ML022200424
| ML022200424 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/29/2002 |
| From: | Forbes J Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022200424 (16) | |
Text
NMC Monticello Nuclear Generating Plan Committed to Nuclear ExceUl] enc Operated by Nuclear Management Company, LLC July 29, 2002 Technical Specification 6.8.K US Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Technical Specification Bases Change 128a Correct Drywell to Suppression Chamber Vacuum Breaker Indicating Light Description Using the Monticello Technical Specification Bases Control Program, a Monticello Technical Specification Bases page has been changed. The affected page is designated with the amendment applicable at the time and the suffix "a." The change is summarized in Attachment A. A marked up page applicable at the time the change was made is provided in Attachment B. A final typed copy of the changed page that is applicable, for entry into the NRC authority copy, is provided in Attachment C. The current copy of our list of effective pages and record of revision is attached for your information, as Attachment D.
se contact Paul Hartmann, at 763-271-5172 with any questions or comments.
Jeffrey S. Forbes Site Vice President Monticello Nuclear Generating Plant Attachment A - Summary of Technical Specification Bases Change (TSBC)
Attachment B -
Monticello Technical Specification Bases Page Marked Up With Changes Attachment C -
Revised Monticello Technical Specification Bases Page Attachment D -
Monticello Technical Specification List of Effective Pages and Record of Revision cc:
Regional Administrator-Ill, NRC NRR Project Manager, NRC Resident Inspector, NRC Minnesota Department of Commerce 0
2807 West County Road 75 9 Monticello, Minnesota 55362-9637 Telephone: 763.295.5151
- Fax: 763.295.1454
Attachment A Summary of Technical Specification Bases Change (TSBC)
Following is a summary of the bases change forwarded herein. The change has been processed in accordance with the Monticello Technical Specification Bases Control Program described in Technical Specification 6.8.K.
TSBC-128a Technical Specification Involved - 3.7 Page affected - 180 Summary of Change: This TSBC corrected the drywell to suppression chamber vacuum breaker indicating light description.
A-1
Attachment B Monticello Technical Specification Bases Page Marked Up With Changes This attachment consists of Monticello Technical Specification bases page marked up with changes. The page included is listed below:
Page 180 B-1
Bases 3.7 (Continued):
vacuum breaker selector switch, and a common test switch. The reactor building vacuum breaker panel contains one red light and one green light for each of the eight valves. There are four independent limit switches on each valve. The two switches controlling the red lights are adjusted to provide an indication of disc opening of less than 1/8" at the bottom of the disc. These switches are also used to activate the valve position alarm circuits. The two switches controlling the green lights are adjusted to provide indication of the disc very near the full open position.
The control room alarm circuits are redundant and fail safe. This assures that no simple failure will defeat alarming to the control room when a valve is open beyond allowable and when power to the switches fails. The alarm is needed to alert the operator that action must be taken to correct a malfunction or to investigate possible changes in valve position status, or both. If the alarm cannot be cleared due to the inability to establish indication of closure of one or more valves, additional testing is required.
The alarm system allows the operator to make this evaluation on a timely basis. The frequency of the,etqg of the alarms is the same as that required for the position indication system.
/1)
Operability of a vacuum breaker valve and the four associated indicating light circuits shall be est blished by cycling the valve.
The sequence of the indicating lights will be observed to be that previously described. If bothe ight circuits are inoperable, the valve shall be considered inoperable and a pressure test is required immediately and upon indication of subsequent operation. If bothd* light circuits are inoperable, the valve shall be considered inoperable, however, no pressure test is required if positive closure i ic present.
Oxygen concentration 1iited to 4% by volume to minimize the possibility of hydrogen combustion following a loss of coolant accident. Significant quantities of hydrogen could be generated if the core cooling systems failed to sufficiently cool the core.
The occurrence of primary system leakage following a major refueling outage or other scheduled shutdown is more probable than the occurrence of the loss of coolant accident upon which the specified oxygen concentration limit is based. Permitting access to the drywell for leak inspections during a startup is judged prudent in terms of the added plant safety offered without significantly reducing the margin of safety. Thus, to preclude the possibility of starting the reactor and operating for extended periods of time with significant leaks in the primary system, leak inspections are scheduled during startup periods, when the primary system is at or near rated operating temperature and pressure. The 24-hour period to provide inerting is judged to be sufficient to perform the leak inspection and establish the required oxygen concentration. The primary containment is normally slightly pressurized during periods of reactor operation. Nitrogen used for inerting could leak out of the containment but air could not leak in to increase oxygen concentration. Once the containment is filled with nitrogen to the required concentration, no monitoring of oxygen concentration is necessary. However, at least once a week the oxygen concentration will be determined as added assurance.
3.7 BASES 180 11/16/01 Amendment No. 17, 35, 0, 100a, 123a
Attachment C Revised Monticello Technical Specification Bases Page This attachment consists of the revised Monticello Technical Specification Bases page that incorporates the change. This page should be entered into the NRC Authority copies of Technical Specifications. The page included is listed below:
Page 180 C-1
Bases 3.7 (Continued):
vacuum breaker selector switch, and a common test switch. The reactor building vacuum breaker panel contains one red light and one green light for each of the eight valves. There are four independent limit switches on each valve. The two switches controlling the red lights are adjusted to provide an indication of disc opening of less than 1/8" at the bottom of the disc. These switches are also used to activate the valve position alarm circuits. The two switches controlling the green lights are adjusted to provide indication of the disc very near the full open position.
The control room alarm circuits are redundant and fail safe. This assures that no simple failure will defeat alarming to the control room when a valve is open beyond allowable and when power to the switches fails. The alarm is needed to alert the operator that action must be taken to correct a malfunction or to investigate possible changes in valve position status, or both. If the alarm cannot be cleared due to the inability to establish indication of closure of one or more valves, additional testing is required.
The alarm system allows the operator to make this evaluation on a timely basis. The frequency of the testing of the alarms is the same as that required for the position indication system.
Operability of a vacuum breaker valve and the four associated indicating light circuits shall be established by cycling the valve.
The sequence of the indicating lights will be observed to be that previously described. If both red light circuits are inoperable, the valve shall be considered inoperable and a pressure test is required immediately and upon indication of subsequent operation. If both green light circuits are inoperable, the valve shall be considered inoperable, however, no pressure test is required if positive closure indication is present.
Oxygen concentration is limited to 4% by volume to minimize the possibility of hydrogen combustion following a loss of coolant accident. Significant quantities of hydrogen could be generated if the core cooling systems failed to sufficiently cool the core.
The occurrence of primary system leakage following a major refueling outage or other scheduled shutdown is more probable than the occurrence of the loss of coolant accident upon which the specified oxygen concentration limit is based. Permitting access to the drywell for leak inspections during a startup is judged prudent in terms of the added plant safety offered without significantly reducing the margin of safety. Thus, to preclude the possibility of starting the reactor and operating for extended periods of time with significant leaks in the primary system, leak inspections are scheduled during startup periods, when the primary system is at or near rated operating temperature and pressure. The 24-hour period to provide inerting is judged to be sufficient to perform the leak inspection and establish the required oxygen concentration. The primary containment is normally slightly pressurized during periods of reactor operation. Nitrogen used for inerting could leak out of the containment but air could not leak in to increase oxygen concentration. Once the containment is filled with nitrogen to the required concentration, no monitoring of oxygen concentration is necessary. However, at least once a week the oxygen concentration will be determined as added assurance.
3.7 BASES 180 07/11/02 Amendment No. 17, 35, 80, lOn0, 123a, 128a
Attachment D Monticello Technical Specification List of Effective Pages and Record of Revision This attachment consists of the current Monticello Technical Specification List of Effective Pages and Record of Revision. The pages included are listed below:
Page A
B C
D E
F G
H I
MONTICELLO NUCLEAR GENERATING PLANT APPENDIX A TECHNICAL SPECIFICATIONS RECORD OF REVISIONS Amend Page No.
A 128a B
128a C
115 D
115 E
115 F
115 G
115 H
119 I
128a i
128 ii 104 iii 120 iv 128 v
120 vi 121 vii 122 1
119 2
70 3
21 4
102 5
120 5a 120 6
128 7
128 8
128 9
128 10 128 11 128 12 128 25a 127 25b 127 25c 127 25d 127 26 5
27 81 27a 81 28 128 29 128 30 103 31 104 32 103 33 103 34 83 35 100a 36 128 Amend Paae No.
37 128 38 128 39 128 40 128 42 103 45 0
46 70 46a 37 47 40 48 89 49 128 50 128 50a 117 51 117 51a 117 52 128 53 128 54 128 55 103 56 102 57 70 58 84 58a 29 59 128 59a 103 60 128 60a 31 60b 62 60c 30 60d 128 60e 89 61 104 62 117 63 117 63a 117 64 128 65 117 66 119a 67 117 68 102 69 118a 69a 100a 70 117 71 100a 71 a 105 Amend Page No.
72 104 76 0
77 86 78 0
79 0
80 29 81 3
82 123 82a 63 83 24 83a 24 84 100a 85 100a 86 100a 87 100a 88 100a 89 104 90 100a 91 123 92 100a 93 122 94 106 95 77 96 77 97 57 98 56 99 104 100 100a 101 122 102 122 103 122 104 122 105 122 106 79 107 97 108 128 109 100a 110 100a 111 122 112 124a 113 122 114 122 121 0
122 106 123 117 Amend Page No.
124 121 125 104 126 104 126a 87 127 128 128 42 129 122 130 82 131 122 132 39 132a 122 133 106 134 106 135 106 136 106 137 0
138 100a 145 118a 146 106 147 107 148 117 149 100a 150 128 151 128 153 100a 154 100a 155 122 156 93 157 117 158 107 159 95 160 95 163 0
164 104 165 64 166 94 167 112 168 94 169 94 170 122 171 96 172 71 175 107 175a 117 176 100a A
Amendment No. 128a 07/11/02
APPENDIX Amend Page No.
177 117 178 100a 179 123a 180 128a 181 100a 182 112 183 117 184 100a 185 100a 188 104 189 100a 190 104 191 0
192 121 193 121 196 126a 197 121 198 121 199 51 200 104 201 77 202 80 203 41 204 100a 205 100a 206 0
207 123 208 63 209 123 209a 100a 210 100a 211 109 212 109 213 99 216 100a 217 128 218 120 223 119 224 119 225 119 226 119 MONTICELLO NUCLEAR GENERATING PLANT A TECHNICAL SPECIFICATIONS RECORD OF REVISIONS Amend Page No.
229a 63 229b 104 229c 104 229d 63 229e 122 229u 104 229v 112 229v v 112 229w 112 229ww 112 229x 112 229y 115a 229z 112 230 54 231 34 232 119 233 124 234 119 235 115 236 115 243 128 244 124 248 59 249 120 250 128 251 124 252 120 253 120 254 120 255 120 256 122 257 122 258 122 259 120 260 120 261 120 262 120 B
Amendment No. 128a 07/11/02
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP Page Revision (REV' No.
Original Note 2 Note 2 Note 2 Note 2 Note 2 Note 2 3
4 6/17/74 6
8/20/74 Note 3 5
7 8
9 10 7/8/75 12 11 13 14 15 1/22/76 16 2/3/76 17 3/16/76 NOTE 3 18 4/14/76 21 5/20/76 License DPR-22 Amend No. & Date 1
1/19/71 Note 2 Note 2 Note 2 2
2/20/73 Note 2 Note 2 NOTE 4 4/13/76 AEC Tech Spec Change Issuance No. and date Note 1 2
1/14/72 3
10/31/72 4
12/8/72 Note 1 5
3/2/73 1
4/28/71 &
6 4/3/73 7
5/4/73 8
7/2/73 9
8/24/73 10 10/2/73 11 11/27/73&
12 11/15/73 13 3/30/74 14 5/14/74 Note 1 Note 1 Note 3 10/24/74 15 1/15/75 16 2/3/75 17 2/26/75 18 4/10/75 Note 1 20 9/15/75 19 9/17/75 21 10/6/75 22 10/30/75 C
Amendment No. 115 12/21/00 Major Subject Appendix A Technical Specifications incorporated in DPR-22 on 9/8/70 Removed 5 MWt restriction MOGS Technical Specification changes issued by AEC but never distributed or put into effect, superseded by TS Change 12 11/15/73 RHR service water pump capability change Temporary surveillance test waiver Increase in U-235 allowed in fission chambers Miscellaneous Technical Specification changes, Respiratory Protection, & Administrative Control Changes Respiratory Protection Changes Relief Valve and CRD Scram Time Changes Fuel Densification Limits Safety Valve Setpoint Change Offgas Holdup System, RWM, and Miscellaneous Changes 8x8 Fuel Load Authorization 8x8 Full Power authorization Changed byproduct material allowance Changed byproduct material allowance Inverted Tube (CRD) Limits REMP Changes Reactor Vessel Surveillance Program Changes Vacuum Breaker Test Changes Corrects Errors & Provides Clarification Increased allowed quantity of U-235 Snubber Requirements Removed byproduct material allowance Suppression Pool Temperature Limits Appendix K and GETAB Limits Reporting Requirements CRD Collet Failure Surveillance NSP Organization Changes Adoption of GETAB Containment Isolation Valve Testing Interim Appendix B, Section 2.4 Tech. Specs.
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 I
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP Revision (REV) No.
26 27 28 29 30 31 32 33 34 35 36 37 38 39 NOTE 1 40 41 42 43 44 45 46 47 48 49 50 NOTE 1 NOTE 1 51 52 NOTE 1 License DPR-22 Amend No. & Date 19 5/27/76 20 6/18/76 22 7/13/76 23 9/27/76 24 10/15/76 25 10/27/76 26 4/1/77 27 5/24/77 28 6/10/77 29 9/16/77 30 9/28/77 31 10/14/77 32 12/9/77 33 1/25/78 34 4/14/78 35 9/15/78 36 10/30/78 37 11/6/78 NOTE 3 11/24/78 38 3/15/79 39 5/15/79 40 6/5/79 41 8/29/79 42 12/28/79 43 2/12/80 44 2/29/80 8/29/80 9/19/80 10/24/80 1/9/81 1/9/81 I
D Amendment No. 115 12/21/00 Major Subject Low Steamline Pressure Setpoint and MCPR Changes APLHGR, LHGR, MCPR Limits Correction of Errors and Environmental Reporting Standby Gas Treatment System Surveillance CRD Test Frequency Snubber Testing Changes APRS Test Method MAPLHGR Clamp at Reduced Flow Radiation Protection Supervisor Qualification REMP Changes More Restrictive MCPR Inservice Inspection Changes Reporting Requirements Fire Protection Requirements Increase in spent fuel storage capacity RPT Requirements Suppression Pool Surveillance 8x8R Authorization, MCPR Limits & SRV Setpoints Corrected Downcomer Submergence Incorporation of Physical Security Plan into License Revised LPCI Flow Capability Respiratory Protection Program Changes Fire Protection Safety Evaluation Report MAPLHGR vs. Exposure Table MCPR & MAPLHGR Changes for Cycle 8 and Extended Core Burnup ILRT Requirements Order for Modification of License-Environmental Qualification Revised Order for Modification of License-Environmental Qualification Order for Modification of License-Environmental Qualification Records Issuance of Facility Operating License (FTOL)
Order for Modification of License Concerning BWR Scram Discharge Systems (License conditions removed per Amendment No. 11 dated 10/8/82)
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS License DPR-22 Amend No. & Date 1/13/81 1
2/12/81 2
3/2/81 3
4 3/27/81 3/27/81 5
5/4/81 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 6/3/81 6/30/81 11/5/81 12/28/81 1/19/82 5/20/82 10/8/82 11/30/82 12/6/82 12/10/82 12/17/82 4/18/83 4/17/83 11/28/83 12/30/83 1/16/84 1/23/84 2/2/84 4/3/84 5/1/84 8/15/84 9/24/84 10/31/84 11/2/84 11/16/84 11/16/84 11/27/84 NSP Revision (REVA No.
NOTE 1 I
E Amendment No. 115 12/21/00 53 54 NOTE 1 Major Subiect Order for Modification Mark I Containment Revision of License Conditions Relating to Fire Protection Modifications TMI Lessons Learned & Safety Related Hydraulic Snubber Additions Low voltage protection, organization and miscellaneous Incorporation of Safeguards Contingency Plan and Security Force Qualification and Training Plan into License Cycle 9 - ODYN Changes, New MAPLHGR's, RPS Response time change Inservice Inspection Program Fire Protection Technical Specification Changes Mark I Containment Modifications Inservice Surveillance Requirements for Snubbers Revised Order for Modification Mark I Containment Scram Discharge Volume New Scram Discharge Volumes RPS Power Monitor Cycle 10 Recirc Piping and Coolant Leak Detection Appendix I Technical Specifications (removed App. B)
Organizational Changes Miscellaneous Changes Steam Line Temperature Switch Setpoint Radiation Protection Program SRM Count Rate Definition of Operability Miscellaneous Technical Specification Changes RPS Electrical Protection Assembly Time Delay Scram Discharge Volume Vent and Drain Valves Miscellaneous Technical Specification Changes Cycle 11 RHR Intertie Line Addition Hybrid I Control Rod Assembly ARTS Low Low Set Logic Degraded Voltage Protection Logic 55 56 57 58 59 NOTE 1 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP Revision (REV) No.
82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 License DPR-22 Amend No. & Date 32 5/28/85 33 10/7/85 34 10/8/85 35 12/3/85 36 12/23/85 37 1/22/86 38 2/12/86 39 3/13/86 40 3/18/86 41 3/24/86 42 3/27/86 43 4/8/86 44 5/27/86 45 7/1/86 46 7/1/86 47 10/22/86 48 12/1/86 49 8/26/87 50 8/26/87 51 10/16/87 52 11/18/87 53 11/19/87 54 11/25/87 55 11/25/87 56 12/11/87 57 9/23/88 58 12/13/88 59 2/16/89 60 2/28/89 61 3/29/89 62 3/31/89 63 4/18/89 64 5/10/89 65 5/30/89 66 5/30/89 F
Amendment No. 115 12/21/00 Maior Subiect Surveillance Requirements Screen Wash/Fire Pump (Partial)
Fuel Enrichment Limits Combustible Gas Control System Vacuum Breaker Cycling NUREG-0737 Technical Specifications Environmental Technical Specifications Administrative Changes Clarification of Radiation Monitor Requirements 250 Volt Battery Jet Pump Surveillance Simmer Margin Improvement Cycle 12 Operation Miscellaneous Changes LER Reporting and Miscellaneous Changes Single Loop Operation Offgas System Trip Rod Block Monitor APRM and IRM Scram Requirements 2R Transformer Surveillance Intervals - ILRT Schedule Extension of Operating License Cycle 13 and Misc Changes Appendix J Testing ATWS - Enriched Boron Increased Boron Enrichment Physical Security Plan Miscellaneous Administrative Changes Miscellaneous Administrative Changes Fire Protection and Detection System ADS Logic and S/RV Discharge Pipe Pressure Miscellaneous Technical Specification Improvements Containment Vent and Purge Valves NUREG-0737 - Generic Letter 83-36 Reactor Vessel Level Instrumentation
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP Revision (REV No.
117 118 119 120 121 122 123 124 125 126 127 128 125 130 131 132 133 134 135 136 137 138 89 8/25/94 90 91 92 93 94 95 96 97 9/7/94 9/9/94 9/15/94 7/12/95 10/2/95 4/3/96 4/9/96 9/17/96 License DPR-22 Amend No. & Date 67 6/19/89 68 7/14/89 69 9/12/89 70 9/28/89 71 10/19/89 72 11/2/89 73 5/1/90 74 6/5/90 75 10/12/90 76 12/20/90 77 2/15/91 78 3/28/91 79 4/9/91 80 8/12/91 81 4/16/92 82 7/15/92 83 8/18/92 84 1/27/93 85 6/29/93 86 7/12/93 87 4/15/94 88 6/30/94 I
G Amendment No. 115 12/21/00 Maior Subject Extension of MAPLHGR. Exposure for One Fuel Type SRO Requirements & Organization Chart Removal Operations Committee Quorum Requirements Relocation of Cycle-Specific Thermal-Hydraulic Limits Deletion of Primary Containment Isolation Valve Table RG 1.99, Rev 2, ISI & ILRT Combined STA/LSO Position Removal of WRGM Automatic ESF Actuation Diesel Fuel Oil Storage Miscellaneous Administrative Changes Redundant and IST Testing Alarming Dosimetry SAFER/GESTR Torus Vacuum Breaker Test Switch/EDG Fuel Oil Tank Level Surveillance Test Interval Extension - Part I Alternate Snubber Visual Inspection Intervals Revisions to Reactor Protection System Tech Specs MELLIA and Increase Core Flow Revision to Diesel Fire Pump Fuel Oil Sampling Requirements Revisions to Control Rod Drive Testing Requirements Revised Coolant Leakage Monitoring Frequency Average Planar Linear Heat Generation Rate (APLHGR)
Specification & Minimum Critical Power Ratio Bases Revisions Removal of Chlorine Detection Requirements and Changes to Control Room Ventilation System Requirements Revisions to Radiological Effluent Specifications Secondary Containment System and Standby Gas Treatment System Water Level Setpoint Change Change in Safety Relief Valves Testing Requirements Revised Core Spray Pump Flow Standby Gas Treatment and Secondary Containment Systems MSIV Combined Leakrate, and Appendix J, Option B Purge and Vent Valve Seal Replacement Interval Implementation of BRWOG Option I-D core Stability Solution and re-issue of pages 11, 12, 82 and 231 to reflect pages issued by NRC amendments.
139 140 141 142 143 144 145 146 147
NSP Revision (REVA No.
148 149 NOTE 5 150 NOTE 6 MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS License DPR-22 Amend No. & Date Mamor Subject 98 7/25/97 Bases changes on containment overpressure and number of RHR pumps required to be operable. Reissue pages 207, 209, 219, 229k, 229p, 230, 245 to reflect pages issued by NRC amendments.
99 10/29/97 SLMCPR for Cycle 18 and reissue pages vi, 155, 202, 207, 219, 229u 11/25/97 Reissue pages a, b, g, iii, vi, 14, 25a, 155, 198y, 198z, 202, 207, 209, 219, 229k, 229p, 229r, 229u, 230, 245 100 4/20/98 SLMCPR for Cycle 19 1 00a 4/30/98 Reissue all pages.
101 08/28/98 Reactor Coolant Equivalent Radioiodine Concentration and Control Room Habitability 102 09/16/98 Monticello Power Rerate 103 12/23/98 Surveillance Test Interval/Allowed Outage Time Extension Program - Part 2 104 12/24/98 Revision of Statement on Shift Length & other Misc Changes 105 03/19/99 CST Low Level HPCI/RCIC Suction Transfer 106 10/12/99 Revised RPV-PT Curves & remove SBLC RV setpoint 107 11/24/99 Reactor Pressure Vessel Hydrostatic and Leakage Testing 108 12/8/99 Testing Requirements for Control Room EFT Filters 109 02/16/00 Safety Limit Minimum Critical Power Ratio for Cycle 20 110 08/07/00 Transfer of Operating Authority from NSP to NMC 111 08/18/00 Transfer of Operating License from NSP to a New Utility Operating Company 112 08/18/00 Emergency Filtration Train Testing Exceptions and Technical Specification Revisions 113 10/02/00 Alternate Shutdown System Operability Requirements 114 11/30/00 Safety/Relief Valve Bellows Leak Detection System Test Frequency 115 12/21/00 Administrative Controls and Other Miscellaneous Changes 11 5a 02/13/01 Bases Change to Reflect Modification 98Q145 Installed Control Room Toxic Gas Air Supply 116 03/01/01 Relocation of Inservice Inspection Requirements to a Licensee Program 117 03/07/01 Reactor Water Cleanup (RWCU) System Automatic Isolation and Miscellaneous Instrumentation System Changes 118 03/09/01 Revision of Standby Liquid Control System Surveillance Requirements 11 8a 05/10/01 Bases Change - 50°F Loop Temperature, Bus Transfer &
Rerate Correction H
Amendment No. 119 04/05/01
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP Revision (REV) No.
License DPR-22 Amend No. & Date 119 04/05/01 119a 06/28/01 120 07/24/01 121 07/25/01 122 08/01/01 122a 10/22/01 123 10/26/01 123a 10/25/01 124 10/30/01 124a 12/05/01 125 12/06/01 Safety Limit Minimum Critical Power Ratio for Cycle 21 126 01/18/02 Elimination of Local Suppression Pool Temperature Limits 126a 02/15/02 Bases Change - Change reflects relocation of sample point for the offgas radiation monitor 127 05/31/02 Missed Surveillance Requirement Technical Specification Changes 128 06/11/02 Changes to the Technical Specifications Revised Reference Point for Reactor Vessel Level Setpoints, Simplification of Safety Limits, and Improvement to the Bases 128a 07/11/02 Bases Change - Correct Drywell to Suppression Chamber Vacuum Breaker Indicating Light Description
- 1.
License Amendment or Order for Modification of License not affecting Technical Specifications.
- 2.
Technical Specification change issued prior to 10 CFR revisions which require issuance of Technical Specification changes as License Amendments.
- 3.
Modification to Bases. No Technical Specification change or License Amendment issued.
- 4.
Technical Specification change numbers no longer assigned beginning with Amendment 15.
- 5.
Pages reissued 11/25/97 to conform with NRC version. Revision number of effected pages not changed.
- 6.
All pages reissued using INTERLEAF in different font. Using NRC Amendment Nos. and issue date. For Bases and Table of Contents, spelling errors corrected and editorial corrections made and all Amendment Nos. changed to 1 00a. For remaining Tech Spec pages, no other changes made and current Amendment Nos. used.
Amendment No. 128a 07/11/02 Maior Subject Fire Protection Technical Specification Changes Bases Change - Added information on cooldown rate Relocation of Radiological Effluent Technical Specifications to a Licensee-Controlled Program Clarify air ejector offgas activity sample point and operability requirements Relocation of Inservice Testing Requirements to a Licensee-Controlled Program Bases Change - Remove scram setpoints sentence and correct typo Control Rod Drive and Core Monitoring Technical Specification Changes Bases Change - Change to reflect new operation of drywell to suppression chamber vacuum breaker valve position indicating lights Relocation of Technical Specification Administrative Controls Related to Quality Assurance Plan Bases Change - Change to reflect revised Technical Specification definition of a containment spray/cooling subsystem