ML061240266
| ML061240266 | |
| Person / Time | |
|---|---|
| Site: | Monticello  (DPR-022) |
| Issue date: | 06/05/2006 |
| From: | Plant Licensing Branch III-2 |
| To: | |
| beltz T, NRR/DORL/LPL3-1, 301-415-3049 | |
| Shared Package | |
| ML061240241 | List: |
| References | |
| TAC MC7505, TAC MC7597, TAC MC7598, TAC MC7599, TAC MC7600, TAC MC7601, TAC MC7602, TAC MC7603, TAC MC7604, TAC MC7605, TAC MC7606, TAC MC7607, TAC MC7608, TAC MC7609, TAC MC7610, TAC MC7611, TAC MC8887 | |
| Download: ML061240266 (21) | |
Text
Table LA - Removed Detail Changes Monticello Page 1 of 21 ATTACHMENT 5 ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type 1.0 LA.1 1.0.Y The CTS 1.0.Y definition of Shutdown states that with the reactor mode switch in Shutdown, "a reactor scram is initiated...directly from the mode switch. The scram can be reset after a short time delay." ITS Table 1.1-1 does not include this additional design information.
3.3.3.1 Bases ITS 5.5.9 1
2.0 None None None None None 3.0 LA.1 4.0.B CTS 4.0.B states that the purpose of the 25% extension of the specified surveillance interval is "to accommodate normal test schedule." ITS SR 3.0.2 does not include this detail.
Bases ITS 5.5.9 3
3.1.1 LA.1 3.3.A.1 CTS 3.3.A.1 states, in part, that the core loading shall be limited to that which can be made subcritical "in the most reactive condition during the operating cycle." ITS LCO 3.1.1 requires SDM to be met. This changes the CTS by relocating the details that the core loading shall be limited to that which can be made subcritical "in the most reactive condition during the operating cycle" to the ITS Bases in the form of a discussion about how core reactivity varies during the fuel cycle and that the SDM verification should consider this behavior.
Bases ITS 5.5.9 3
3.1.1 LA.2 4.3.A.1 CTS 4.3.A.1 states, in part, "Sufficient control rods shall be withdrawn... to demonstrate" reactivity margin is within the specified limit. ITS SR 3.1.1.1 states "Verify SDM to be within limits," but does not provide similar details of how to perform the verification. This changes the CTS by relocating the test method "Sufficient control rods shall be withdrawn to demonstrate" reactivity margin to the ITS Bases.
Bases ITS 5.5.9 3
3.1.2 LA.1 3.3.E, 4.3.E CTS 3.3.E states, in part, "At a specific steady state base condition" the reactor actual control rod inventory will be periodically compared to a "normalized computed" prediction of the inventory. CTS 3.3.E also implies that the reactivity difference shall be shall be within +/- 1% )k/k. CTS 4.3.E states, in part, that the actual rod inventory shall be compared to a "normalized computed" prediction of inventory and that "These comparisons will be used as base data for reactivity monitoring during subsequent power operation throughout the fuel cycle." Furthermore, the actual rod configuration will be compared to the configuration expected "based upon appropriately corrected past data." ITS LCO 3.1.2 states "The reactivity difference between the monitored control rod inventory and the predicted control rod inventory shall be within +/- 1% )k/k." ITS SR 3.1.2.1 states "Verify core reactivity difference between the monitored control rod inventory and the predicted control rod inventory is within +/- 1% )k/k." This changes the CTS by relocating these details for performing the reactivity anomaly Surveillance to the ITS Bases.
Bases ITS 5.5.9 3
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 2 of 21 ATTACHMENT 5 3.1.3 LA.1 3.3.A.2.(a),
3.3.B.1 CTS 3.3.A.2.(a) states, in part, that the "directional control valves" for inoperable control rods shall be disarmed "electrically." CTS 3.3.B.1 states, in part, that each control rod shall be coupled to its drive or completely inserted and the "directional control valves" disarmed "electrically." ITS 3.1.3 ACTION A covers the condition of one withdrawn control rod stuck. ITS 3.1.3 Required Action A.2 states "Disarm the associated control rod drive (CRD)." ITS 3.1.3 ACTION C covers the condition of one or more control rods inoperable for reasons other than a stuck rod. ITS 3.1.3 Required Action C.2 states "Disarm the associated CRD." Neither of these two Required Actions provides specific details of how to disarm the CRD. This changes the CTS by relocating the details that the "directional control valves" are disarmed "electrically" to the ITS Bases.
Bases ITS 5.5.9 3
3.1.5 LA.1 3.3.D CTS 3.3.D states, in part, that if a control rod with an inoperable accumulator is inserted full-in and either its "directional control valves are electrically "disarmed" or it is hydraulically isolated," it shall not be considered to have an inoperable accumulator. ITS 3.1.3 ACTION C covers the compensatory actions for one or more inoperable control rods (control rods inoperable as a result of an inoperable accumulator are covered by this condition when declared inoperable) ITS 3.1.3 Required Action C.2 states "Disarm the associated CRD," but does not provide the specific details of how to disarm the CRD. This changes the CTS by relocating the details that the "directional control valves are electrically" disarmed "or it is hydraulically isolated" to the ITS Bases.
Bases ITS 5.5.9 3
3.1.6 LA.1 3.3.B.3.(a)
CTS 3.3.B.3.(a) states "Control rod withdrawal sequences shall be established so that the maximum calculated reactivity that could be added by dropout of any increment of any one control blade will not make the core more than 1.3% )k supercritical." ITS LCO 3.1.6 states "OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS)." This changes the CTS by relocating the details of the system design of control rod withdrawal sequences to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 3 of 21 ATTACHMENT 5 3.1.7 LA.1 4.4.A.2.a, 4.4.A.2.b CTS 4.4.A.2.a states "Manually initiate" one of the two standby liquid control systems "and pump demineralized water" into the reactor vessel. It further states that "This test checks explosion of the charge associated with the tested system, proper operation of the valves" and that both SLC subsystems shall be tested "and inspected, including each explosion valve."
CTS 4.4.A.2.b states "Explode one of the primer assemblies manufactured in the same batch to verify proper function. Then install, as a replacement, the second primer assembly in the explosion valve of the system tested for operation." ITS SR 3.1.7.8 requires verification of flow through one SLC subsystem from pump into reactor pressure vessel. This changes the CTS by relocating the above procedural details concerning performance of the flow path test to the ITS Bases.
Bases ITS 5.5.9 3
3.1.7 LA.2 3.4.B.1, Figure 3.4-1 CTS 3.4.B.1 states that Equation 1 is consistent with the "Original Design Basis" and Equation 2 is consistent with the "ATWS Design Basis."
CTS Figure 3.4-1 specifies that the curves are based on "B-10 Enrichments Greater than 55.0%." ITS Figure 3.1.7-1 includes the same requirements as CTS Figure 3.4-1, except the detail concerning the B-10 enrichment. ITS Table 3.1.7-1 includes Equation 1 and Equation 2, however the statements concerning the "Original Design Basis" and "ATWS Design Basis" are not included. This changes the CTS by relocating these details to the ITS Bases.
Bases ITS 5.5.9 1
3.1.7 LA.3 4.4.B.1 CTS 4.4.B.1 requires the boron enrichment to be determined by "laboratory analysis." ITS SR 3.1.7.10 does not specify the method that shall be used to determine the B-10 enrichment. This changes the CTS by relocating the procedure detail "laboratory analysis" to the ITS Bases.
Bases ITS 5.5.9 3
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 4 of 21 ATTACHMENT 5 3.2.1 LA.1 3.11.A CTS 3.11.A specifies the APLHGR limits for "two loop" and "one loop" operation.
For two loop operation, the APLGHR limits are specified "for each type of fuel as a function of average planar exposure."
For one loop operation, the APLGHR limits are specified "for each type of fuel" and shall not exceed the most limiting of
- a. The above values multiplied by 0.80 for GE11 and GE12 fuel and 0.90 for GE14 fuel, or
- b. The above values multiplied by the appropriate flow and power dependent correction factors provided in the Core Operating Limits Report."
In addition, CTS 4.11.A states that the APLHGR "for each type of fuel as a function of average planar exposure" shall be determined.
ITS 3.2.1 states "All APLHGRs shall be less than or equal to the limits specified in the COLR." and ITS SR 3.2.1.1 requires verification that all APLGHRs are less than or equal to the limits specified in the COLR.
This changes the CTS by relocating to the Bases the details that the APLHGR limits are specified for one loop and two loop operation, that the two loop APLHGR limits are specified for each type of fuel as a function of average planar exposure, and that the single loop APLHGR limits for each type of fuel shall not exceed the most limiting of
- a. the above values multiplied by 0.80 for GE11 and GE12 fuel and 0.90 for GE14 fuel, or
- b. the above values multiplied by the appropriate flow and power dependent correction factors provided in the Core Operating Limits Report Bases ITS 5.5.9 3
3.2.1 LA.2 3.11.A CTS 3.11.A states "When hand calculations are required, the APLHGR for each type of fuel as a function of average planar exposure shall not exceed the limiting value for the most limiting lattice (excluding natural uranium) provided in the Core Operating Limits Report." ITS LCO 3.2.1 states "All APLHGRs shall be less than or equal to the limits specified in the COLR."
This changes the CTS by relocating the hand calculation APLHGR limits to the COLR.
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 5 of 21 ATTACHMENT 5 3.2.1 LA.3 3.11.A CTS 3.11.A states that if at any time during power operation it is determined that the APLHGR limiting condition for operation is being exceeded, "action shall be initiated within 15 minutes to restore operation to within the prescribed limits." ITS 3.2.1 does not include this 15 minute action. This changes the CTS by relocating the procedural detail that "action shall be initiated within 15 minutes to restore operation to within the prescribed limits" to the Bases in the form of a discussion that "prompt action should be taken to restore the APLHGR(s) to within the required limits."
Bases ITS 5.5.9 3
3.2.2 LA.1 3.11.C CTS 3.11.C states that if at any time during power operation it is determined that the limiting value for MCPR is being exceeded, "action shall be initiated within 15 minutes to restore operation to within the prescribed limits." ITS 3.2.2 does not include this 15 minute action. This changes the CTS by relocating the procedural detail that "action shall be initiated within 15 minutes to restore operation to within the prescribed limits" to the Bases in the form of a discussion that "prompt action should be taken to restore the MCPR(s) to within the required limits."
Bases ITS 5.5.9 3
3.2.3 LA.1 3.11.B CTS 3.11.B states that if at any time during power operation it is determined that the limiting value for LHGR limiting condition for operation is being exceeded, "action shall be initiated within 15 minutes to restore operation to within the prescribed limits." ITS 3.2.3 does not include this 15 minute action. This changes the CTS by relocating the procedural detail that "action shall be initiated within 15 minutes to restore operation to within the prescribed limits" to the Bases in the form of a discussion that "prompt action should be taken to restore the LHGR(s) to within the required limits."
Bases ITS 5.5.9 3
3.3.1.1 LA.1 3.1.A CTS 3.1.A states that the RPS response time "shall not exceed 50 milliseconds." ITS SR 3.3.1.1.15 requires the RPS RESPONSE TIME to be "within limits." This changes the CTS by relocating the details of the actual response time limit to the ITS Bases.
Bases ITS 5.5.9 1
3.3.1.1 LA.2 3.1.A, 3.1.B, Table 3.1.1, including Note (1)
CTS 3.1.A states that the "minimum number of trip systems" that must be OPERABLE for the RPS Instrumentation is in Table 3.1.1 and CTS 3.1.B provides a Condition for an inoperable trip system; however, no explicit actions are provided for any inoperable trip system. CTS Table 3.1.1 Note (1) states that there shall be two operable or tripped trip systems for each function. In addition, CTS Table 3.1.1 provides a requirement for the "Total No. of Instrument Channels Per Trip System" for each RPS Instrumentation Trip Function. ITS 3.3.1.1 does not include these details. This changes the CTS by moving the information concerning the required number of OPERABLE trip systems and the "Total No. of Instrument Channels per Trip System" to the ITS Bases.
Bases ITS 5.5.9 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 6 of 21 ATTACHMENT 5 3.3.1.1 LA.3 Table 3.1.1 Trip Functions 3.a and 4.a CTS Table 3.1.1 states that the Neutron Flux IRM - High High (Trip Function 3.a) Limiting Trip Setting is < 120/125 of full scale AND "< 20% of Rated Thermal Power." The CTS Table 3.1.1 Flow Referenced Neutron Flux APRM High High (Trip Function 4.a) Limiting Trip Setting provides a flow reference setting as a function of "W" and states "W=percent of recirculation drive flow to produce a core flow of 57.6 x106 lbm/hr." ITS Table 3.3.1.1-1 Function 1.a provides the Allowable Value for the IRM Neutron Flux - High High Function, but does not include the "< 20% of Rated Thermal Power" portion of the Allowable Value. ITS Table 3.3.1.1-1 Function 2 provides the flow referenced equation for the APRM Flow Reference Neutron Flux - High High Function; however, the definition of "W" is not retained. This changes the CTS by moving the details of the definition of "W" and the "20% of Rated Thermal Power" requirement to the ITS Bases.
Bases ITS 5.5.9 1
3.3.1.1 LA.4 Table 3.1.1 Notes (2) and (5)
CTS Table 3.1.1 Note (2) states that a Neutron Flux IRM (Trip Function 3) channel is considered to be OPERABLE if "its detector is fully inserted."
CTS Table 3.1.1 Note (5) states that a Flow Referenced Neutron Flux APRM (Trip Function 4) channel is considered to be operable if "2 LPRM inputs per level and at least a total of 14 LPRM inputs, except that channels 1, 2, 5, and 6 may lose all LPRM inputs from the companion APRM Cabinet plus one additional LPRM input and still be considered operable." ITS 3.3.1.1 does not include these details. This changes the CTS by relocating the details for meeting TS requirements to the ITS Bases.
Bases ITS 5.5.9 3
3.3.1.1 LA.5 Table 3.1.1 Note (8)
CTS Table 3.1.1 Trip Function 8 provides the Limiting Trip Setting for the Scram Discharge Volume High level channels. CTS Table 3.1.1 Note (8) states that the Limiting Trip Setting for the Scram Discharge Volume High Level channels refers to the volume of water in the discharge volume receiver tank and does not include the volume in the lines to the level switches. ITS Table 3.3.1.1-1 Function 7 provides the Allowable Value for this Function and does not include these details. This changes the CTS by relocating the details for meeting TS requirements to the ITS Bases.
Bases ITS 5.5.9 3
3.3.1.1 LA.6 Table 4.1.2 Group column CTS Table 4.1.2 defines the "Group" each RPS Instrumentation Function is assigned. The Table defines two groups. Group A is defined as "Passive type devices" and Group B is defined as "Vacuum tube or semiconductor devices and detectors that drift or lose sensitivity." ITS 3.3.1.1 does not include this information. This changes the CTS by relocating the design details associated with the RPS Instrumentation "Groups" to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 7 of 21 ATTACHMENT 5 3.3.1.1 LA.7 Table 4.1.2 (for APRM), including Note (4)
CTS Table 4.1.2 specifies that the calibration method for the APRM test is a heat balance. CTS Table 4.1.2 Note 4 also states that this test is performed by taking a heat balance and adjusting the APRM to agree with the heat balance. ITS SR 3.3.1.1.2 does not include the method for performing the Surveillance. This changes the CTS by relocating the procedural details for meeting TS requirements to the ITS Bases.
Bases ITS 5.5.9 3
3.3.1.2 LA.1 3.10.B.1 CTS 3.10.B.1 requires SRMs be inserted to normal operating level. ITS 3.3.2.1 does not specify the level to which SRMs are required to be inserted.
This changes the CTS by moving the information concerning the SRM insertion level to the ITS Bases.
Bases ITS 5.5.9 2
3.3.2.1 LA.1 Table 3.2.3 CTS Table 3.2.3 for Rod Block instrumentation Functions includes the column "Total No. of Instrument Channels per Trip System." ITS Table 3.3.2.1-1 does not retain this column. This changes the CTS by moving the information concerning the "Total No. of Instrument Channels per Trip System" column to the ITS Bases.
Bases ITS 5.5.9 1
3.3.2.1 LA.2 Table 3.2.3 Note (5)
CTS Table 3.2.3 Note (5) specifies that the RBM channel is inoperable if there are less than half the total number of normal inputs. ITS Table 3.3.2.1-1 does not retain this information. This changes the CTS by moving the specific conditions of RBM OPERABILITY to the ITS Bases.
Bases ITS 5.5.9 1
3.3.2.1 LA.3 4.3.B.3.(a)(ii),
4.3.B.3.(a)(iii),
4.3.B.3.(a)(iv)
CTS 4.3.B.3.(a)(ii) states that "The rod worth minimizer computer on-line diagnostic test shall be successfully completed." CTS 4.3.B.3.(a)(iii) states that "Proper annunciation of the selection error of at least one out-of-sequence control rod in each fully inserted group shall be verified." CTS 4.3.B.3.(a)(iv) specifies that the rod worth minimizer rod block function be verified "by attempting to withdrawal an out-of-sequence control rod beyond the block point." The ITS does not include these requirements. This changes the CTS by moving the specific details for performing rod worth minimizer testing to the ITS Bases.
Bases ITS 5.5.8 3
3.3.3.1 LA.1 3.14.1 Required Condition D CTS Table 3.14.1 Required Condition D requires immediate initiation of the preplanned alternate method of monitoring the appropriate parameters if the number of OPERABLE channels is less than the minimum number of channels (i.e., both of the channels are inoperable). The ITS does not include this requirement. This changes the CTS by moving this detail to the ITS Bases.
Bases ITS 5.5.9 3
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 8 of 21 ATTACHMENT 5 3.3.3.2 LA.1 4.13.A.2 CTS 4.13.A.2 requires verification that the Alternate Shutdown System panel master transfer switch alarms in the control room when unlocked once per operating cycle. ITS SR 3.3.3.2.2 does not include the specifics of how to functionally test the Alternate Shutdown System panel master transfer switch (i.e., verifies it alarms in the control room when unlocked). This changes the CTS by relocating this specific detail to the ITS Bases.
Bases ITS 5.5.9 3
3.3.3.2 LA.2 3.13.A.3 CTS 3.13.A.3 requires the Alternate Shutdown System panel master transfer switch to be locked in the normal position, except when in use, being tested, or being maintained. ITS 3.3.3.2 does not retain this information. This changes the CTS by moving the specific conditions of Alternate Shutdown System OPERABILITY to the ITS Bases.
Bases ITS 5.5.9 1
3.3.4.1 LA.1 3.2.F, Table 3.2.5, Table 4.2.1 (Recirculation Pump Trip and Alternate Rod Injection)
CTS 3.2.F, CTS Table 3.2.5, and CTS Table 4.2.1 provide requirements for the Alternate Rod Injection Instrumentation. ITS 3.3.4.1 does not include requirements for the Alternate Rod Injection Instrumentation. This changes the CTS by moving the explicit Alternate Rod Injection Instrumentation requirements from the TSs to the Technical Requirements Manual (TRM).
TRM 10 CFR 50.59 6
3.3.4.1 LA.2 Table 3.2.5 CTS Table 3.2.5 specifies the "Minimum No. of Operable or Operating Trip Systems" and "Total No. of Instrument Channels Per Trip System" for the ATWS-RPT Functions. ITS 3.3.4.1 does not include these details. This changes the CTS by moving the information concerning the "Minimum No. of Operable or Operating Trip Systems" and "Total No. of Instrument Channels Per Trip System" to the ITS Bases.
Bases ITS 5.5.9 1
3.3.5.1 LA.1 Tables 3.2.2 (including Notes 4 and 6) and 3.2.8 CTS Table 3.2.2 and CTS Table 3.2.8 specify the "Minimum No. of Operable or Operating Trip Systems" and the "Total No. of Instrument Channels Per Trip System" requirements for the ECCS Instrumentation. CTS Table 3.2.2 Note 4 states that certain instrument channels are shared by both trip systems, and CTS Table 3.2.2 Note 6 states that a shared channel is considered one channel. ITS 3.3.5.1 does not include these details. This changes the CTS by moving the information concerning the "Minimum No. of Operable or Operating Trip Systems," "Total No. of Instrument Channels Per Trip System," and the information that the channels are shared to the ITS Bases.
Bases ITS 5.5.9 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 9 of 21 ATTACHMENT 5 3.3.5.1 LA.2 Table 3.2.2 Function 3 (including Note 2),
Table 4.2.1 (ECCS Instrumentation)
Functions 5 and 7 CTS Table 3.2.2 Function 3 requires the Loss of Auxiliary Power Function to be OPERABLE. CTS Table 3.2.2 Note 2 states that the two channels associated with each trip system consist of a circuit breaker contact and an undervoltage relay. CTS Table 4.2.1 ECCS Instrumentation Function 5 requires a functional test and a calibration of the "Undervoltage Emergency Bus" channels, while Function 7 requires a functional test and calibration of the "Loss of Auxiliary Power" channels. These tests are required each "Refueling Interval." These requirements are not included in ITS 3.3.5.1.
This changes the CTS by moving the explicit Loss of Auxiliary Power requirements from the TSs to the TRM.
TRM 10 CFR 50.59 6
3.3.5.1 LA.3 Table 3.2.8 Function C.1 CTS Table 3.2.8 specifies that the Condensate Storage Tank Low Level (Function C.1) Trip Setting is referenced from "above tank bottom." ITS Table 3.3.5.1-1 Function 3.d does not include this detail. This changes the CTS by moving the information associated with the condensate storage tank level reference point to the ITS Bases.
Bases ITS 5.5.9 1
3.3.5.2 LA.1 Table 3.2.8 CTS Table 3.2.8 specifies the "Minimum No. of Operable or Operating Trip System" and "Total No. of Instrument Channels Per Trip System" requirements for the RCIC System Instrumentation. ITS 3.3.5.2 does not include these details. This changes the CTS by moving the information concerning the "Minimum No. of Operable or Operating Trip System" and "Total No. of Instrument Channels Per Trip System" to the ITS Bases.
Bases ITS 5.5.9 1
3.3.5.2 LA.2 Table 3.2.8 Function C.1 CTS Table 3.2.8 specifies that the Condensate Storage Tank Low Level (Function C.1) Trip Setting is referenced from "above tank bottom." ITS Table 3.3.5.2-1 Function 3 does not include this detail. This changes the CTS by moving the information associated with the condensate storage tank level reference point to the ITS Bases.
Bases ITS 5.5.9 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 10 of 21 ATTACHMENT 5 3.3.6.1 LA.1 Table 3.2.1 (including Notes (1), (4), (6), and (7)),
Table 4.2.1 CTS Table 3.2.1 specifies the "Total No. of Instrument Channels Per Trip System" for each Primary Containment Isolation Function, and CTS Table 3.2.1 Note (1) states that "There shall be two operable...trip systems for each function." CTS Tables 3.2.1 and 4.2.1 Functions 1, 2, 3, 4, and 5 specify the group of valves isolated by each Function (i.e., "Group 1," "Group 2," "Group 3," "Group 4," and "Group 5"). CTS Table 3.2.1 Function 1 states that Function 1 provides isolation, in part, to "Recirc Sample Line" isolation valves, and Function 2 states that Function 2 provide isolation, in part, to "Sump" isolation valves. CTS Table 3.2.1 Note (4) states that for certain Functions, "All instrument channels are shared by both trip systems."
Furthermore, CTS Table 3.2.1 Note (1) has a parenthetical statement that "a shared channel is considered one channel." CTS Table 3.2.1 Note (6) states that, for CTS Table 3.2.1 Function 4.c, "The four pressure switches are arranged in a one-out-of-two-twice logic, the output of the logic providing a trip signal to a single trip system for isolation." CTS Table 3.2.1 Note (7) states that, for CTS Table 3.2.1 Function 5.c, "The four pressure switches are arranged in a one-out of two-twice logic, the output of the logic providing a trip signal to each of two separate trip systems. Each trip system is able, by itself, to initiate isolation." ITS 3.3.6.1 does not include these details.
This changes the CTS by moving the information concerning the "Total No.
of Instrument Channels Per Trip System" column, the number of trip systems, the name of the group isolated by each Function, that Function 1 isolates the "Recirc Sample Line" isolation valves and Function 2 isolates the "Sump" isolation valves, that certain channels are shared by both trip systems, and the logic description for CTS Table 3.2.1 Functions 4.c and 5.c to the ITS Bases.
Bases ITS 5.5.9 1
3.3.6.1 LA.2 Table 4.1.2 Group column CTS Table 4.1.2 defines the "Group" each instrumentation Function is assigned. The Table defines two groups. Group A is defined as "Passive type devices" and Group B is defined as "Vacuum tube or semiconductor devices and detectors that drift or lose sensitivity." ITS 3.3.6.1 does not include this information. This changes the CTS by relocating the design details associated with the instrumentation "Groups" to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 11 of 21 ATTACHMENT 5 3.3.6.2 LA.1 Table 3.2.4 including Note (1)
CTS Table 3.2.4 specifies the "Minimum No. of Operable or Operating Trip Systems" and "Total No. of Instrument Channels Per Trip System" for the Secondary Containment Isolation Instrumentation Functions. CTS Table 3.2.4 Note (1) also states that "There shall be two operable Trip Systems for each Function." ITS 3.3.6.2 does not include these details. This changes the CTS by moving the information concerning the "Minimum No. of Operable or Operating Trip Systems" and "Total No. of Instrument Channels Per Trip System" columns, and Note (1) information concerning the number of OPERABLE Trip Systems, to the ITS Bases.
Bases ITS 5.5.9 1
3.3.6.3 LA.1 Table 3.2.7 including Notes (1), (2), and (3)
CTS Table 3.2.7 specifies the "Min. No. of Operable or Operating Trip Systems" and "Total No. of Instrument Channels Per Trip System" for the S/RV LLS Instrumentation Functions. CTS Table 3.2.7 Note (1) states that the LLS and inhibit logic is provided for three S/RVs. The three valves have staggered setpoints as indicated. Table 3.2.7 Note (2) states that each valve is provided with two trip, or actuation, systems. CTS Table 3.2.7 Note (3) states that the Trip Setting for the Discharge Pipe Pressure Inhibit and Position Indication Function is with respect to drywell atmosphere. This changes the CTS by moving the information concerning the "Min. No. of Operable or Operating Trip Systems," "Total No. of Instrument Channels Per Trip System," and the Notes to the ITS Bases.
Bases ITS 5.5.9 1
3.3.7.1 LA.1 Table 3.2.9 CTS Table 3.2.9 specifies the "Total No. of Instrument Channels per Trip System" and "Minimum No. of Trip Systems" for the Control Room Radiation
- High Function. ITS 3.3.7.1 does not include these details. This changes the CTS by moving the information concerning the "Total No. of Instrument Channels per Trip System" and "Minimum No. of Trip Systems" columns to the ITS Bases.
Bases ITS 5.5.9 1
3.3.8.1 LA.1 Table 3.2.6 including Notes (2) and (3)
CTS Table 3.2.6 specifies the "Minimum No. of Operable or Operating Trip Systems" and "Total No. of Instrument Channels Per Trip System" for the Degraded Voltage and Loss of Voltage Functions. In addition, CTS Table 3.2.6 Notes (2) and (3) provide details of the LOP Instrumentation trip logic (i.e., one out of two twice for the Loss of Voltage Function and two-out-of-three for the Degraded Voltage Function). ITS 3.3.8.1 does not include these details. This changes the CTS by moving the information concerning the "Minimum No. of Operable or Operating Trip Systems" and "Total No. of Instrument Channels Per Trip System" columns, as well as the details of the trip logic, to the ITS Bases.
Bases ITS 5.5.9 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 12 of 21 ATTACHMENT 5 3.4.1 LA.1 3.5.F.1, 3.5.F.2, 3.5.F.4.a If the Stability Exclusion Region of the power to flow map is entered, CTS 3.5.F.1 requires exiting the region by either inserting control rods or increasing the speed of an operating recirculation pump. If the Stability Buffer Region of the power to flow map is entered, CTS 3.5.F.2 requires exiting the region by the same two actions. If either region is entered as a result of both recirculation pumps tripping, CTS 3.5.F.4.a requires complying with CTS 3.5.F.1 and 2 by inserting control rods. ITS 3.4.1 Required Action A.1 requires action to be taken to restore operation to within the Normal Region of the power to flow map, but does not provide the specific details of how operation is to be restored. This changes the CTS by relocating the details that operation is restored to within the Normal Region of the power to flow map by either inserting control rods or increasing the speed of an operating pump (as applicable) to the ITS Bases.
Bases ITS 5.5.9 3
3.4.3 LA.1 3.6.E.1 CTS 3.6.E.1 states that the safety valve function "(self actuation)" of seven S/RVs shall be OPERABLE. ITS LCO 3.4.3 requires the safety function of seven S/RVs to be OPERABLE. This changes the CTS by moving the detail that the safety function of S/RVs is by "self actuation" to the ITS Bases.
Bases ITS 5.5.9 1
3.4.3 LA.2 4.6.E.1.a CTS 4.6.E.1.a states that the S/RVs shall be "tested or replaced each refueling interval" in accordance with the Inservice Testing Program. ITS SR 3.4.3.1 requires the verification that the safety function lift setpoints of the required S/RVs are 1109 + 33.2 psig in accordance with the Inservice Testing Program. This changes the CTS by relocating the procedural detail that the S/RVs "shall be tested or replaced each refueling interval" to the Inservice Testing Program.
IST Program 10 CFR 50.55a 3
3.4.3 LA.3 4.6.E.1.b CTS 4.6.E.1.b states that "At least two of the safety/relief valves shall be disassembled and inspected each refueling interval." This changes the CTS by relocating this Surveillances Requirement to the TRM.
TRM 10 CFR 50.59 6
3.4.3 LA.4 4.6.E.1.c, 4.6.E.1.d CTS 4.6.E.1.c states that "The integrity of the safety/relief valve bellows shall be continuously monitored." CTS 4.6.E.1.d states that "The operability of the bellows monitoring system shall be demonstrated each operating cycle."
This changes the CTS by relocating these Surveillances Requirements to the TRM.
TRM 10 CFR 50.59 6
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 13 of 21 ATTACHMENT 5 3.4.9 LA.1 4.6.A, 4.6.B.1 CTS 4.6.A requires the reactor coolant temperatures at the following locations to be monitored: a. reactor vessel shell adjacent to shell flange; b.
reactor vessel bottom drain; c. recirculation loops A and B; and d. reactor vessel bottom head temperatures. The temperatures are to be monitored during heatups and cooldowns "until 3 consecutive readings at each location are within 5°F." CTS 4.6.B.1 requires the RCS temperatures at the following locations to be monitored during inservice hydrostatic or leak testing: a.
reactor vessel shell adjacent to shell flange; b. reactor vessel bottom head; and c. reactor vessel shell or coolant temperature representative of the minimum temperature of the beltline region. ITS SR 3.4.9.1 requires the RCS pressure, RCS temperature, and RCS heatup and cooldown rates to be within the applicable limits. This changes the CTS by relocating the details of the specific reactor coolant temperature locations that must be monitored and the criteria for ending the RCS heatup and cooldown rates verification to the ITS Bases.
Bases ITS 5.5.9 3
3/4.6.H LA.1 3/4.6.H CTS 3/4.6.H provides the requirements for all safety related snubbers. This Specification, with the exception of CTS 3.6.H.2, is not included in the ITS.
This changes the CTS by moving the explicit snubber requirements from the TSs to the TRM.
TRM 10 CFR 50.59 6
3.5.1 LA.1 4.5.A.2 CTS 4.5.A.2 requires the demonstration that LPCI pumps develop a 3,870 gpm flow rate against a system head corresponding to "two pumps delivering 7,740 gpm" at a reactor pressure of 20 psi greater than containment pressure. ITS SR 3.5.1.7 includes the same requirement, except the detail that the system head must correspond to "two pumps delivering 7,740 gpm" is not included. This changes CTS by moving the system head correction due to two pumps operating in parallel to the ITS Bases.
Bases ITS 5.5.9 3
3.5.1 LA.2 4.5.A.4 CTS 4.5.A.4 requires the performance of an ADS Valve Operability test by cycling each ADS valve "and observing a compensatory change in turbine bypass or control valve position." ITS SR 3.5.1.12 requires the verification that each ADS valve opens when manually actuated, but does not include the method for determining that the ADS valve has opened. This changes the CTS by moving the detail that the change in turbine bypass or control valve position shall be observed during the test to the ITS Bases.
Bases ITS 5.5.9 3
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 14 of 21 ATTACHMENT 5 3.5.1 LA.3 4.5.A.4 CTS 4.5.A.4 requires the performance of a simulated automatic actuation test of all ECCS subsystems and includes HPCI transfer to the suppression pool and automatic restart on subsequent Low Low reactor water level. ITS SR 3.5.1.10 requires the verification that each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.
This changes the CTS by moving the detail that the test verification must include "HPCI transfer to the suppression pool and automatic restart on subsequent Low Low reactor water level" to the ITS Bases. The change to allow an actual signal is discussed in DOC L.4.
Bases ITS 5.5.9 3
3.5.1 LA.4 4.5.A.5 CTS 4.5.A.5 requires the performance of an instrument check, test, and calibration of the Core Spray )p Instrumentation. ITS 3.5.1 does not include any Surveillance Requirements for the Core Spray )p instrumentation. This changes the CTS by relocating this Surveillance Requirement to the TRM.
TRM 10 CFR 50.59 4
3.5.1 LA.5 4.5.B.2 CTS 4.5.B.2 states to either close the inoperable valve or close the other Return Line isolation valve and the RHR suction line isolation valve when it is determined that one RHR intertie return line isolation valve is inoperable.
ITS 3.5.1 ACTION F covers the condition for inoperable RHR intertie return line isolation valve(s) and requires isolation of the RHR intertie line. This changes the CTS by moving the details on how to isolate the line to the ITS Bases.
Bases ITS 5.5.9 3
3.5.3 LA.1 4.5.D.2 CTS 4.5.D.2 requires the performance of a simulated automatic actuation test of the RCIC System that includes RCIC transfer to the suppression pool and automatic restart on subsequent low reactor water level. ITS SR 3.5.3.4 requires the verification that RCIC actuates on an actual or simulated automatic initiation signal. This changes the CTS by moving the detail that the test verification must include "RCIC transfer to the suppression pool and automatic restart on subsequent low reactor water level" to the ITS Bases.
The change to allow an actual signal is discussed in DOC L.2.
Bases ITS 5.5.9 3
3.6.1.1 LA.1 1.0.P CTS 1.0.P definition of Primary Containment Integrity states, in part, that "Primary Containment Integrity means that the drywell and pressure suppression chamber are intact," and that "All manways are closed." ITS 3.6.1.1 does not include these requirements. This changes the CTS by moving these requirements to the ITS Bases.
Bases ITS 5.5.9 2
3.6.1.2 LA.1 3.7.A.2.c CTS 3.7.A.2.c states (in part) what constitutes an OPERABLE containment air lock (i.e., both doors closed except when the air lock is being used, then at least one air lock door shall be closed). ITS LCO 3.6.1.2 does not include this level of detail. This changes the CTS by moving details concerning what constitutes an OPERABLE containment air lock to the ITS Bases.
Bases ITS 5.5.9 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 15 of 21 ATTACHMENT 5 3.6.1.2 LA.2 1.0.P.2 The CTS 1.0.P.2 definition of Primary Containment Integrity states that "At least one door in the air lock is closed and sealed." ITS 3.6.1.2 does not include this requirement. This changes the CTS by moving these details to the ITS Bases.
Bases ITS 5.5.9 2
3.6.1.3 LA.1 4.7.D.1.c, 4.7.D.1.d CTS 4.7.D.1.c states that "All normally open power-operated isolation valves shall be tested in accordance with the Inservice Testing Program. Main Steam isolation valves shall be tested (one at a time) with the reactor power less than 75% of rated." CTS 4.7.D.1.d states, At least once per week the main steam line power-operated isolation valves shall be exercised by partial closure and subsequent reopening." ITS 3.6.1.3 does not include these requirements. This changes the CTS by relocating these Surveillances Requirement to the TRM.
TRM 10 CFR 50.59 6
3.6.1.3 LA.2 3.7.D.2.a, 3.7.D.2.b, 3.7.D.3.b A parenthetical phrase to CTS 3.7.D.2.a, CTS 3.7.D.2.b, and CTS 3.7.D.3.b states that "Deactivated means electrically or pneumatically disarm or otherwise secure the valve." ITS 3.6.1.3 does not define the term "de-activated." This changes the CTS by moving the intent of the word "de-activated" to the ITS Bases.
Bases ITS 5.5.9 3
3.6.1.3 LA.3 3.7.D.3.a CTS 3.7.D.3.a specifies that inerting and de-inerting operations permitted by TS 3.7.A.5.b shall be via the 18 inch purge and vent valves "aligned to the Reactor Building plenum and vent." ITS SR 3.6.1.3.1 includes a Note that states that the 18-inch primary containment purge and vent valves may be opened for inerting, de-inerting, pressure control, ALARA, or air quality considerations for personnel entry, or Surveillance that require the valves to be open, but does not specify that the 18-inch purge and vent valves must be aligned to the Reactor Building Plenum and vent. This changes the CTS by moving the details on how to purge and vent through the 18-inch valves to the ITS Bases. The change adding additional reasons to use the 18-inch valves is discussed in DOC L.6.
Bases ITS 5.5.9 2
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 16 of 21 ATTACHMENT 5 3.6.1.7 LA.1 3.7.A.4.a, 3.7.A.4.b, Figure 3.7.1 CTS 3.7.A.4.a requires all suppression chamber-to-drywell vacuum breakers be closed "as indicated by the position indication system." CTS 3.7.A.4.b states that a suppression chamber-to-drywell vacuum breaker may not be fully closed "as indicated by the position indication and alarm system provided that drywell to suppression chamber differential pressure decay does not exceed that shown on Figure 3.7.1." CTS 4.7.A.4.b states that when the position of any suppression chamber-to-drywell vacuum breaker is indicated to be not fully closed, "the drywell to suppression chamber differential pressure decay shall be demonstrated to be less than shown on Figure 3.7.1." ITS 3.6.1.7 does not include the details for determining how the vacuum breakers are to be determined closed. This changes the CTS by relocating these details to the ITS Bases.
Bases ITS 5.5.9 3
3.6.1.7 LA.2 4.7.A.4.a.(4)
CTS 4.7.A.4.a.(4) requires a verification that the vacuum breaker opening force does not exceed an equivalent of 0.5 psid "acting on the suppression chamber face of the valve disc. (Containment access required.)" ITS SR 3.6.1.7.3 continues to require a verification that the vacuum breaker opening force is < 0.5 psid, but the location of the force (acting on the suppression chamber face of the valve disc) is not specified. In addition, the information that performance of the SR requires containment access is also not specified. This changes the CTS by relocating these details to the ITS Bases.
Bases ITS 5.5.9 3
3.6.1.7 LA.3 4.7.A.4.a.(2)
CTS 4.7.A.4.a.(2) states, in part, that "Once each operating cycle each vacuum breaker shall be visually inspected." ITS 3.6.1.7 does not include this requirement. This changes the CTS by relocating this Surveillance Requirement to the TRM.
TRM 10 CFR 50.59 6
3.6.1.7 LA.4 3.7.A.4.d CTS 3.7.A.4.d allows the suppression chamber-to-drywell vacuum breakers to be cycled, one at a time, during containment inerting and de-inerting operations "to assist in purging air or nitrogen from the suppression chamber vent header." ITS SR 3.6.1.7.1 Note 3 continues to provide the same allowance, but does not specify the purpose of the allowance. This changes the CTS by relocating this detail to the ITS Bases.
Bases ITS 5.5.9 3
3.6.1.8 LA.1 3.5.C.1 CTS 3.5.C.1 states that a containment spray subsystem consists of the following equipment powered from one division: 1 RHR Heat Exchanger, 1 RHR Pump, and valves and piping necessary for drywell spray. ITS 3.6.1.8 requires two RHR drywell spray subsystems to be OPERABLE, but the details of what constitutes an OPERABLE subsystem are moved to the ITS Bases. This changes the CTS by moving the details of what constitutes an OPERABLE subsystem to the ITS Bases.
Bases ITS 5.5.9 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 17 of 21 ATTACHMENT 5 3.6.2.3 LA.1 3.5.C.1 CTS 3.5.C.1 states that a containment cooling subsystem consists of the following equipment powered from one division: 1 RHR Heat Exchanger, 1 RHR Pump, and valves and piping necessary for torus cooling. ITS 3.6.2.3 requires two RHR suppression pool cooling subsystems to be OPERABLE, but the details of what constitutes an OPERABLE subsystem are moved to the ITS Bases. This changes the CTS by moving the details of what constitutes an OPERABLE subsystem to the ITS Bases.
Bases ITS 5.5.9 1
3.6.3.1 LA.1 3.7.A.5.a CTS 3.7.A.5.a states that the primary containment atmosphere shall be reduced to less than 4% oxygen by volume "with nitrogen gas." ITS LCO 3.6.3.1 states that primary containment oxygen concentration shall be < 4 volume percent, but does not state that it is to be done using nitrogen gas.
This changes the CTS by relocating the details on how to reduce oxygen concentration (i.e., "with nitrogen gas") to the ITS Bases.
Bases ITS 5.5.9 3
3.6.4.1 LA.1 4.7.C.1.a CTS 4.7.C.1.a requires the secondary containment capability test to maintain at least 1/4 inch of water vacuum "under calm wind (u < 5 mph) conditions."
CTS 4.7.C.1.a also states "If calm wind conditions do not exist during this testing, the test data is to be corrected to calm wind conditions." ITS SR 3.6.4.1.4 includes the same test; however, the wind conditions are not specified. This changes CTS by moving the details of the wind conditions to the ITS Bases.
Bases ITS 5.5.9 3
3.6.4.3 LA.1 3.7.B.1 CTS 3.7.B.1 states that two "separate and independent" Standby Gas Treatment (SGT) System trains shall be OPERABLE. ITS LCO 3.6.4.3 requires two SGT subsystems to be OPERABLE, but does not include the details of what constitutes OPERABILITY. This changes the CTS by moving the detail that the trains must be "separate and independent" to the ITS Bases.
Bases ITS 5.5.9 1
3.6.4.3 LA.2 3.7.B.2.c CTS 3.7.B.2.c requires the SGT subsystem be shown to be OPERABLE with automatic initiation upon receipt of the following inputs: Low Low Reactor Water Level; high drywell pressure; reactor building ventilation plenum high radiation; or refueling floor high radiation. ITS SR 3.6.4.3.3 requires verification that each SGT subsystem actuates on an initiation signal. This changes the CTS by moving the specific type of actuation signals to the ITS Bases.
Bases ITS 5.5.9 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 18 of 21 ATTACHMENT 5 3.7.1 LA.1 3.5.C.1 CTS 3.5.C.1 states that an RHRSW subsystem consists of the following equipment powered from one division: 1 RHR Heat Exchanger, 1 RHR Service Water Pump, and valves and piping necessary for torus cooling.
ITS 3.7.1 requires two RHRSW subsystems to be OPERABLE, but the details of what constitutes an OPERABLE subsystem are moved to the Bases. This changes the CTS by moving the details of what constitutes an OPERABLE subsystem to the Bases.
Bases ITS 5.5.9 1
3.7.4 LA.1 4.17.B.1 CTS 4.17.B.1 states to "initiate from the control room" flow through CREF subsystem and operate for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. ITS SR 3.7.4.1 includes the same requirement; however, the statement to "initiate from the control room" is not included. This changes the CTS by moving the requirement to "initiate from the control room" from the CTS to the ITS Bases.
Bases ITS 5.5.9 3
3.7.4 LA.2 3.17.B.2.c.(3),
4.17.B.2.c.(3)
CTS 3.17.B.2.c.(3) and CTS 4.17.B.2.c.(3) require each CREF subsystem be shown to be OPERABLE with automatic initiation upon receipt of a "high radiation" signal. ITS SR 3.7.4.3 requires verification that each CREF subsystem actuates on an initiation signal. This changes the CTS by moving the specific type of actuation signal to the ITS Bases.
Bases ITS 5.5.9 1
3.8.1 LA.1 3.9.A.1, 3.9.A.1.c, 3.8.B.1, 4.9.A.1 CTS 3.9.A.1 states, in part, that two NSP transmission lines and associated switchgear must be fully operational. Furthermore, a parenthetical phrase in CTS 3.9.A.1.c states that one of the sources to the required offsite circuits is the "source from 10 transformer." CTS 3.9.B.1 provides actions to be taken when one of the two required NSP transmission lines is found to be inoperable. CTS 4.9.A.1 specifies Surveillances for the substation switchyard battery that provides control power for the NSP transmission line breakers. ITS 3.8.1 does not include any requirements for the NSP transmission lines and associated switchgear and batteries. This changes the CTS by relocating the LCO, Actions, and Surveillance Requirements for the NSP transmission lines and associated switchgear and batteries to the TRM.
TRM 10 CFR 50.59 6
3.8.1 LA.2 3.9.A.1, 3.9.A.1.a, 3.9.A.1.b, 3.9.A.1.c CTS 3.9.A.1 requires two offsite power sources to be fully operational and energized to carry power to the plant 4160 V AC buses and provides details of what constitutes an offsite power source. ITS 3.8.1 requires two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System to be OPERABLE, but the details of what constitutes an OPERABLE qualified circuit is contained in the ITS Bases. This changes the CTS by moving the details of what constitutes an OPERABLE qualified circuit to the ITS Bases.
Bases ITS 5.5.9 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 19 of 21 ATTACHMENT 5 3.8.1 LA.3 3.9.A.2 CTS 3.9.A.2 specifies that both diesel generators be operable and "capable of feeding their designated 4160 volt buses." ITS 3.8.1 requires both diesel generators to be OPERABLE, but the details of what constitutes an OPERABLE diesel generator is moved to the ITS Bases. This changes the CTS by moving the details of what constitutes an OPERABLE diesel generator to the ITS Bases.
Bases ITS 5.5.9 1
3.8.1 LA.4 4.9.B.3.b.2)
CTS 4.9.B.3.b.2) requires the diesel fuel oil transfer pump and diesel oil service pump to be operated. ITS SR 3.8.1.5 requires verification that the fuel oil transfer system operates to transfer fuel oil from the storage tank to the day tanks and from the day tanks to the associated base tanks. The details of what constitutes an OPERABLE diesel fuel oil transfer system is moved to the ITS Bases. This changes the CTS by moving the details of what constitutes an OPERABLE diesel generator to the ITS Bases.
Bases ITS 5.5.9 1
3.8.3 LA.1 3.9.B.3.b CTS 3.9.B.3.b states that the minimum specified diesel fuel volume in the diesel oil storage tank is adequate to supply 7 days of operation for one EDG at full load (2500 kW). ITS 3.8.3 does not include this statement. This changes the CTS by relocating the details of the system design to the ITS Bases.
Bases ITS 5.5.9 1
3.8.4 LA.1 3.9.A.4, 3.9.B.5, 4.9.B.5 CTS 3.9.A.4 states that the 24/48 volt batteries must be charged and in service, and the associated battery chargers must be OPERABLE. CTS 3.9.B.5 provides the Actions to take when one of the two 24 V battery systems are found to be inoperable, and CTS 4.9.B.5 includes Surveillance Requirements for the station 24 volt batteries. ITS 3.8.4 does not include any requirements for the station 24/48 VDC batteries or chargers. This changes the CTS by relocating the LCO, Actions, and Surveillances Requirements to the TRM.
TRM 10 CFR 50.59 6
3.8.4 LA.2 3.9.A.4 CTS 3.9.A.4, in part, requires the 125 V and 250 V batteries to be charged and in service, and the associated battery chargers to be OPERABLE. ITS LCO 3.8.4 requires the Division 1 and Division 2 125 VDC and 250 VDC electrical power subsystems to be OPERABLE. This changes the CTS by relocating the details of the system design (i.e., batteries are charged and in service, and the batteries chargers are OPERABLE) to the ITS Bases.
Bases ITS 5.5.9 1
3.8.6 LA.1 4.9.B.4.b CTS 4.9.B.4.b requires each cell voltage to be measured "to the nearest 0.01 volt." ITS SR 3.8.6.5 requires verification that each battery connected cell voltage is within a specified limit. This changes the CTS by relocating the details that the cell voltage measurement be "to the nearest 0.01 volt" to the ITS Bases.
Bases ITS 5.5.9 3
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 20 of 21 ATTACHMENT 5 3.8.7 LA.1 3.9.A.3.(a),
3.9.A.3.(b)
CTS 3.9.A.3.(a) requires the 4160V Buses #15 and #16 to be energized.
CTS 3.9.A.3.(b) requires the 480V Buses #103 and #104 to be energized.
ITS LCO 3.8.7, in part, requires the Division 1 and Division 2 AC electrical power distribution subsystems to be OPERABLE. This changes the CTS by moving the specific names of the buses, the associated nominal bus voltages (i.e., 4160 V and 480 V), and that the buses must be energized from the CTS to the ITS Bases.
Bases ITS 5.5.9 1
ITS 3.9 /
CTS 3.10.D LA.1 3.10.D CTS LCO 3.10.D requires the reactor to be subcritical for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to movement of fuel within the reactor. The ITS does not include the requirements for decay time. This changes the CTS by moving the explicit decay time requirements from the TSs to the TRM.
TRM 10 CFR 50.59 6
3.10 None None None None None 4.0 LA.1 5.1 CTS 5.1 provides details describing the site location and property lines. The ITS does not contain these details. This changes the CTS by moving the details of the site location and property to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 1 4.0 LA.2 5.2.B CTS 5.2.B states that the control rod material shall be boron carbide "powder (B4C) compacted to approximately 70% of theoretical density" or hafnium.
ITS 4.2.2 states the control material shall be boron carbide or hafnium metal as approved by the NRC. This changes the CTS by moving the detailed description of the boron carbide control rod material to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 1 4.0 LA.3 5.3 CTS 5.3 includes some design details of the reactor pressure vessel and the reactor recirculation system. The ITS does not contain this information. This changes the CTS by moving the description of the design details of the reactor pressure vessel and the reactor recirculation system to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 1 4.0 LA.4 5.4 CTS 5.4 describes the various design features of the primary and secondary containments. The ITS does not contain this information. This changes the CTS by moving the description of the design feature of the containment to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 1 4.0 LA.5 5.5.A CTS 5.5.A states, in part, that normal storage for unirradiated fuel assemblies is in critically-safe new fuel storage racks in the reactor building storage vault. The ITS does not contain this information. This changes the CTS by moving the detail of the location for normal storage of unirradiated fuel assemblies to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 1 4.0 LA.6 5.6 CTS 5.6 describes certain general seismic design requirements for Class 1 structures and equipment. The ITS does not contain this information. This changes the CTS by moving the description of these general seismic design requirements to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 1
Table LA - Removed Detail Changes ITS/CTS No.
and DOC No CTS Requirement Description of Relocated Requirement Location Change Control Process Change Type Monticello Page 21 of 21 ATTACHMENT 5 5.1 LA.1 6.1.A CTS 6.1.A uses the title "Shift Supervisor." ITS 5.1.2 uses the generic title "shift supervisor." This changes the CTS by moving the specific Monticello organizational title to the USAR or Quality Assurance Topical Report (QATR) and replacing it with a generic title.
USAR or QATR 10 CFR 50.59, 10 CFR 50.71(e),
10 CFR 50.54 (a) 3 5.2 LA.1 6.1.C.1, Table 6.1.1, including Notes 2, 3, and 4 CTS 6.1.C.1 and Table 6.1.1, including Notes 2, 3, and 4, provide minimum shift crew composition requirements. ITS 5.2.2 only includes the minimum shift crew composition requirements that are not already included in 10 CFR 50.54. This changes the CTS by moving the minimum shift crew composition requirements addressed by 10 CFR 50.54 to the TRM.
TRM 10 CFR 50.59 3
5.3 LA.1 6.1.C.8, 6.1.D CTS 6.1.C.8 states that the licensed Senior Operator and Operator training program must be accredited by the National Nuclear Accrediting Board. CTS 6.1.D states that the training program must be under the direction of a designated member of Nuclear Management Company, LLC management.
These requirements are not retained in the ITS. This changes the CTS by moving the requirements for the training program to the USAR.
USAR 10 CFR 50.59, 10 CFR 50.71(e) 6 5.5 LA.1 6.8.G CTS 6.8.G states that the Inservice Testing Program provides controls for inservice testing of Quality Group A, B, and C pumps and valves which shall be performed in accordance with the requirements of ASME Code Class 1, 2, and 3 pumps and valves, respectively. ITS 5.5.5 only states that the Inservice Testing Program provides controls for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves. This changes the CTS by moving these procedural details that the "Quality Group A, B, and C pumps and valves" corresponds to the ASME Code Class 1, 2, and 3 pumps and valves, respectively, from the TSs to the Inservice Testing Program.
IST Program 10 CFR 50.55a 3
5.6 LA.1 6.7.A.7.b CTS 6.7.A.7.b specifies the revision/supplement numbers and dates (e.g.,
latest approved version at the time the reload analyses are performed) of the referenced methodologies used for the development of the COLR. ITS 5.6.3.b does not contain this level of detail. This changes the CTS by moving the specific methodology references for revisions/supplements and dates to the COLR.
Change Types (only applicable to LA DOCs):
1 - Removing Details of System Design and System Description, including Design Limits 2 - Removing Descriptions of System Operation 3 - Removing Procedural Details for Meeting TS Requirements or Reporting Requirements 4 - Removing Performance Requirements for Indication-Only Instrumentation and Alarms 5 - Removal of Cycle-Specific Parameter Limits from the Technical Specifications to the COLR 6 - Removal of LCO, SR, or other TS Requirement to the TRM, USAR, ODCM, OQAP, IST Program, or IIP