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 Committed to NuclearExceUl]enc Monticello Nuclear Generating Plan 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 controlling the red lights are adjusted to provide an indication of disc opening of less than 1/8" each valve. The two switches 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 alarm cannot be cleared due to the inability to establish indication of closure of one or more valves, status, or both. If the 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 Amend Amend Amend Page No. Paae No. Page No. Page No.
A 128a 37 128 72 104 124 121 B 128a 38 128 76 0 125 104 C 115 39 128 77 86 126 104 D 115 40 128 78 0 126a 87 E 115 42 103 79 0 127 128 F 115 45 0 80 29 128 42 G 115 46 70 81 3 129 122 H 119 46a 37 82 123 130 82 I 128a 47 40 82a 63 131 122 i 128 48 89 83 24 132 39 ii 104 49 128 83a 24 132a 122 iii 120 50 128 84 100a 133 106 iv 128 50a 117 85 100a 134 106 v 120 51 117 86 100a 135 106 vi 121 51a 117 87 100a 136 106 vii 122 52 128 88 100a 137 0 1 119 53 128 89 104 138 100a 2 70 54 128 90 100a 145 118a 3 21 55 103 91 123 146 106 4 102 56 102 92 100a 147 107 5 120 57 70 93 122 148 117 5a 120 58 84 94 106 149 100a 6 128 58a 29 95 77 150 128 7 128 59 128 96 77 151 128 8 128 59a 103 97 57 153 100a 9 128 60 128 98 56 154 100a 10 128 60a 31 99 104 155 122 11 128 60b 62 100 100a 156 93 12 128 60c 30 101 122 157 117 25a 127 60d 128 102 122 158 107 25b 127 60e 89 103 122 159 95 25c 127 61 104 104 122 160 95 25d 127 62 117 105 122 163 0 26 5 63 117 106 79 164 104 27 81 63a 117 107 97 165 64 27a 81 64 128 108 128 166 94 28 128 65 117 109 100a 167 112 29 128 66 119a 110 100a 168 94 30 103 67 117 111 122 169 94 31 104 68 102 112 124a 170 122 32 103 69 118a 113 122 171 96 33 103 69a 100a 114 122 172 71 34 83 70 117 121 0 175 107 35 100a 71 100a 122 106 175a 117 36 128 71 a 105 123 117 176 100a A
Amendment No. 128a 07/11/02
MONTICELLO NUCLEAR GENERATING PLANT APPENDIX A TECHNICAL SPECIFICATIONS RECORD OF REVISIONS Amend Amend Page No. Page No.
177 117 229a 63 178 100a 229b 104 179 123a 229c 104 180 128a 229d 63 181 100a 229e 122 182 112 229u 104 183 117 229v 112 184 100a 229v v 112 185 100a 229w 112 188 104 229ww 112 189 100a 229x 112 190 104 229y 115a 191 0 229z 112 192 121 230 54 193 121 231 34 196 126a 232 119 197 121 233 124 198 121 234 119 199 51 235 115 200 104 236 115 201 77 243 128 202 80 244 124 203 41 248 59 204 100a 249 120 205 100a 250 128 206 0 251 124 207 123 252 120 208 63 253 120 209 123 254 120 209a 100a 255 120 210 100a 256 122 211 109 257 122 212 109 258 122 213 99 259 120 216 100a 260 120 217 128 261 120 218 120 262 120 223 119 224 119 225 119 226 119 B
Amendment No. 128a 07/11/02
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP Page License AEC Tech Spec Revision DPR-22 Change Issuance (REV' No. Amend No. & Date No. and date Major Subject Original Appendix A Technical Specifications incorporated in DPR-22 on 9/8/70 1 1/19/71 Note 1 Removed 5 MWt restriction Note 2 2 1/14/72 MOGS Technical Specification changes issued by AEC but never distributed or put into effect, superseded by TS Change 12 11/15/73 1 Note 2 3 10/31/72 RHR service water pump capability change Note 2 4 12/8/72 Temporary surveillance test waiver 2 2/20/73 Note 1 Increase in U-235 allowed in fission chambers 2 Note 2 5 3/2/73 Miscellaneous Technical Specification changes, 3 Note 2 1 4/28/71 & Respiratory Protection, & Administrative Control 6 4/3/73 Changes 4 Note 2 7 5/4/73 Respiratory Protection Changes 5 Note 2 8 7/2/73 Relief Valve and CRD Scram Time Changes 6 Note 2 9 8/24/73 Fuel Densification Limits 7 Note 2 10 10/2/73 Safety Valve Setpoint Change 8 Note 2 11 11/27/73& Offgas Holdup System, RWM, and 12 11/15/73 Miscellaneous Changes 9 Note 2 13 3/30/74 8x8 Fuel Load Authorization 10 3 14 5/14/74 8x8 Full Power authorization 4 6/17/74 Note 1 Changed byproduct material allowance 6 8/20/74 Note 1 Changed byproduct material allowance 11 Note 3 Note 3 10/24/74 Inverted Tube (CRD) Limits 12 5 15 1/15/75 REMP Changes 13 7 16 2/3/75 Reactor Vessel Surveillance Program Changes 14 8 17 2/26/75 Vacuum Breaker Test Changes 15 9 18 4/10/75 Corrects Errors & Provides Clarification 10 7/8/75 Note 1 Increased allowed quantity of U-235 16 12 20 9/15/75 Snubber Requirements 17 11 19 9/17/75 Removed byproduct material allowance 18 13 21 10/6/75 Suppression Pool Temperature Limits 19 14 22 10/30/75 Appendix K and GETAB Limits 20 15 1/22/76 NOTE 4 Reporting Requirements 21 16 2/3/76 CRD Collet Failure Surveillance 22 17 3/16/76 NSP Organization Changes 23 NOTE 3 4/13/76 Adoption of GETAB 24 18 4/14/76 Containment Isolation Valve Testing 25 21 5/20/76 Interim Appendix B, Section 2.4 Tech. Specs.
C Amendment No. 115 I
12/21/00
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP License Revision DPR-22 (REV) No. Amend No. & Date Major Subject 26 19 5/27/76 Low Steamline Pressure Setpoint and MCPR Changes 27 20 6/18/76 APLHGR, LHGR, MCPR Limits 28 22 7/13/76 Correction of Errors and Environmental Reporting 29 23 9/27/76 Standby Gas Treatment System Surveillance 30 24 10/15/76 CRD Test Frequency 31 25 10/27/76 Snubber Testing Changes 32 26 4/1/77 APRS Test Method 33 27 5/24/77 MAPLHGR Clamp at Reduced Flow 34 28 6/10/77 Radiation Protection Supervisor Qualification 35 29 9/16/77 REMP Changes 36 30 9/28/77 More Restrictive MCPR 37 31 10/14/77 Inservice Inspection Changes 38 32 12/9/77 Reporting Requirements 39 33 1/25/78 Fire Protection Requirements NOTE 1 34 4/14/78 Increase in spent fuel storage capacity 40 35 9/15/78 RPT Requirements 41 36 10/30/78 Suppression Pool Surveillance 42 37 11/6/78 8x8R Authorization, MCPR Limits & SRV Setpoints 43 NOTE 3 11/24/78 Corrected Downcomer Submergence 44 38 3/15/79 Incorporation of Physical Security Plan into License 45 39 5/15/79 Revised LPCI Flow Capability 46 40 6/5/79 Respiratory Protection Program Changes 47 41 8/29/79 Fire Protection Safety Evaluation Report 48 42 12/28/79 MAPLHGR vs. Exposure Table 49 43 2/12/80 MCPR & MAPLHGR Changes for Cycle 8 and Extended Core Burnup 50 44 2/29/80 ILRT Requirements NOTE 1 - 8/29/80 Order for Modification of License-Environmental Qualification NOTE 1 - 9/19/80 Revised Order for Modification of License-Environmental Qualification 51 - 10/24/80 Order for Modification of License-Environmental Qualification Records 52 - 1/9/81 Issuance of Facility Operating License (FTOL)
NOTE 1 - 1/9/81 Order for Modification of License Concerning BWR Scram Discharge Systems (License conditions removed per Amendment No. 11 dated 10/8/82)
D Amendment No. 115 I
12/21/00
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP License Revision DPR-22 (REVA No. Amend No. & Date Major Subiect NOTE 1 - 1/13/81 Order for Modification Mark I Containment 1 2/12/81 Revision of License Conditions Relating to Fire Protection Modifications 53 2 3/2/81 TMI Lessons Learned & Safety Related Hydraulic Snubber Additions 54 3 3/27/81 Low voltage protection, organization and miscellaneous NOTE 1 4 3/27/81 Incorporation of Safeguards Contingency Plan and Security Force Qualification and Training Plan into License 55 5 5/4/81 Cycle 9 - ODYN Changes, New MAPLHGR's, RPS Response time change 56 6 6/3/81 Inservice Inspection Program 57 7 6/30/81 Fire Protection Technical Specification Changes 58 8 11/5/81 Mark I Containment Modifications 59 9 12/28/81 Inservice Surveillance Requirements for Snubbers NOTE 1 1/19/82 Revised Order for Modification Mark I Containment 60 10 5/20/82 Scram Discharge Volume 61 11 10/8/82 New Scram Discharge Volumes 62 12 11/30/82 RPS Power Monitor 63 13 12/6/82 Cycle 10 64 14 12/10/82 Recirc Piping and Coolant Leak Detection 65 15 12/17/82 Appendix I Technical Specifications (removed App. B) 66 16 4/18/83 Organizational Changes 67 17 4/17/83 Miscellaneous Changes 68 18 11/28/83 Steam Line Temperature Switch Setpoint 69 19 12/30/83 Radiation Protection Program 70 20 1/16/84 SRM Count Rate 71 21 1/23/84 Definition of Operability 72 22 2/2/84 Miscellaneous Technical Specification Changes 73 23 4/3/84 RPS Electrical Protection Assembly Time Delay 74 24 5/1/84 Scram Discharge Volume Vent and Drain Valves 75 25 8/15/84 Miscellaneous Technical Specification Changes 76 26 9/24/84 Cycle 11 77 27 10/31/84 RHR Intertie Line Addition 78 28 11/2/84 Hybrid I Control Rod Assembly 79 29 11/16/84 ARTS 80 30 11/16/84 Low Low Set Logic 81 31 11/27/84 Degraded Voltage Protection Logic E
Amendment No. 115 I
12/21/00
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP License Revision DPR-22 (REV) No. Amend No. & Date Maior Subiect 82 32 5/28/85 Surveillance Requirements 83 33 10/7/85 Screen Wash/Fire Pump (Partial) 84 34 10/8/85 Fuel Enrichment Limits 85 35 12/3/85 Combustible Gas Control System 86 36 12/23/85 Vacuum Breaker Cycling 87 37 1/22/86 NUREG-0737 Technical Specifications 88 38 2/12/86 Environmental Technical Specifications 89 39 3/13/86 Administrative Changes 90 40 3/18/86 Clarification of Radiation Monitor Requirements 91 41 3/24/86 250 Volt Battery 92 42 3/27/86 Jet Pump Surveillance 93 43 4/8/86 Simmer Margin Improvement 94 44 5/27/86 Cycle 12 Operation 95 45 7/1/86 Miscellaneous Changes 96 46 7/1/86 LER Reporting and Miscellaneous Changes 97 47 10/22/86 Single Loop Operation 98 48 12/1/86 Offgas System Trip 99 49 8/26/87 Rod Block Monitor 100 50 8/26/87 APRM and IRM Scram Requirements 101 51 10/16/87 2R Transformer 102 52 11/18/87 Surveillance Intervals - ILRT Schedule 103 53 11/19/87 Extension of Operating License 104 54 11/25/87 Cycle 13 and Misc Changes 105 55 11/25/87 Appendix J Testing 106 56 12/11/87 ATWS - Enriched Boron 107 57 9/23/88 Increased Boron Enrichment 108 58 12/13/88 Physical Security Plan 109 59 2/16/89 Miscellaneous Administrative Changes 110 60 2/28/89 Miscellaneous Administrative Changes 111 61 3/29/89 Fire Protection and Detection System 112 62 3/31/89 ADS Logic and S/RV Discharge Pipe Pressure 113 63 4/18/89 Miscellaneous Technical Specification Improvements 114 64 5/10/89 Containment Vent and Purge Valves 115 65 5/30/89 NUREG-0737 - Generic Letter 83-36 116 66 5/30/89 Reactor Vessel Level Instrumentation F
Amendment No. 115 12/21/00
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP License Revision DPR-22 (REV No. Amend No. & Date Maior Subject 117 67 6/19/89 Extension of MAPLHGR. Exposure for One Fuel Type 118 68 7/14/89 SRO Requirements & Organization Chart Removal 119 69 9/12/89 Operations Committee Quorum Requirements 120 70 9/28/89 Relocation of Cycle-Specific Thermal-Hydraulic Limits 121 71 10/19/89 Deletion of Primary Containment Isolation Valve Table 122 72 11/2/89 RG 1.99, Rev 2, ISI & ILRT 123 73 5/1/90 Combined STA/LSO Position 124 74 6/5/90 Removal of WRGM Automatic ESF Actuation 125 75 10/12/90 Diesel Fuel Oil Storage 126 76 12/20/90 Miscellaneous Administrative Changes 127 77 2/15/91 Redundant and IST Testing 128 78 3/28/91 Alarming Dosimetry 125 79 4/9/91 SAFER/GESTR 130 80 8/12/91 Torus Vacuum Breaker Test Switch/EDG Fuel Oil Tank Level 131 81 4/16/92 Surveillance Test Interval Extension - Part I 132 82 7/15/92 Alternate Snubber Visual Inspection Intervals 133 83 8/18/92 Revisions to Reactor Protection System Tech Specs 134 84 1/27/93 MELLIA and Increase Core Flow 135 85 6/29/93 Revision to Diesel Fire Pump Fuel Oil Sampling Requirements 136 86 7/12/93 Revisions to Control Rod Drive Testing Requirements 137 87 4/15/94 Revised Coolant Leakage Monitoring Frequency 138 88 6/30/94 Average Planar Linear Heat Generation Rate (APLHGR)
Specification & Minimum Critical Power Ratio Bases Revisions 139 89 8/25/94 Removal of Chlorine Detection Requirements and Changes to Control Room Ventilation System Requirements 140 90 9/7/94 Revisions to Radiological Effluent Specifications 141 91 9/9/94 Secondary Containment System and Standby Gas Treatment System Water Level Setpoint Change 142 92 9/15/94 Change in Safety Relief Valves Testing Requirements 143 93 7/12/95 Revised Core Spray Pump Flow 144 94 10/2/95 Standby Gas Treatment and Secondary Containment Systems 145 95 4/3/96 MSIV Combined Leakrate, and Appendix J, Option B 146 96 4/9/96 Purge and Vent Valve Seal Replacement Interval 147 97 9/17/96 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.
G I Amendment No. 115 12/21/00
MONTICELLO NUCLEAR GENERATING PLANT RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSP License Revision DPR-22 (REVA No. Amend No. & Date Mamor Subject 148 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.
149 99 10/29/97 SLMCPR for Cycle 18 and reissue pages vi, 155, 202, 207, 219, 229u NOTE 5 11/25/97 Reissue pages a, b, g, iii, vi, 14, 25a, 155, 198y, 198z, 202, 207, 209, 219, 229k, 229p, 229r, 229u, 230, 245 150 100 4/20/98 SLMCPR for Cycle 19 NOTE 6 100a 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 License Revision DPR-22 (REV) No. Amend No. & Date Maior Subject 119 04/05/01 Fire Protection Technical Specification Changes 119a 06/28/01 Bases Change - Added information on cooldown rate 120 07/24/01 Relocation of Radiological Effluent Technical Specifications to a Licensee-Controlled Program 121 07/25/01 Clarify air ejector offgas activity sample point and operability requirements 122 08/01/01 Relocation of Inservice Testing Requirements to a Licensee-Controlled Program 122a 10/22/01 Bases Change - Remove scram setpoints sentence and correct typo 123 10/26/01 Control Rod Drive and Core Monitoring Technical Specification Changes 123a 10/25/01 Bases Change - Change to reflect new operation of drywell to suppression chamber vacuum breaker valve position indicating lights 124 10/30/01 Relocation of Technical Specification Administrative Controls Related to Quality Assurance Plan 124a 12/05/01 Bases Change - Change to reflect revised Technical Specification definition of a containment spray/cooling subsystem 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