5V surveillances are completed without initiating others. In some cases Cold Shutdown Testing may be required to be performed in Mode 4 or Mode 3 depending on the overdue dates relative to testing already performed during Mode 5.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 8 of 47 Rev. 33
___ 3.17 S1.OP-AB.RHR-0001(Q), Loss Of RHR, is to be reviewed prior to opening any RCS Vent Path within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of reactor shutdown with the Containment Equipment Hatch open.
___ 3.18 When the RCS is vented to the Containment with either the Containment Equipment Hatch or a Containment Air Lock OPEN, the vent path established must be capable of being closed prior to the time to Core Boiling as determined by S1.OP-AB.RHR-0001(Q).
When the RCS is vented to the Containment, Salem's interpretation of NUMARC 91-06 requires that either the RCS is made intact prior to the time to core boiling should RHR be lost (applicable when the RCS loops are filled and two or more Steam Generators are available as a heat sink for Natural Circulation. Heat sink means the Steam Generators has a feed make-up source available, Secondary water level above the U-tubes, and a Steam Generator vent path), OR Containment Closure is established prior to time to core boiling should a Loss of RHR occur. (Containment Closure in this statement only applies to the Containment Equipment Hatch and the Containment Air Locks; Containment Closure of all other penetrations is required prior to Core Uncovery and is established IAW S1.OP-AB.CONT-0001(Q) [80082938].
___ 3.19 An alternate Pressurizer Cold Scaled Level indication for at least one
[CAPR 70090887]
of the three hot calibrated PZR Level Channels is to be provided whenever the PZR Liquid/Vapor temperature is #210°F. A Cold Scaled Level indication is simply a hot calibrated channel with a different meter scale. The scaling was developed utilizing the known relationship between the hot and cold calibrated channels at 140°F as depicted in Exhibit 1. It should be noted that the Indicated Pressurizer Level (%) displayed in Exhibit 1 graphs were developed using existing Hot Calibrated channel scaling and cannot be used with selected Cold Scaled Level indication(s). Cold Scaled Level indication(s) may be provided at anytime after Mode 4 is entered, however at least one indication is to be provided prior to lowering pressurizer level at Step 5.1.59.
4.0 EQUIPMENT/MATERIAL REQUIRED 3/64 Hex Key (Allen) wrench (for Maintenance to provide Cold Scale Level indications)
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 9 of 47 Rev. 33 5.0 PROCEDURE 5.1 Hot Standby to Cold Shutdown 5.1.1 IF this procedure was entered from the EOP network procedures, THEN:
A.
IF the Automatic Safety Injection Block is established (1RP4),
THEN:
1.
COMPLETE one of the following:
COMPLY with T/S 3.0.3.
(SSPS Train A & B inoperable; T/S 3.3.2.1, Table 3.3-3, Functional Unit 1.b, Automatic Actuation Logic)
RE-INSTATE AUTO SI IAW S1.OP-SO.RPS-0008(Q),
Establishing/Removing Auto SI Block.
Direct a second Operator to PERFORM Independent Verification of AUTO SI BLOCK removed (unblocked):
IV Signature Date 2.
INITIATE S1.OP-SO.SJ-0004(Q), Post Safety Injection System Restoration.
B.
REVIEW Mode 3 T/S requirements to determine applicable action statements based on the evaluation of available instrumentation, Phase A and/or Phase B system alignments, electrical distribution system alignment, and other ECCS/ESF system alignments.
C.
IF Main Steam Isolation signal is NOT present, THEN OPEN 11-14MS7, MN STM DRN valves.
D.
INITIATE S1.OP-SO.CN-0002(Z), Steam Generator Feed Pump Operation, to complete SGFP shutdown sequence.
NOTE Steps 5.1.2 through 5.1.13 may be performed in any order at discretion of the SM/CRS.
5.1.2 DIRECT an Operator to CLOSE 1BF44, FW TO MSCDT.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 10 of 47 Rev. 33 5.1.3 IF Containment inspection is required, THEN INITIATE S1.OP-PT.CAN-0001(Q), Containment Walkdown.
5.1.4 IF Main Turbine-Generator degas is required, THEN INITIATE S1.OP-SO.GEN-0003(Z),
Main Generator Gas System Operation.
5.1.5 ESTABLISH Pressurizer Level between 25-53%:
[CAPR 70090887]
A.
PLACE Charging System Master Flow Controller in MANUAL.
B.
ADJUST CHARGING FLOW as required to establish and maintain pressurizer level during cooldown.
5.1.6 IF RCS is to be borated prior to start of cooldown to 350°F OR is to be borated concurrently with cooldown, THEN:
A.
ENSURE Shutdown Margin IAW SC.RE-ST.ZZ-0002(Q), Figures.
B.
PERFORM RCS boration IAW S1.OP-SO.CVC-0006(Q),
Boron Concentration Control.
NOTE To preclude delays during the next Unit startup, 13 AFW Pump, when available, should be placed in service to ensure any required maintenance is identified.
5.1.7 IF 13 AFW Pump is available AND at the SM/CRS discretion, THEN:
A.
PLACE 13 AFW Pump in service IAW S1.OP-SO.AF-0001(Q),
Auxiliary Feedwater System Operation, to verify proper operation.
B.
INITIATE S1.OP-ST.AF-0007(Q), Inservice Testing -
Auxiliary Feedwater Valves Mode 3.
C.
When operation is verified, SWAP to motor driven AFW pumps AND REMOVE 13 AFW Pump from service IAW S1.OP-SO.AF-0001(Q),
Auxiliary Feedwater System Operation.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 11 of 47 Rev. 33 5.1.8 COORDINATE RCS Fission Gas Removal AND RCS Mechanical Degasification evolutions with Chemistry personnel IAW S1.OP-SO.CVC-0011(Q),
RCS Degasification.
5.1.9 ENSURE CVCS Makeup Control System is adjusted to at least the Cold Shutdown boron concentration value IAW S1.RE-RA.ZZ-0012(Q), Figures.
5.1.10 IF Steamline Isolation and Response Time Testing is to be performed, THEN INITIATE S1.OP-ST.MS-0003(Q), Steamline Isolation and Response Time Testing.
5.1.11 IF the High Flux at Shutdown Alarm was NOT adjusted in S1.OP-IO.ZZ-0005(Q) at approximately 547°F, THEN NOTIFY Maintenance to adjust the High Flux at Shutdown Alarm IAW SC.IC-DC.NIS-0003(Q), Bistable Setpoint Adjustment N31 and N32 Source Range High Flux at Shutdown.
5.1.12 IF any RCP(s) are to be stopped when RCS temperature is <500°F to support the current outage plan (Refer to Step 5.1.21),
THEN:
A.
IF Rod Control System is ENERGIZED, THEN INITIATE S1.OP-SO.RCS-0001(Q), Rod Control System Operation to align the system NOT capable of Rod withdrawal to comply with T/S 3.4.1.2.c.
B.
INITIATE S1.OP-SO.RC-0001(Q), Reactor Coolant Pump Operation.
A minimum of one RCP is to remain in operation to comply with T/S 3.4.1.2.
C.
INITIATE the performance of S1.OP-ST.RC-0005(Q),
Reactor Coolant System RC/RHR Loop Status Modes 3-4.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 12 of 47 Rev. 33 5.1.13 PERFORM the following (70016928):
A.
IF Turbine Building Sump Pumps are aligned to the Non-Rad Waste Basin, THEN:
1.
ENSURE 1BD107, 1 TGA SUMP ISO VLV TO NON-RAD is OPEN.
2.
ENSURE 1BD109, 1TGA SUMP TO SKIMMER ISOL VLV is CLOSED.
- 3.
ENSURE S1230-1HY5TB1H, 1 FLOOD PUMP is OPEN.
B.
IF Turbine Building Sump Pumps are aligned to #1 Skimmer Tank, THEN PERFORM the following:
OPEN the following breakers:
___ ! S1230-1HY5TB1H, 1 FLOOD PUMP
___ ! S1230-1HY5TB4G, 13 TURBINE AREA SUMP PUMP
___ ! S1230-1HY5TB5G, 14 TURBINE AREA SUMP PUMP DIRECT Site Services to install a temporary sump pump in 13 TGA Sump with the pump discharge directed to the Chemical Waste Hopper (100N TGA, DM Plant).
NOTIFY Chemistry of temporary sump pump status AND DOCUMENT in the Control Room Narrative Log.
NOTE RCS and Pressurizer cooldown plots should be maintained IAW S1.OP-TM.ZZ-0001(Q),
RCS Pressure/Temperature Curves.
5.1.14 INITIATE the following:
SC.OP-DL.ZZ-0011(Q), Reactor Coolant System Heatup/Cooldown Log SC.OP-DL.ZZ-0012(Q), Pressurizer Heatup/Cooldown Log
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 13 of 47 Rev. 33 NOTES During normal RCS heatup and cooldown evolutions, some plant operating practices induce pressurizer insurge and outsurge cycles. These cycles can introduce additional fatigue loading to the lower end of the pressurizer when the temperature difference between the RCS and PZR is significant. Existing plant instrumentation cannot be relied upon to detect the occurrence of this condition.
During Pressurizer cooldown evolutions, the Pressurizer Surge Line temperature should be monitored to ensure an outsurge and relatively stable temperature is maintained.
Pressurizer Surge Line temperature should trend with the saturation temperature in the Pressurizer. Pressurizer Surge Line temperature trending away from the saturation temperature and towards RCS Hot Leg temperature is an indication of an insurge.
To minimize Pressurizer insurge during RCS cooldown, Charging flow should be adjusted to offset the change in RCS volume while maintaining Pressurizer Level relatively constant. Another strategy would be to maximize Pressurizer Spray flow while maintaining Pressurizer Level relatively constant.
The pre-job brief should discuss factors that may have a significant impact on pressurizer insurge and outsurge cycles. Factors such as, Pressurizer Heater capacity, RCS heatup / cooldown rates and Charging / Letdown flow adjustments can all contribute to undesirable pressurizer insurge and outsurge cycles. The use of human performance reduction tools should also be discussed.
When a Pressurizer insurge that causes a >100°F step change in PZR surge line temperature is identified, efforts should be made to allow the water to reach equilibrium temperature prior to initiating an outsurge. A NOTF directed to Engineering is to be initiated for evaluation IAW WCAP 14950.
5.1.15 ESTABLISH Pressurizer outsurge flow by placing the Pressurizer Control System in MANUAL IAW S1.OP-SO.PZR-0005(Q),
Pressurizer Pressure Control System Operation.
5.1.16 ESTABLISH Pressurizer Level between 25-53%:
[CAPR 70090887]
A.
PLACE Charging System Master Flow Controller in MANUAL.
B.
ADJUST CHARGING FLOW as required to establish and maintain pressurizer level during cooldown.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 14 of 47 Rev. 33 5.1.17 IF Steam Dump System is available, THEN INITIATE RCS Cooldown IAW S1.OP-SO.MS-0002(Q),
Steam Dump System Operation.
5.1.18 IF the Steam Dump System is NOT available, AND 11-14MS10, Main Steam System Relief Valve use is authorized, THEN INITIATE RCS Cooldown using 11-14MS10, Main Steam System Relief Valves, as necessary, to establish an RCS cooldown rate of <100°F/hour.
[Refer to Step 3.11]
5.1.19 When RCS temperature reaches 543°F AND LOW LOW TAVG 2/4, TAVG LOW LOW (P-12 Permissive) yellow status lamp is illuminated on 1RP4:
A.
IF Steam Dump System is in service, THEN BYPASS Steam Dump Low Low TAVG Block (P-12 Permissive)
IAW S1.OP-SO.MS-0002(Q), Steam Dump System Operation.
B.
DEPRESS the Safeguards Actuation, Train "A" Controls, BLOCK HI STM LN FLO SI Bezel pushbutton. (Blocks Train "A" High Steam Flow coincident with Low Steam Pressure or Low-Low TAVG SI).
C.
DEPRESS the Safeguards Actuation, Train "B" Controls, BLOCK HI STM LN FLO SI Bezel pushbutton. (Blocks Train "B" High Steam Flow coincident with Low Steam Pressure or Low-Low TAVG SI).
D.
ENSURE HI STM LN FLO SI BLKD blue status lamp illuminated on 1RP4.
E.
DIRECT a second Operator to perform Independent Verification of Safeguards Actuation block status:
Train "A" Controls, BLOCK HI STM LN FLO SI Bezel pushbutton illuminated.
Train "B" Controls, BLOCK HI STM LN FLO SI Bezel pushbutton illuminated.
IV Signature Date 5.1.20 ADJUST Pressurizer Pressure Control System controls to establish a desired Pressurizer cooldown rate while maintaining Pressurizer outsurge flow.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 15 of 47 Rev. 33 5.1.21 IF RCS temperature is <500°F AND RCP(s) are to be stopped to support the current outage plan, THEN INITIATE RCP stop sequence as directed by the SM/CRS as follows:
A.
ENSURE Rod Control System is de-energized to comply with T/S 3.4.1.2.c.
NOTE Steam Generator steam flow will transfer to the RC Loop(s) with an operating RCP as the RCP(s) on the other RC Loops are stopped. This transfer of steam flow is more prevalent immediately after the third RCP is stopped. The NCO should be prepared to make significant AFW adjustments after each RCP is stopped.
B.
STOP RCPs as directed by the SM/CRS IAW S1.OP-SO.RC-0001(Q),
Reactor Coolant Pump Operation while maintaining a minimum of one in operation to comply with T/S 3.4.1.2.
NOTE Pressurizer Pressure SI will automatically reset when pressure rises above 1915 psig.
SI signal may be blocked when pressure is reduced to <1915 psig.
5.1.22 When RCS is <1915 psig, AND PZR PRESS BELOW P-11 2/3, P-11 green status lamp is illuminated on 1RP4:
A.
PRESS Train "A" Controls, BLOCK LO PZR PRESS SI, 1CC1 Console Safeguards Actuation Bezel.
B.
PRESS Train "B" Controls, BLOCK LO PZR PRESS SI, 1CC1 Console Safeguards Actuation Bezel.
C.
ENSURE 1RP4, LO PZR PRESS SI BLOCK, blue status lamp illuminated.
D.
DIRECT a second Operator to perform Independent Verification of Safeguards Actuation block status:
Train "A" Controls, BLOCK LO PZR PRESS SI Bezel pushbutton illuminated.
Train "B" Controls, BLOCK LO PZR PRESS SI Bezel pushbutton illuminated.
IV Signature Date
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 16 of 47 Rev. 33 NOTE Letdown flow should NOT exceed 130 gpm. Letdown pressures and temperatures are to be closely monitored to ensure flashing in the Letdown line does NOT occur.
5.1.23 PERFORM the following:
A.
OPEN 1CV3, 1CV4 and 1CV5 to maintain required letdown flow rates as required during RCS cooldown.
B.
IF CVCS Letdown is to be maximized to support current plant evolutions, THEN MAXIMIZE Letdown Flow During Shutdown IAW S1.OP-SO.CVC-0001(Q), Charging, Letdown, And Seal Injection.
5.1.24 During cooldown, ADJUST charging flow as needed to maintain Pressurizer level $25%.
[CAPR 70090887]
5.1.25 IF a Centrifugal Charging Pump is in service, THEN:
A.
PLACE 1CA2015, CONTROL AIR SUPPLY TO CV55 BYPASS VALVE, in BYPASS.
B.
ADJUST 1CV55 to obtain the desired flow.
C.
ENSURE Seal Injection flow 6-12 gpm to each Reactor Coolant Pump not to exceed 40 gpm total Seal Injection flow.
5.1.26 IF RCS makeup from the RWST is required to maintain VCT level during RCS cooldown, THEN INITIATE Attachment 1, RCS Makeup Source.
5.1.27 IF Steam Generator level control is to be transferred to the Condensate System when S/G pressure is #550 psig, THEN ESTABLISH feeding the Steam Generators from the Condensate System IAW S1.OP-SO.CN-0001(Q), Condensate System Operation, at the discretion of the SM/CRS.
5.1.28 IF S1.OP-ST.SJ-0020(Q), Periodic Leakage Test-RCS Pressure Isolation Valves, is to be performed (Refer to Step 2.8),
THEN MAINTAIN RCS pressure $1000 psig while continuing with this procedure.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 17 of 47 Rev. 33 NOTE Steps 5.1.29 to 5.1.36 may be performed in any order at discretion of the SM/CRS.
5.1.29 SM/CRS to EVALUATE placing the Condensate System On Recirc and flush the condenser sparging steam header IAW S1.OP-SO.CN-0001(Q),
Condensate System Operation. This is to identify potential system deficiencies and to facilitate repairs during the outage [80082196].
5.1.30 IF RCS temperature is to be stabilized between 350°F and 450°F for >12 hours, THEN when RCS is <450°F, NOTIFY Maintenance to adjust the High Flux at Shutdown Alarm IAW SC.IC-DC.NIS-0003(Q), Bistable Setpoint Adjustment N31 and N32 Source Range High Flux at Shutdown.
5.1.31 When RCS pressure is <1000 psig:
A.
PLACE 11-14SJ54 in VALVE OPERABLE on 1RP4.
B.
Direct a second Operator to PERFORM Independent Verification that 11-14SJ54 are in VALVE OPERABLE on 1RP4.
IV Signature Date C.
CLOSE 11-14SJ54, Accumulator Outlet Valves.
D.
Direct a second Operator to PERFORM Independent Verification that 11-14SJ54 are CLOSED.
IV Signature Date E.
DIRECT an Operator to OPEN 11-14SJ54 power supply breakers AND UPDATE WCM for 11-14SJ54 "Off-Normal" Status.
F.
IF the repositioning of 1CV114, Seal Water Bypass, is required:
THEN REFER to S1.OP-SO.RC-0001(Q), Reactor Coolant Pump Operation, for 1CV114 valve position requirements AND UPDATE WCM for 1CV114 "Off-Normal" Status.
5.1.32 IF Rod Control System is ENERGIZED, THEN INITIATE S1.OP-SO.RCS-0001(Q), Rod Control System Operation to align the system NOT capable of Rod withdrawal prior to Mode 4.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 18 of 47 Rev. 33 5.1.33 IF RCS temperature is <400°F AND any RCP is to be stopped to support current plant conditions, THEN:
A.
ENSURE Rod Control System is de-energized to comply with T/S 3.4.1.2.c.
B.
OPERATE RCPs as required for current plant conditions IAW S1.OP-SO.RC-0001(Q), Reactor Coolant Pump Operation while maintaining a minimum of one in operation to comply with T/S 3.4.1.2.
C.
INITIATE the performance of S1.OP-ST.RC-0005(Q),
Reactor Coolant System RC/RHR Loop Status Modes 3-4.
5.1.34 IF RCS boration is required to establish Shutdown Margin boron concentration for #200°F, THEN:
A.
REFER to S1.RE-RA.ZZ-0016(Q), Curve Book, for required RCS boron concentration for #200°F.
B.
PERFORM boration IAW S1.OP-SO.CVC-0006(Q),
Boron Concentration Control.
NOTE Operation of the 11-14MS10 valves may be required when the preferred heat sink is NOT available OR inadequate. Refer to Step 3.11 for management expectations for authorizing the use of the 11-14MS10 valves during RCS cooldown.
5.1.35 IF the Steam Dump System is being used for plant cooldown, AND 11-14MS18 valves are adequate to support RCS cooldown with the 11-14MS167 valves CLOSED, THEN:
A.
OPEN 11-14MS18, MN STM STOP BYPASS VLV, as necessary to support RCS cooldown.
B.
CLOSE 11-14MS167 valves.
C.
IF 11-14MS10, Main Steam System Relief Valves use is authorized, THEN OPERATE 11-14MS10, as necessary to support RCS cooldown.
5.1.36 IF the Steam Dump System is NOT being used for plant cooldown, THEN CLOSE 11-14MS167 valves.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 19 of 47 Rev. 33 5.1.37 IF 11-14MS167 valves are CLOSED, THEN INITIATE Post-Fire Safe Shutdown Equipment Administrative Controls IAW OP-SA-108-115-1001, Operability Assessment And Equipment Control Program [80067063].
5.1.38 When RCS temperature is <350°F and >312°F:
A.
RECORD time Mode 4 is entered in Control Room Narrative Log.
B.
UPDATE WCM to reflect Mode change.
C.
IF S1.OP-ST.SJ-0020(Q), Periodic Leakage Test-RCS Pressure Isolation Valves, is to be performed (Refer to Step 2.8),
THEN INITIATE S1.OP-ST.SJ-0020(Q).
D.
PLACE 1SJ135 in VALVE OPERABLE on 1RP4.
E.
Direct a second Operator to PERFORM Independent Verification that 1SJ135 is in VALVE OPERABLE on 1RP4.
IV Signature Date F.
CLOSE 1SJ135, SI Discharge to Cold Legs Valve.
G.
Direct a second Operator to PERFORM Independent Verification that 1SJ135 is CLOSED.
IV Signature Date H.
CLOSE 11 & 12SJ134, SI Pumps to Cold Legs Valves.
I.
Direct a second Operator to PERFORM Independent Verification that 11 & 12SJ134 are CLOSED.
IV Signature Date (step continued on next page)
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 20 of 47 Rev. 33 5.1.38 (continued)
NOTE A maximum of one Centrifugal Charging Pump or one Safety Injection Pump shall be operable when RCS Cold Leg temperature #312°F IAW T/S 3.5.3 J.
C/T 11 & 12 SI Pump power supplies for SM/CRS.
K.
IF both Centrifugal Charging Pumps are OPERABLE, THEN C/T OPEN the breaker to one Centrifugal Charging Pump AND RECORD SI/CVC Pump breaker status in S1.OP-DL.ZZ-0006(Q), Primary Plant Log.
L.
ENSURE 1CV3, 1CV4 and 1CV5 are OPEN to maintain required letdown flow rates as required during RCS cooldown.
M.
IF manual control of 1CV18 is required to maximize Letdown flow, THEN:
1.
Using Regenerative Heat Exchanger outlet temperature (T0127A),
Letdown pressure (1PI135B) and Steam Tables, DETERMINE the minimum pressure required to maintain the outlet of the Regenerative Heat Exchanger at least 10°F subcooled.
2.
PLACE 1CV18 in MANUAL.
3.
Slowly ADJUST 1CV18 as required to obtain desired letdown flow while maintaining Regenerative Heat Exchanger outlet at least 10°F subcooled.
N.
CLOSE 2CV464, CHARGING CROSS TIE ISOLATION VALVE.
O.
NOTIFY the Unit 2 CRS that 2CV464 is CLOSED AND 23 Charging Pump is NOT required to provide Post-Fire Shutdown capability for Unit 1.
P.
NOTIFY the Appendix R Safe Shutdown Program Engineer that 23 Charging Pump is NOT available to provide Post-Fire Safe Shutdown capability AND to initiate the appropriate compensatory measures for Unit 1.
(step continued on next page)
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 21 of 47 Rev. 33 5.1.38 (continued)
Q.
PLACE 13 Charging Pump linkage in the low pressure position as follows:
1.
IF 13 Charging Pump is in service, THEN TRANSFER to a Centrifugal Charging Pump IAW S1.OP-SO.CVC-0002(Q), Charging Pump Operation.
2.
PLACE 13 Charging Pump linkage in the low pressure position.
3.
IF 13 Charging Pump is to be placed in service, THEN TRANSFER to 13 Charging Pump IAW S1.OP-SO.CVC-0002(Q), Charging Pump Operation.
CAUTION Operation of RCPs, other than as specified, can result in uneven RCS temperatures and create conditions in Steam Generators causing inadvertent SI due to SG differential pressures.
R.
IF high RCS flow rates for chemical additions are no longer required, THEN REDUCE number of operating RCPs to two OR one IAW S1.OP-SO.RC-0001(Q), Reactor Coolant Pump Operation.
S.
INITIATE S1.OP-SO.RPS-0009(Q), Installation / Removal of AFW Start Function, Section for defeating Aux Feed Pump Auto Start.
[C0569]
5.1.39 IF RCS temperature is to be stabilized between 200°F and 350°F for >12 hours, THEN NOTIFY Maintenance to adjust the High Flux at Shutdown Alarm IAW SC.IC-DC.NIS-0003(Q), Bistable Setpoint Adjustment N31 and N32 Source Range High Flux at Shutdown.
5.1.40 When RCS pressure is <360 psig and temperature >312°F:
A.
ENSURE Maintenance has completed POPS functional IAW S1.IC-FT.RCP-0070(Q), 1PT403 Reactor Coolant System Hot Leg Pressure Channel II AND S1.IC-FT.RCP-0071(Q),
1PT405 Reactor Coolant System Hot Leg Pressure Channel I.
B.
ARM POPS IAW S1.OP-SO.PZR-0004(Q),
Pressurizer Overpressure Protection Operation.
C.
IF RHR Loop boron concentration is less than the required RCS boron concentration for 200°F IAW S1.RE-RA.ZZ-0016(Q), Curve Book, THEN PLACE the RHR System In Service For Sampling in Mode 4 IAW S1.OP-SO.RHR-0001(Q), Initiating RHR.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 22 of 47 Rev. 33 5.1.41 When RCS pressure is #340 psig, PLACE the RHR System In Service For Shutdown Cooling in Mode 4 IAW S1.OP-SO.RHR-0001(Q), Initiating RHR.
5.1.42 When RCS temperature is <250°F, PERFORM the following:
OPERATE 11-14MS10 Main Steam System Relief Valves as necessary to vent non condensable gasses.
COORDINATE RCS Chemical Degasification AND RCS crud solubilization evolutions with Chemistry personnel IAW S1.OP-SO.CVC-0011(Q), RCS Degasification.
5.1.43 IF RCS temperature is <248°F AND the second loop of RHR is to be placed in service, THEN INITIATE placing the second loop of RHR in service IAW S1.OP-SO.RHR-0001(Q), Initiating RHR.
5.1.44 IF plant maintenance requires RCS temperature <210°F, THEN:
A.
MAINTAIN RCS temperature <210°F until work is completed.
B.
RECORD Admin Tag Number(s):
5.1.45 IF more than two RCPs are in service, THEN prior to reducing RCS temperature <200°F, REDUCE the number of operating RCPs to two OR one IAW S1.OP-SO.RC-0001(Q), Reactor Coolant Pump Operation.
5.1.46 INITIATE S1.OP-DL.ZZ-0002(Q), Control Room Logs - Mode 5, 6, and Defueled.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 23 of 47 Rev. 33 NOTE RCS cooldown rate is limited to #50°F/hour IAW S1.OP-TM.ZZ-0001(Q),
RCS Pressure/Temperature Curves.
RCS pressure <100 psig eliminates the use of crediting the RCS to meet T/S 3.4.1.4.
[C0609]
5.1.47 When RCS temperature is <200°F:
A.
REDUCE RCS cooldown rate to #50°F/hour.
B.
RECORD time Mode 5 is entered in Control Room Narrative Log.
C.
UPDATE WCM to reflect Mode change.
D.
IF the second loop of RHR is NOT inservice, THEN INITIATE placing second loop of RHR in service IAW S1.OP-SO.RHR-0001(Q), Initiating RHR.
E.
INITIATE IST valve surveillance procedures which are required to be performed in Mode 5.
F.
CONTINUE RCS Cooldown while slowly raising Pressurizer level to.80%
as indicated on the cold calibrated level channel.
G.
PERFORM the following:
1.
C/T 11 and 12 Containment Spray Pumps for SM/CRS 2.
CLOSE AND LOCK the following:
11CS20 12CS20 3.
UNLOCK AND CLOSE the following:
11CS6 12CS6 4.
SELECT 1CS14 VALVE OPERABLE at 1RP4 5.
CLOSE 1CS14 6.
UPDATE WCM to reflect current component status (step continued on next page)
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 24 of 47 Rev. 33 5.1.47 (continued)
H.
IF the remaining Centrifugal Charging Pump is NOT required to support current plant operation, THEN C/T the remaining Centrifugal Charging Pump for the SM/CRS.
I.
IF Condenser vacuum is NOT to be maintained, THEN BREAK Vacuum IAW S1.OP-SO.AR-0001(Z),
Condenser Air Removal System Operation.
J.
IF Steam Generators will be placed in Wet Layup, THEN INITIATE S1.OP-SO.SG-0002(Q),
Maintaining Steam Generators in Wet Layup.
K.
ESTABLISH Auto SI Block IAW S1.OP-SO.RPS-0008(Q),
Establishing/Removing Auto SI Block.
L.
PLACE Containment Evacuation horn block switch on 1RP2 in BLOCK position.
M.
NOTIFY the Appendix R Safe Shutdown Program Engineer that Unit 1 RCS temperature is <200°F and the compensatory measures implemented for Unit 1 may be removed.
N.
IF entry into Mode 5 is for Refueling Outage, THEN NOTIFY the Outage Execution Team Supervisor to have the Containment Sump Strainer Covers installed on all sump strainers.
5.1.48 NOTIFY Maintenance to adjust the High Flux at Shutdown Alarm IAW SC.IC-DC.NIS-0003(Q), Bistable Setpoint Adjustment N31 and N32 Source Range High Flux at Shutdown.
5.1.49 IF Pressurizer cooldown is required, THEN INITIATE monitoring of parameters listed in Attachment 2, Section 4.0 AND CONTINUE to monitor parameters until PZR fill and drain down evolutions have been completed.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 25 of 47 Rev. 33 NOTE Performance of Step 5.1.50 will collapse the pressurizer steam bubble while maintaining at least one RCP in operation.
5.1.50 IF Pressurizer Cooldown is required, THEN:
A.
ENSURE Pressurizer Spray )T between the PZR and Auxiliary Spray fluid is <320°F AND recorded IAW S1.OP-DL.ZZ-0002(Q), Control Room Logs Mode 5, 6 and Defueled (T/S 4.4.9.1.1).
B.
ENSURE SC.OP-DL.ZZ-0012(Q), Pressurizer Heatup/Cooldown Log is maintained during cooldown.
C.
STABILIZE the following parameters:
RCS Temperature RCS Pressure CAUTION Pressurizer Spray Flow should be maximized in order to maintain a continuous PZR outsurge flow that will minimize temperature transients in the PZR surge nozzle and portions of the PZR lower head during PZR fill evolutions. (WCAP-13588/14950)
D.
MAXIMIZE Pressurizer Spray flow as follows:
1.
PLACE all available Pressurizer BACKUP AND CNTRL GRP HEATERS to ON.
2.
ADJUST SPRAY VALVE CONTROL to maintain the following parameters:
RCP Seal )P $200 psid RCS Pressure #340 psig (step continued on next page)
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 26 of 47 Rev. 33 5.1.50 (continued)
CAUTION RCP Seal )P of $200 psid is to be maintained during RCP operation.
PZR pressure is limited to #340 psig when RHR is aligned to the RCS.
A relatively constant PZR Surge Line temperature is an indication of continuous PZR outsurge flow.
The Pressurizer cold calibrated level is calibrated for 68°F. At.430°F, the Pressurizer cold calibrated level will indicate.84% with actual level being 100%.
At this point.528 gallons will be needed to take the pressurizer solid (SC-RC002-01) assuming a constant PZR water temperature. An additional
.33 gallons is needed for each 1.0°F change in PZR water temperature.
Previous performance has shown this value to be.1600 gallons.
Expect to go water solid when indicated COLD CAL level is <100%.
E.
FILL the Pressurizer to 84% as indicated on both COLD CAL level indications, console (LI462) and SPDS (U1LT0462S).
F.
When 84% Pressurizer cold calibrated level is achieved, ADJUST the PZR fill rate to #25 gpm.
NOTE It may take several hours to fill the pressurizer and completely collapse the steam bubble.
Steam bubble collapse is indicated by further opening of the spray valve(s) with little or no effect on pressure. Pressure control is then transferred from the spray valves to the charging flow control.
G.
When the pressurizer is water solid (steam bubble collapsed),
Slowly ADJUST Charging OR Letdown flowrate to stabilize RCP Seal )P $200 psid AND RCS Pressure #340 psig.
H.
PLACE Pressurizer BACKUP AND CNTRL GRP HEATERS to OFF.
I.
ENSURE 1CV79, Charging Line Stop Valve is CLOSED.
J.
OPEN 1CV75, Pressurizer Auxiliary Spray Stop Valve.
K.
CLOSE 1CV77, Charging Line Stop Valve.
L.
IF RCS makeup from the RWST is required to maintain VCT level during RCS cooldown, THEN INITIATE Attachment 1, RCS Makeup Source.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 27 of 47 Rev. 33 5.1.51 ENSURE PZR and RCS Boron Concentrations are above the concentration specified in S1.RE-RA.ZZ-0016(Q), Curve Book.
5.1.52 ENSURE PZR and RCS Boron Concentrations are within 50 ppm of each other OR RCS is $2050 ppm and PZR is $2000 ppm.
5.1.53 IF the BAST System cross-connect was aligned during RCS cooldown, THEN ENSURE Unit 2 BAST to Unit 1 BAST restoration is complete IAW S1.OP-SO.CVC-0005(Q), Boric Acid Solution Preparation and Transfer.
CAUTION The Reactor Vessel Inlet Nozzles are the limiting components during cooldown with all RCPs secured. Because of this, the RHR HX Inlet temperature shall not be used to plot RCS cooldown rate.
The RHR discharge piping injects into the RCS downstream of the RCS WR Tcold RTDs. Because of this, the RCS WR Tcold RTDs shall not be used to plot RCS cooldown rate with all RCPs secured.
When the last RCP is secured, the RHR HX Outlet temperature should be used to plot RCS cooldown rate.
RHR cooling will be reduced prior to securing the last RCP to ensure that the Operator has control of the RCS cooldown rate.
When the last RCP is secured, the RCS Cold Leg temperature will trend towards the RHR HX Outlet temperature. This will change the RCS cooldown rate.
To ensure that the next calculated hourly cooldown rate does not exceed the T/S 3.4.9.1 limit of 50°F/hour, the RHR HX Outlet temperature must be compared to the RCS cooldown rate for the previous 60 minutes.
5.1.54 PERFORM the following:
A.
ADJUST RHR Cooling to provide a slight RCS Heatup Rate, AND ENSURE RHR HX Outlet temperature is within 50°F of the RCS WR Tcold RTD for the previous 60 minutes.
B.
TRANSITION from the coldest RCS WR Tcold RTD to the RHR HX Outlet temperature for plotting RCS cooldown rate.
C.
NOTIFY Chemistry AND ENSURE all evolutions requiring RCP operation (RCS boron/chemical additions, RCS Crud Burst, RCS Degas, RCS Cleanup, S/G cooldown and PZR cooldown) are completed.
(step continued on next page)
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 28 of 47 Rev. 33 5.1.54 (continued)
D.
IF Step 5.1.50 was performed,
[CAPR 70090887/70100702]
THEN ENSURE PZR Liquid/Vapor Temperatures are #210°F prior to securing the last RCP.
E.
SECURE remaining RCP(s) IAW S1.OP-SO.RC-0001(Q),
Reactor Coolant Pump Operation.
F.
ADJUST RHR cooling to establish a #50°F/hour RCS Cooldown Rate.
G.
IF Step 5.1.50 was performed AND the RCS is to be depressurized to support plant maintenance activities or refueling outage, THEN:
1.
ENSURE all RCPs are secured.
CAUTION The rate of RCS depressurization should be maintained at #25 psig / minute.
Potential voiding of the reference leg for PZR level transmitter LT462 (COLD CAL) may occur at faster rates.
[CAPR 70090887]
2.
Slowly DEPRESSURIZE the Reactor Coolant System at
- 25 psig / minute by adjusting Charging flow to less than Letdown flow.
3.
When RCS pressure is <100 psig, PERFORM the following:
___ a. CLOSE 11-14CV104, RCP Seal Water Return Stop.
___ b. ENSURE 1CV114, Seal Water Bypass is CLOSED.
___ c. Direct a second Operator to PERFORM Independent Verification that 1CV114, Seal Water Bypass is CLOSED.
IV Signature Date 4.
When Pressurizer cooldown temperature is obtained:
___ a. OPEN 1CV77.
___ b. CLOSE 1CV75.
H.
DIRECT Maintenance to initiate
[CAPR 70090887]
SC.IC-GP.RC-0092(Q), Backfilling LT462 Cold Pressurizer Level Reference Leg.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 29 of 47 Rev. 33 5.1.55 IF Step 5.1.50 is marked as N/A, AND Pressurizer cooldown and depressurization is required to support plant maintenance activities or refueling outage, THEN:
A.
ENSURE all RCPs are secured.
B.
ENSURE Pressurizer Spray )T between the PZR and Auxiliary Spray fluid
<320°F AND is recorded IAW S1.OP-DL.ZZ-0002(Q), Control Room Logs Mode 5, 6 and Defueled (T/S 4.4.9.1.1).
C.
ENSURE SC.OP-DL.ZZ-0012(Q), Pressurizer Heatup/Cooldown Log is maintained during cooldown.
D.
PLACE all Pressurizer BACKUP AND CNTRL GRP HEATERS to OFF.
E.
ENSURE 1CV79, Charging Line Stop Valve is CLOSED.
F.
OPEN 1CV75, Pressurizer Auxiliary Spray Stop Valve.
G.
CLOSE 1CV77, Charging Line Stop Valve.
H.
When RCS pressure is reduced to <100 psig, PERFORM the following:
1.
CLOSE 11-14CV104, RCP Seal Water Return Stop.
2.
ENSURE 1CV114, Seal Water Bypass is CLOSED.
3.
Direct a second Operator to PERFORM Independent Verification that 1CV114, Seal Water Bypass is CLOSED.
IV Signature Date I.
RAISE Pressurizer level by adjusting Charging and Letdown flow.
J.
Prior to reducing RCS pressure <25 psig, OPEN 1PR1 and 1PR2.
K.
CONTINUE raising Pressurizer level by adjusting Charging flow until Pressurizer overflows and an increase in level is observed in PRT.
L.
When Pressurizer cooldown temperature is obtained:
1.
OPEN 1CV77.
2.
CLOSE 1CV75.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 30 of 47 Rev. 33 5.1.56 IF a vent path through the pressurizer safety drains is required (this vent path does NOT satisfy Technical Specification requirements),
THEN:
A.
REFER to P&L Step 3.17 prior to opening any RCS Vent Path.
B.
CONNECT temporary hose from 1PR67 and 1PR68, LOOP SEAL DRAIN LINE to the Containment Bioshield annulus.
C.
CLOSE 1PR1 and 1PR2 AND PLACE in AUTO.
D.
IF required to remove hydrogen or gaseous activity atmosphere, THEN INITIATE S1.OP-SO.PZR-0001(Q), Purging the PRT; Section for Purging PRT of Hydrogen or Xenon.
E.
ENSURE POPS is ARMED IAW S1.OP-SO.PZR-0004(Q),
Pressurizer Overpressure Protection Operation.
F.
ADJUST Charging flow as required to minimize pressure at 1PR67 and 1PR68, LOOP SEAL DRAIN LINE.
G.
CLOSE 1PS22, PZR LIQUID SAMP V.
H.
Slowly OPEN 1PR67 AND 1PR68, LOOP SEAL DRAIN LINE AND MONITOR for flow.
I.
When PZR pressure is relieved through the hose, CLOSE 1PR67 AND 1PR68, LOOP SEAL DRAIN LINE.
J.
DISCONNECT temporary hose from 1PR67 and 1PR68, LOOP SEAL DRAIN LINE.
K.
OPEN 1PS22, PZR LIQUID SAMP V.
L.
OPEN 1PS32 AND 1PS33, PZR SPRAY LINE VENT.
M.
IF additional vent paths are required to support PZR draining, THEN ESTABLISH any of the following vent paths:
OPEN 1PS21 AND 1PS7, PZR VENT
OPEN 1PR19, PZR SPRAY V LOOP SEAL DR VENT AND 1PR69, LOOP SEAL DR LN DR VT ISO
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 31 of 47 Rev. 33 NOTE Gas Decay Tank (GDT) volume is always an issue during an outage since numerous VCT purges are required to degas the RCS. To conserve GDT volume, the RCDT Pumps may be aligned to the Waste Holdup System during RCDT/PRT purge evolutions.
5.1.57 IF RCDT Pump discharge is to be aligned to the WHUT inlet header at the discretion of the SM/CRS, THEN INITIATE S1.OP-SO.WL-0005(Q), Reactor Coolant Drain Tank Operation to align the RCDT pump discharge to WHUT.
5.1.58 IF Pressurizer level is to be lowered after PRT purge is completed, THEN:
A.
IF required to remove hydrogen or gaseous activity atmosphere, THEN PERFORM S1.OP-SO.PZR-0001(Q), Purging the PRT; Section for Purging PRT of Hydrogen or Xenon.
B.
DRAIN PRT to 10% IAW S1.OP-SO.PZR-0003(Q),
Pressurizer Relief Tank Operation.
C.
ESTABLISH RCS vent path IAW S1.OP-SO.PZR-0006(Q), RCS Venting.
5.1.59 IF PZR Liquid/Vapor temperature is #210°F,
[CAPR 70090887]
THEN request Maintenance to PROVIDE COLD SCALED LEVEL indication for at least one of the three hot calibrated PZR Level Channels (Refer to Step 3.19).
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 32 of 47 Rev. 33 CAUTION [CAPR 70090887]
Refer to Exhibit 1, Pressurizer Level Channels, for channel behavior based on pressurizer water temperature.
The expected PZR COLD CAL level value in SPDS (U1LT0462S)
[70090500]
in a water solid condition is <105%. An indicated level of $105% is highly suspect.
Maintenance is to be notified to troubleshoot the apparent failure of the instrument whenever the indicated value is not as expected.
When
.528 gallons has been drained from the RCS, the PZR COLD CAL level should indicate.95% (PZR at.200°F) (Actual level at 100%).
When
.2500 gallons has been drained from the RCS, the PZR COLD CAL level should indicate.82% (PZR at.200°F) (Actual level at.84%).
At
.60% COLD CAL level, PZR Level Channels I, II, & III should begin to come on scale at.98.8% (.61.0% on COLD SCALED LEVEL indication).
At
.20% PZR Level Channels I, II, & III should approximate the COLD CAL Level, (crossover). PZR Level Channels I, II, & III are normally off scale low at
.11.5% COLD CAL level.
The PZR volume from a water solid condition to 25% level is.9,978 gallons.
There is.12,600 gallons between the upper and lower level taps and.528 gallons from the upper level tap to a water solid condition.
Maintain a positive nitrogen pressure in the PRT until venting is performed in Step 5.1.65.
5.1.60 LOWER Pressurizer level to on scale indication as follows:
A.
ENSURE Maintenance has completed
[CAPR 70090887]
SC.IC-GP.RC-0092(Q), Backfilling LT462 Cold Pressurizer Level Reference Leg.
B.
ENSURE PZR COLD CAL Level in SPDS (U1LT0462S) is
[70090500]
indicating <105%.
C.
ENSURE PZR COLD CAL Level in SPDS (U1LT0462S) is indicating as expected. Refer to Exhibit 1, Pressurizer Level Channels, for channel behavior based on pressurizer water temperature.
D.
RECORD the following in Attachment 2, Sections 2.0 and 3.0:
Inservice CVC HUT Level (Initial)
VCT Level (Initial)
(step continued on next page)
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 33 of 47 Rev. 33 5.1.60 (continued)
NOTE The expected response of the PZR COLD CAL level channel shall be confirmed after.2500 gallons has been drained from the RCS. The Charging / Letdown Flow mismatch and the change in CVC HUT level will be initially used to determine the RCS volume drained.
This change in RCS volume is compared to actual PZR COLD CAL level and other relevant parameters in Attachment 2, Section 4.0, to confirm the expected response.
E.
CALCULATE the time to drain 2500 gallons from the RCS based on the desired Letdown / Charging Flow Mismatch ) gpm (PZR drain down rate) in Attachment 2, Section 1.0.
F.
ADJUST Charging and Letdown flow to obtain desired drain down rate.
G.
RECORD the following in Attachment 2, Section 1.0:
Tim e (Start)
Letdown Flow (FI134)
Charging Flow (FI128B)
Mism atch () gpm)
NOTE Refer to Exhibit 1, Pressurizer Level Channels, for PZR Level Channel behavior based on pressurizer water temperature.
H.
When.2500 gallons has been drained from the RCS based on the time (minutes) calculated in Attachment 2, Section 1.0, PERFORM the following to confirm the expected response of Pressurizer Level (COLD CAL) indication:
1.
ADJUST Charging and Letdown flow to stabilize PZR level.
2.
COMPLETE Attachment 2, Sections 1.0, 2.0, and 3.0.
I.
ADJUST Charging and Letdown flow to obtain desired drain down rate.
J.
When the PZR is at the desired level ($25%, COLD CAL) as directed by SM/CRS, STABILIZE Pressurizer level by adjusting Charging and Letdown flow.
K.
IF PZR level is to be lowered to <25% (COLD CAL),
[CAPR 70090887]
THEN INITIATE S1.OP-SO.RC-0005(Q),
Draining the RCS Reactor Coolant System to $101 Ft Elevation.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 34 of 47 Rev. 33 5.1.61 IF 1PS32 and 1PS33 were opened in Step 5.1.56L, THEN:
A.
ENSURE RCS vent path IAW S1.OP-SO.PZR-0006(Q), RCS Venting.
B.
CLOSE 1PS32 AND 1PS33, PZR SPRAY LINE VENT.
5.1.62 IF additional vent paths were required to support PZR draining, THEN ISOLATE the following vent paths:
CLOSE 1PS21 AND 1PS7, PZR VENT
CLOSE 1PR19, PZR SPRAY V LOOP SEAL DR VENT AND 1PR69, LOOP SEAL DR LN DR VT ISO 5.1.63 IF Pressurizer cooldown was performed, THEN DISCONTINUE monitoring of parameters listed in, Section 4.0, at the discretion of the SM/CRS.
5.1.64 IF required to remove hydrogen or gaseous activity atmosphere from RCDT, THEN INITIATE PURGE of RCDT of Hydrogen IAW S1.OP-SO.WL-0005(Q),
Reactor Coolant Drain Tank Operation.
5.1.65 IF PRT is to be vented to the containment atmosphere, THEN PERFORM venting IAW S1.OP-SO.PZR-0003(Q), PRT Operation.
5.1.66 IF RCS temperature will be reduced to <145°F, THEN REMOVE Reactor Shield Ventilation and Nozzle Support Fans from service IAW S1.OP-SO.CBV-0001(Q), Containment Ventilation Operation.
NOTE The ability to reduce Reactor Coolant System or Steam Generator metal temperature is hindered when RCS water inventory is reduced. As a result of this, upcoming outage activities, such as the removal of S/G primary manway covers, should be reviewed prior to reducing RCS water inventory.
[70034006]
5.1.67 IF draining the RCS is required, THEN INITIATE S1.OP-SO.RC-0005(Q), Draining the Reactor Coolant System to
$101 Ft Elevation.
5.1.68 IF shutdown is for refueling, THEN INITIATE S1.OP-IO.ZZ-0007(Q), Cold Shutdown to Refueling.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 35 of 47 Rev. 33 5.2 Completion And Review 5.2.1 COMPLETE Attachment 3, Sections 1.0 and 2.0, AND FORWARD this procedure to the SM/CRS for review and approval.
5.2.2 SM/CRS PERFORM the following:
A.
REVIEW this procedure with Attachments 1-3 for completeness and accuracy.
B.
COMPLETE Attachment 3, Section 3.0.
C.
IF this procedure is terminated prior to completion, THEN NOTE reason, date and time of termination on, Section 1.0.
D.
IF this procedure is completed successfully, THEN FORWARD completed procedure, including any terminated procedure, if applicable, to Operations Staff.
END OF PROCEDURE SECTION
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 36 of 47 Rev. 33 6.0 RECORDS 6.1 Retain the following IAW RM-AA-101, Records Management Program:
Attachments 1-3 Completed Heatup/Cooldown Plots performed IAW S1.OP-TM.ZZ-0001(Q)
7.0 REFERENCES
7.1 Updated Final Safety Analysis Report 7.1.1 Section 4, Reactor 7.1.2 Section 5, Reactor Coolant System and Connected Systems 7.1.3 Section 7, Instrumentation and Controls 7.1.4 Section 8, Electrical Systems 7.1.5 Section 9, Auxiliary Systems 7.1.6 Section 15.1, Condition 1, Normal Operation and Operational Transients 7.2 Technical Specifications - Unit 1 7.2.1 3.1.1.2, Shutdown Margin - TAVG #200°F 7.2.2 3.3.1.1, Reactor Trip System Instrumentation 7.3 Drawings 7.3.1 205201, No. 1 Unit Reactor Coolant System 7.3.2 205240, No. 1 Unit Waste Disposal - Gas 7.3.3 205232, No. 1 Unit Residual Heat Removal 7.3.4 205234, No. 1 Unit Safety Injection System 7.3.5 205231, No. 1 Unit Component Cooling System 7.3.6 205228, No. 1 Unit Chemical and Volume Control System 7.3.7 205233, No. 1 Unit Spent Fuel Cooling 7.4 Others 7.4.1 ATS Item DES-DEF-90-01584, Cooldown Step Change Concerns 7.4.2 DCP 80029150, Unit CVCS Cross-Tie 7.4.3 INPO SOER 88-3, Losses of RHR With Reduced Reactor Vessel Water Level 7.4.4 LER 272/96-008, Failure to Meet Technical Specifications Requirements While in Mode 5 for Natural Circulation.
7.4.5 PSEG VTD 304209, Westinghouse Precautions, Limitations, and Setpoints for Nuclear Steam Supply Systems 7.4.6 NRC INFO 87-23, Loss Of Decay Heat Removal Function At PWRs With Partially Drained Reactor Coolant Systems 7.4.7 SC-R200-MSE-0738-1, Mid-Loop Operation, 10/10/88 7.4.8 WCAP-11916, 7-88, Loss Of RHR While The RCS Is Partially Filled
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 37 of 47 Rev. 33 7.4.9 WCAP-13588, Operating Strategies for Mitigating Pressurizer Insurge/Outsurge Transients.
7.4.10 WCAP-14950, Mitigation and Evaluation of Pressurizer Insurge/Outsurge Transients.
7.4.11 Westinghouse Tech. Bulletin NSD-TB-92-02-R0, Recommended PZR hydrogen concentration limit during RCS oxygenation process.
7.4.12 Westinghouse Owners Group Abnormal Response Guideline WOG-ARG-1, Loss of RHR While Operating at Mid-Loop Conditions 7.4.13 PR980929096 - BPCA #19, Cooldown Flexibility with RCS Below 200°F 7.4.14 70011541, MSIV Operability in Mode 3 7.4.15 LRI-00-0439, Maintaining the MS167 Valves Open During Plant Cooldown (11/09/00) 7.4.16 DCP 80065300, Restoration Of The Positive Displacement Pump As The Normal Charging Pump [Safety Evaluation S003-002]
7.5 Cross-References 7.5.1 Technical Specifications:
A.
4.4.9.1.1, RCS Pressure\\Temperature Limits Surveillance B.
4.4.9.2, Reactor Coolant System Pressurizer Surveillance C.
4.4.9.3.1, RCS Overpressure Protection Systems Surveillance D.
4.5.2.i, ECCS Subsystems - TAVG $350°F
7.5.2 Procedures
SC.IC-TI.CVC-0001(Q), CV55 Flow Adjustment SC.CH-AD.RC-0413(Q), Chemical Addition to Primary System SC.CH-TI.ZZ-0544(Q), Reactor Startup, Shutdown, and >15% Power Change Surveillance Requirement.
S1.IC-FT.RCP-0070(Q), 1PT403 Reactor Coolant System Hot Leg Pressure Channel II S1.IC-FT.RCP-0071(Q), 1PT405 Reactor Coolant System Hot Leg Pressure Channel I S1.IC-ST.RHR-0014(Q), RHR Interlock and Alarm Verification S1.OP-DL.ZZ-0001(Q), Control Room Logs S1.OP-DL.ZZ-0002(Q), Control Room Logs Modes 5, 6 and Defueled S1.OP-DL.ZZ-0006(Q), Primary Plant Log S1.OP-DL.ZZ-0014(Q), Shift Routines S1.OP-IO.ZZ-0007(Q), Cold Shutdown to Refueling S1.OP-PT.CAN-0001(Q), Containment Walkdown (step continued next page
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 38 of 47 Rev. 33 7.5.2 (continued)
S1.OP-SO.AF-0001(Q), Auxiliary Feedwater System Operation S1.OP-SO.AR-0001(Z), Condenser Air Removal System Operation.
S1.OP-SO.CBV-0001(Q), Containment Ventilation Operation S1.OP-SO.CN-0001(Q), Condensate System Operation S1.OP-SO.SG-0003(Q), Maintaining Steam Generators in Wet Layup S1.OP-SO.CVC-0002(Q), Charging Pump Operation S1.OP-SO.CVC-0005(Q), Boric Acid Preparation And Transfer S1.OP-SO.CVC-0006(Q), Boron Concentration Control S1.OP-SO.CVC-0011(Q), RCS Degassification S1.OP-SO.GEN-0003(Z), Main Generator Gas System Operation S1.OP-SO.GS-0001(Q), Turbine Gland Sealing Steam System Operation S1.OP-SO.MS-0002(Q), Steam Dump System Operation S1.OP-ST.MS-0003(Q), Steamline Isolation and Response Time Testing S1.OP-SO.PZR-0001(Q), Purging the PRT S1.OP-SO.PZR-0003(Q), Pressurizer Relief Tank Operation S1.OP-SO.PZR-0004(Q),
Pressurizer Overpressure Protection Operation S1.OP-SO.PZR-0005(Q), Pressurizer Pressure Control System Operation S1.OP-SO.RC-0001(Q), Reactor Coolant Pump Operation S1.OP-SO.RC-0005(Q), Draining the RCS to $101 Feet Elevation S1.OP-SO.RCS-0001(Q), Rod Control System Operation S1.OP-SO.RHR-0001(Q), Initiating RHR S1.OP-SO.RPS-0008(Q),
Establishing/Removing Auto SI Block S1.OP-SO.RPS-0009(Q), Installation / Removal of AFW Start Function S1.OP-SO.WL-0005(Q), Reactor Coolant Drain Tank Operation S1.OP-ST.SJ-0020(Q), Periodic Leakage-RCS Pressure Isolation Valves S1.OP-TM.ZZ-0001(Q), RCS Pressure/Temperature Curves S1.RE-RA.ZZ-0012(Q),
Figures S1.RE-RA.ZZ-0016(Q), Curve Book 7.6 Commitments 7.6.1 C0326 - INPO OMR - 312 7.6.2 CO565 - ASME Code Case N514 7.6.3 C0569 - NSO INCI 94-124 7.6.4 C0609 - NRC INFO 95-35 7.6.5 C0565 - PSLT NLR-N94229 and ASME Code Case N-514 via Reg Guide 1.147, Rev. 12, dated 5/99
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 39 of 47 Rev. 33 ATTACHMENT 1 (Page 1 of 1)
Page ____ of ____
RCS MAKEUP SOURCE 1.0 Alignment CAUTION T/S 3.1.2.6 minimum RWST level in Modes 1-4 is $40.5 ft (364,500 gallons).
T/S 3.1.2.5 minimum RWST level in Modes 5-6 is $1.9 ft (37,000 gallons).
A constant Pressurizer outsurge and relatively constant Pressurizer level should be maintained during makeup. Rapid makeup rates may cause a Pressurizer insurge. Refer to P&L Step 3.6.1.
Limit the number of Motor Operated Valve (MOV) full valve cycles to 3 in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. A full valve cycle is defined as traveling from one position to the opposite position, then back to original position.
[C0326]
OPEN 1SJ1 OR 1SJ2.
2.
CLOSE 1CV40 OR 1CV41.
3.
COMPLETE Section 2.0 of this Attachment.
4.
When desired VCT level is obtained (CV35 AUTO divert to CVC HUT at 77%),
ALIGN to VCT Source.
1.
OPEN 1CV40 AND 1CV41 2.
CLOSE 1SJ1 AND 1SJ2 3.
COMPLETE Section 2.0 of this Attachment.
4.
When additional VCT makeup is desired (VCT AUTO makeup at 14%),
ALIGN to RWST Source.
2.0 Valve Position And Independent Verification Valve Position Initials Date/Time IV Date/Time 1CV40 1CV41 1SJ1 1SJ2
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 40 of 47 Rev. 33 ATTACHMENT 2
[CAPR 70090887]
(Page 1 of 2)
PRESSURIZER COLD CALIBRATED LEVEL INDICATION (LI-462) 1.0 Letdown / Charging Flow Mismatch TIME TO DRAIN 2500 GALLONS 2500 gallons
÷
) gpm
=
minutes 2500 gallons ÷ Desired Letdown / Charging Flow Mismatch () gpm) = minutes Parameter Flow Time Gallons (1)
Start Stop Letdown Flow FI134 Charging Flow FI128B
) minutes Mismatch
) gpm (1)
The combined change in CVCS HUT AND VCT volume should be within 500 gallons of the Letdown / Charging Flow Mismatch volume, otherwise Shift Managers concurrence is required to continue with the pressurizer drain down.
2.0 CVCS HUT Level Change Parameter Level Gallons (2)
CVCS HUT Level Initial Final Level Change
)
(2)
Obtain gallons using S1.OP-TM.ZZ-0002(Q), Tank Capacity Data.
3.0 Volume Control Tank (VCT) Level Change Parameter Level Gallons (3)
VCT Level Initial Final Level Change
)
(3)
Obtain gallons using S1.OP-TM.ZZ-0002(Q), Tank Capacity Data.
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 41 of 47 Rev. 33 ATTACHMENT 2
[CAPR 70090887]
(Page 2 of 2)
PRESSURIZER COLD CALIBRATED LEVEL INDICATION (LI-462) 4.0 Plant Indications Parameters (1)
Control Room Plant Computer SPDS Pressurizer Level COLD CAL (2)(3)
LI462 N/A U1LT0462S Pressurizer Level Channel I LI459 L0480A U1LT0459S Pressurizer Level Channel II LI460 L0481A U1LT0460S Pressurizer Level Channel III LI461 L0482A U1LT0461S VCT Level (3)
LI112 L0112A U1LT0112S Letdown Flow LI134 F0134A U1LT0134S Charging Flow LI128B F0128A U1LT0128S 11 CVCS HUT LA-4145 N/A U1LT0167S 13 CVCS HUT U1LT0170S RVLIS Full Range - Train A (3)(4)
LD-3375 U1LT1311S RVLIS Full Range - Train B LD-3367 U1LT1321S (1)
ENSURE all available plant indications / trends are responding as expected during all pressurizer fill and drain down evolutions.
(2)
REFER to Exhibit 1, Pressurizer Level Channels, for channel behavior based on pressurizer water temperature.
(3)
PLACE Plant Computer and SPDS points on trend prior to performing the associated evolution.
At a minimum, all points are required to be trended with the following stipulations:
Only one of the Hot Calibrated Pressurizer Level Channels (I, II, or III) is required.
Only one of the RVLIS Full Range Trains (A or B) is required.
Both RVLIS Trains may be excluded from trend with Shift Managers concurrence.
Only the In Service CVC HUT is required.
(4)
ENSURE available RVLIS Full Range indications remain >100%
during the entire draindown to $25% in the Pressurizer.
[CAPR 70090887]
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 42 of 47 Rev. 33 ATTACHMENT 3 (Page 1 of 2)
Page ____ of ____
COMPLETION SIGN-OFF SHEET 5.0 COMMENTS (INCLUDE procedure deficiencies and corrective actions.)
S1.OP-IO.ZZ-0006(Q)
Salem 1 Page 43 of 47 Rev. 33 ATTACHMENT 3 (Page 2 of 2)
COMPLETION SIGN-OFF SHEET 6.0 SIGNATURES Print Initials Signature Date INDEPENDENT VERIFICATION 7.0 SM/CRS FINAL REVIEW AND APPROVAL This procedure with Attachments 1-3 are reviewed for completeness and accuracy.
All deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section.
Signature:__________________________________________________
Date:______________
SM/CRS
100 90
~ 80 G;)<
==-
70 G;)<
---I -
60 G;)<
- s 50 c:n c:n G;)<
40
/
/
/
/
v
./
D....
cu 30
- s: -
<.:It 20
<C 10
/
//
V
/' ~
/
v~
~
/'
/
/'A ~
~
~
~
o o
10 20 Salem 1 EXIDBIT 1 (page 1 of 4)
PRESSURIZER LEVEL CHANNELS (COLD CALIBRATED CHANNEL) 700F 600F S 1.oP-Io.zz-0006(Q)
[CAPR 70090887]
500F 400F 300F 200F
/
/'
.,.-/
/
/" v/ ~
/
/'
.,/'
/
./
/
/"
/
V
/'
././"
/
/'
./ r
.,.-V //
/
V V
/" v.......... ~
/
/"
~
/
~
v-----
V
./
/
/
~
~
V
./ // ~
~
/'
/L ~
~
/./ /~
~
/
/
V~ ~
/'" ~
~
~
P
.11
~
,.. c; ; *..
C;;.I -......
30 40 50 60 70 Indicated Pressurizer Level (0/0)
Page 44 of 47
/"
./ v~
~
140F
./" /"/ ~
// ~
~
II'"
1_'
80 90 100 Rev. 33
100 90
~ 80
<SI;!'
~ 70 CD
---I -
60 CD
- s 50 ton ton CD 40
/'" ".-
// ~
~
D....
cu 30
- s -
c;.>
20
<C 10 b--:: k:;; ~
~ ~
~
~
~
~
~
0 o
20 40 Salem 1 EXIDBITl (page 2 of 4)
PRESSURIZER LEVEL CHANNELS (HOT CALIBRATED CHANNELS)
S 1.oP-Io.zz-0006(Q)
[CAPR 70090887]
500F 350F 212F 100F
/" V
./'
",V
/'"
V V
k--':: ~
V V
"..,.".; ~
- t,
I<"" /.. ?
/'
"...".".. ~
~
I-
/" V
,./ ~
~
V V
/' '" V v~.p V
".- ~
~
J&,e;..,.-
~
~
II~,.. -
-.. 1,1 fir.
60 80 100 120 140 Indicated Pressurizer Level (%)
Page4S of 47 L.....-:
v 1-'"'
".-V
/ '/-
/
V V V v
~.....
..... 1 J 160 180 200 Rev. 33
100 90
~ 80
= -cv 70 Cl)
--I 10-60 cv 10-50
=:::s:
fJ) fJ) 40 cv 10-0..
30 C'G
=:::s:
20 c.>
c::(
10 ~ --
/
0 V' o
Salem 1 EXHIBIT 1 (Page 3 of 4)
PRESSURIZER LEVEL CHANNELS (COLD AND HOT CALIBRATED CHANNELS FOR 140°F)
~.:Ii COl.;':
\\?
~
/""
/'"
~
/""
/""
/""
f-"'
.:Ii
.. !10.. s.w....
lCev;, fl 11:..st'-' ~
"."./"
l.----
~ ll-Cal
... p; ~a.-4 V"
f-"
l~l:'-'-
,,/ ----
~ ----
~ -
~
"7' V
10 20 30 40 50 60 70 80 Indicated Pressurizer Level (%)
Page 46 of 47
-~ -_.. ------.-._---
S 1.oP-Io.zz-0006(Q)
[CAPR 70090887]
~
.",/
~
~ -
r-
"'..{
~D~lIl )fAf
,611, 90 100 Rev. 33
EXHIBIT 1 (Page 4 of 4)
S 1.oP-Io.zz-0006(Q)
PRESSURIZER LEVEL CHANNELS
[CAPR 70090887]
Bot Oalibrated Channels On Scale PRESSURIZER LEf/'EL COLD COIVDITIOIVS -100°F COLD CAL Elevation Channell. U. JU Galhms 100.0%
15:2.1ft 180.0%
1,3,200 gal.
75.0%
141.8ft 129.3%
10,.000 gaL
- _~,~_
.'t[ _. or _
"._,*r.:_ ~",_.
60.0%
13.5.2ft 98.$%
8,160 gal.
- &la:tm(92~t)
- fU:4!n.t (1~~).
.. _ 'f~I!!l~Jti()~.'l'Q lQmtit\\dQ~ P~f?~4p.l!.. _.
IDa%m(17%)
If' ill
- c.
II<
ill 56.7%
45.8%
25.(')%
19.7%
133.8ft 129.(lft 119J)fl 117.6ft o.()%
10<6 *. 9ft 104.34ft Salem 1 Page 47 of 47 92.1%
7,744 gal.
70.0%
6,371 gal.
27.8%
3.,75(') gal.
17.0%
3,(')32 gal,
- 2:7%
,},860 gal.
-23.0%
601) gal.
Rev. 33