Letter Sequence Acceptance Review |
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MONTHYEARML0233002952003-02-0404 February 2003 Issuance of Amendment 132 License Amendment Request for Conversion to Option B for Containment Leak Rate Testing Project stage: Approval ML0303804272003-02-0404 February 2003 Tech Specs Pages for Amendment No. 132 License Amendment Request for Conversion to Option B for Containment Leak Rate Testing Project stage: Acceptance Review 2003-02-04
[Table View] |
Tech Specs Pages for Amendment No. 132 License Amendment Request for Conversion to Option B for Containment Leak Rate TestingML030380427 |
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Monticello |
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02/04/2003 |
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NRC/NRR/DLPM/LPD3 |
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TAC MB4975 |
Download: ML030380427 (6) |
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Category:Technical Specifications
MONTHYEARML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML22357A1002023-03-31031 March 2023 And Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML22318A2152022-12-27027 December 2022 Issuance of Amendment No. 209 Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank ML21148A2742021-07-12012 July 2021 Issuance of Amendment No. 206 TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20352A3492021-01-0808 January 2021 Issuance of Amendment No. 205, Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-582, RPV WIC Enhancements, and TSTF-583-T, TSTF-582 Diesel Generator Variation ML20210M0142020-09-0808 September 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules ML19176A4212019-08-29029 August 2019 Issuance of Amendment No. 203 Adoption of 10 CFR 50.69 ML19162A0932019-07-30030 July 2019 Issuance of Amendment No, 202 Regarding Deletion of the Note Associated with Technical Specification 3.5.1., Erccs - Operating ML18291B2142018-11-26026 November 2018 Issuance of Amendment Adoption of TSTF-551 Revise Secondary Containment Surveillance Requirements L-MT-18-060, License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.12018-11-12012 November 2018 License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.1 L-MT-18-006, Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements2018-07-0303 July 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML17346A0852017-12-12012 December 2017 Final Pre-App TS Markups ML17250A8712017-09-0707 September 2017 MNGP TSTF-542 TS Draft Markups ML17250A8702017-09-0707 September 2017 MNGP TSTF-542 Draft Variations ML17172A4312017-06-23023 June 2017 Correction of Amendment No. 194, Issuance of Amendment to Adopt F Tstf 545, Revision 3, Ts Inservice Testing Program Removal & Clarify Sr Usage Rule Application to Section 5.5 Testing ML17123A3212017-06-16016 June 2017 Issuance of Amendment Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing ML15335A4932015-11-20020 November 2015 Technical Requirements Manual, Revision 17 L-MT-15-032, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure2015-09-0202 September 2015 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure ML15072A1412015-06-0505 June 2015 Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods L-MT-15-043, Withdrawal of License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure2015-05-29029 May 2015 Withdrawal of License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure ML15110A2802015-04-15015 April 2015 Operating License and Technical Specifications ML14323A0332015-01-0808 January 2015 Issuance of Amendment No. 187 Regarding Revision to TS 5.5.11 for Drywell Personnel Airlock Leakage Rate Testing ML14281A3182014-11-25025 November 2014 Issuance of Amendment Regarding Reduction in Steam Dome Pressure Safety Limit L-MT-14-088, Areva Atrium 10XM Fuel Transition License Amendment Request Supplement2014-11-11011 November 2014 Areva Atrium 10XM Fuel Transition License Amendment Request Supplement ML14246A4492014-11-0303 November 2014 Issuance of Amendment to Revise TS 3.5.1, ECCS - Operating L-MT-14-043, License Amendment Request for Fuel Storage Changes Supplement to Proposed Spent Fuel Pool Boral Monitoring Program Technical Specification2014-05-30030 May 2014 License Amendment Request for Fuel Storage Changes Supplement to Proposed Spent Fuel Pool Boral Monitoring Program Technical Specification ML14035A2482014-03-28028 March 2014 Issuance of Amendment No. 180 to Implement Maximum Extended Load Line Limit Analysis Plus (Mellla+) Operating Domain ML14072A3902014-03-13013 March 2014 License Amendment Request for Fuel Storage Changes, Supplement to Propose a Spent Fuel Pool Boral Monitoring Program Technical Specification ML13218A0612014-01-28028 January 2014 Issuance of Amendment No. 178 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML13316B2982013-12-0909 December 2013 Issuance of Amendment No. 176 to Renewed Facility Operating License Regarding Extended Power Uprate ML13168A3732013-08-28028 August 2013 Issuance of Amendment No. 175 to Make Minor Corrections and Editorial Changes, Clarify Fuel Storage Capacity, and Remove Obsolete Information ML13168A2192013-08-0909 August 2013 Issuance of Amendment No. 174 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities L-MT-13-055, License Amendment Request for Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methodology2013-07-15015 July 2013 License Amendment Request for Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methodology ML13189A1942013-06-27027 June 2013 Operating License and Technical Specifications Updating Instructions L-MT-13-030, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs2013-04-19019 April 2013 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs L-MT-12-076, License Amendment Request for Fuel Storage Changes2012-10-30030 October 2012 License Amendment Request for Fuel Storage Changes L-MT-12-071, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2012-09-18018 September 2012 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. L-MT-12-055, License Amendment Request: Revise Renewed Facility Operating License & Technical Specifications to Clarify Fuel Storage Capacity, Remove Obsolete Information and Make Minor Corrections and Miscellaneous Editorial Changes2012-08-21021 August 2012 License Amendment Request: Revise Renewed Facility Operating License & Technical Specifications to Clarify Fuel Storage Capacity, Remove Obsolete Information and Make Minor Corrections and Miscellaneous Editorial Changes L-MT-12-051, License Amendment Request: Remove Degraded Voltage Transfer to the 1AR Transformer2012-05-25025 May 2012 License Amendment Request: Remove Degraded Voltage Transfer to the 1AR Transformer L-MT-12-028, License Amendment Request: Revise Allowable Value for the Automatic Depressurization System Bypass Timer2012-04-0505 April 2012 License Amendment Request: Revise Allowable Value for the Automatic Depressurization System Bypass Timer ML12083A2522012-03-22022 March 2012 Enclosure 2 - Monticello Nuclear Generating Plant Technical Requirements Manual Revision 10 L-MT-11-022, 002 Monticello - Technical Requirements Manual, Revision 72011-04-27027 April 2011 002 Monticello - Technical Requirements Manual, Revision 7 L-MT-09-047, Supplement to Extended Power Uprate License Amendment Request: Revision to Proposed Technical Specification Changes in Response to Staff Comments2009-08-31031 August 2009 Supplement to Extended Power Uprate License Amendment Request: Revision to Proposed Technical Specification Changes in Response to Staff Comments L-MT-09-020, License Amendment Request: Revise the Modes of Applicability for Reactor Water Cleanup System Isolation on a Standby Liquid Control System Initiation2009-05-29029 May 2009 License Amendment Request: Revise the Modes of Applicability for Reactor Water Cleanup System Isolation on a Standby Liquid Control System Initiation L-MT-09-041, Supplement to License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function2009-04-0202 April 2009 Supplement to License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function ML0834406812009-01-30030 January 2009 (Mngp), License Amendment No. 159 Regarding the Power Range Neutron Monitoring System L-MT-08-012, License Amendment Request: Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2008-04-22022 April 2008 License Amendment Request: Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process L-MT-08-013, License Amendment Request: Application for Technical Specification Change TSTF-427, Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process2008-04-0404 April 2008 License Amendment Request: Application for Technical Specification Change TSTF-427, Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML0810101932008-03-31031 March 2008 Monticello, License Amendment Request: Extended Power Uprate ML0802806012008-01-30030 January 2008 Technical Specifications 2024-10-01
[Table view] |
Text
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS
- - . . . -. * - ,iI ,i
- 2. Pnmary Containment Integnty 2. rinmary Containmen integnriy
- a. (1) Primary Containment Integrity as defined in a. Perform required visual examinations and Section 1, shall be maintained at all times leakage rate testing except for primary when the reactor Is critical or when the containment air lock testing, In accordance with reactor water temperature Is above 212°F the Primary Containment Leakage Rate Testing and fuel Is In the reactor vessel; except as Program.
specified In 3.7.A.2.a.(2) or 3.7.A.2.a.(3).
(2) Primary Containment Integrity Is not required when performing low power physics tests at atmospheric pressure during or after refueling at power levels not to exceed 5 MW(t).
(3) Primary Containment Integrity Is not required when performing reactor vessel hydrostatic or leakage tests with the reactor not critical.
(4) If requirements of 3.7.A.2.a.(1) cannot be met, restore Primary Containment Integrity within one hour or be in at least Hot Shutdown within the next 12 hotrs and Cold Shutdown within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
3.7/4.7 158 Amendment No. 30,55, ,6, 95, 4.w, 132
3.0 UMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS
- b. Deleted I I b. Deleted 159 132 3.7/4.7 Amendment No. 6.2,557245,
3.0 UMITING CONDITONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 IMIINGCONDONSFOROPERTIO 4. SUREILANC REQIREENT
- c. When Primary Containment Integrity Is c, (1) Perform required primary containment air required, the primary containment air lock shall lock leakage rate testing In accordance with the Containment Leakage Rate I
be operable with both doors*closed except when the air lock Is being used, then at least Testing Program.(*)*)
one air lock door shall be closed.
(2) Once per 24 months, verify that only one With the'primary containment air lock door In the primary containment air lock Inoperable, maintain at least one air lock door can be opened at a time.
closed and restore the air lock to Operable status within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> or be in at least Hot d. The Interior surfaces of the drywall shall be Shutdown within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and in Cold visually Inspected each operating cycle for Shutdown within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. evidence of deterioration.
- An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.
- Results shall be evaluated against acceptance criteria applicable to SR 4.7.A.2.a.
3.7/4.7 .NEXT PAGE IS 163 160 0 Amendment No. 65, 60, 9 132
Bases 4.7 (Continued):
On September 26, 1995, Regulatory Guide 1.163 became effective providing guidance on performance based testing to the requirements*of 10 CFR 50, Appendix J, Option B. Monticello has adopted 10 CFR Part 50, Appendix J, Option B, and a Primary Containment Leakage Rate Testing Program.
Maintaining primary containment Integrity requires compliance with the visual examinations and leakage rate test requirements of the Primary Containment Leakage Rate Testing.Program. Failure to meet air lock leakage testing, primary containment purge valve resilient seal leakage testing or main steam isolation valve leakage does not necessarily result in a failure of this SR. The Impact of the failure to meet these SRs must be evaluated againstthe Type A, B and C acceptance criteria of the Pdmarý Containment Leakage Rate Testing Program.
Maintaining primary containment air locks requires compliance with the leakage rate testing requirements of the Primary Containment Leakage Rate Testing Program. This SR reflects the leakage rate testing requirements with respect to air lock leakage (Type B leakage tests). The periodic testing requirements verify that the air lock leakage does not exceed the allowed fraction of the overall primary containment leakage rate. The frequency Is required by the Primary Containment Leakage Rate Testing Program.
The SR has been modified by two footnotes. Note
- states that an Inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test. This is considered reasonable since either air lock door is capable of providing a fission barrier in the event of a DBA. Note ** has been added to this SR requiring the results to be evaluated against the acceptance criteria which is applicable to Primary Containment Integrity. This ensures that the air lock leakage is properly accounted for in determining the combined Type B and C primary containment leakage.
and air The lockdoors outer Interlock of anmechanism designedto towithstand air lock areIsdesigned prevent simultaneous expectedofpost the maximum opening bothaccident doors inprimary the air lock. Since both containment the Inner pressure, closure of either door will support primary containment Integrity. Thus, the interlock feature supports primary containment Integrity while the air lock is being used for personnel transit In and out of the containment. Periodic testing of the interlock demonstrates that the Interlock will function as designed and that the simultaneous Inner and outer door opening will not inadvertently occur. Due to the Ipurelymechanicai nature of this Interlock, and given that the interlock mechanism is not normally challenged when primary containment airlock door Is used for entry and exit (procedures require strict adherence to single door opening), this test is only required to be performed. every 24 months. The 24 month frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage, and the potential for loss of primary containment Integrity if the Surveillance were performed with the reactor at power. The 24 month frequency Is based on engineering Judgment and is considered adequate given that the Interlock Is not challenged during the use of the air lock.
4.7 BASES NEXT PAGE IS PAGE 188 185 Amendment No. 05,,00 132
6.8.J -RESERVED K Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
- 1. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- 2. Changes to Bases may be made without prior NRC approval provided the changes do not involve either of the following:
- a. a change In the TS incorporated In the license; or
- b. a change to the USAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
- 3. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the USAR.
- 4. Proposed changes to the Bases that Involve changes as described In a. or b. of Specification 6.8.K.2 above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases Implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
6.8.L - RESERVED M. PrimarynContainment Leakage Rate Testing Program
- 1. This program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J, Option B, as modified by approved exemptions. This program shall be In accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995.
- 2. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 42 psig. The containment design pressure Is 56 psig.
6.8 258 Amendment No. 420,1422 132
- 3. The maximum allowable containment leakage rate, La, at Pa, shall be 1.2% of containment air weight per day.
- 4. Leakage rate acceptance criteria are:
- a. Containment leakage rate acceptance criterion Is < 1.0 La. During the first unit startup following testing In accordance with this program, the leakage rate acceptance criteria are <0.60 La for the Type B and C tests and :50.75 La for Type A tests.
- b. Air lock testing acceptance criteria are:
- 1) Overall air leakage rate is < 0.05 La when tested at ;- Pa.
- 2) For each door, leakage rate Is < 0.007 La when pressurized to >10 psig.
- 5. The provisions of SRs 4.0.D and 4.0.E are applicable to the Primary Containment Leakage Rate Testing Program.
- 6. Nothing In these Technical Speciications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.
6.8 258a Amendment No.1 132 2