Letter Sequence Other |
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TAC:MC4951, Removal of Monthly Operating Report and Occupational Radiation Exposure Report (Open) |
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Category:Technical Specifications
MONTHYEARML23033A1032023-01-27027 January 2023 Supplement to License Amendment Request - Proposed Changes to TMl-2 Possession Only License and Technical Specifications ML22087A3942022-03-28028 March 2022 Supplemental Information Supporting License Amendment Request - Proposed Revision to License Conditions and Permanently Defueled Technical Specifications for Permanent Removal of Irradiated Fuel from the Spent Fuel Pool (ISFSI-Only Technica ML21118A0572021-04-13013 April 2021 Submittal of Changes to Technical Specifications Bases ML20352A3812020-12-18018 December 2020 TMI-2 License Transfer Conforming Amendment ML20261H9252020-12-0202 December 2020 Issuance of Amendment No. 299 for Unit 1 Permanently Defueled Emergency Plan and Emergency Action Level Scheme Changes ML19065A1142019-04-18018 April 2019 Issuance of Amendment No. 296 for Unit 1 Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML19065A2172019-03-0606 March 2019 Supplement - License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML15225A1582015-10-0101 October 2015 Issuance of Amendment for Temporary Restoration of the Borated Water Storage Tank Cleanup and Recirculation Operation (TAC No. 6504) ML15090A5842015-07-28028 July 2015 Issuance of Amendments Technical Specifications to Modify Reactor Coolant System Pressure Isolation Check Valve Maximum Allowable Leakage Limits ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) TMI-15-072, Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limts2015-06-10010 June 2015 Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limts TMI-15-064, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2015-05-0707 May 2015 Supplement to the Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process TMI-13-033, Technical Specification Change Request 352, Revise Technical Specification 3.14.2 and the Licensing Basis Flood Hazard Contained in the Updated Final Safety Analysis Report2013-04-10010 April 2013 Technical Specification Change Request 352, Revise Technical Specification 3.14.2 and the Licensing Basis Flood Hazard Contained in the Updated Final Safety Analysis Report TMI-12-169, Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements2013-02-0404 February 2013 Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements TMI-12-064, Supplemental Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications2012-04-11011 April 2012 Supplemental Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications TMI-11-171, Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications2012-01-20020 January 2012 Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications TMI-11-103, License Amendment Request to Revise Technical Specifications to Incorporate Administrative Changes2011-10-18018 October 2011 License Amendment Request to Revise Technical Specifications to Incorporate Administrative Changes TMI-10-035, Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves2010-09-24024 September 2010 Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves ML1003204932010-03-11011 March 2010 License Amendment Technical Specification Changes Adopting TSTF-490-A, Revision 0, Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification ML0927104632009-10-22022 October 2009 Renewed Facility Operating License ML0927104012009-10-22022 October 2009 Issuance of Renewed Facility Operating License No. DPR-50 for Three Mile Island, Unit 1 TMI-09-082, Response to Request for Additional Information Related to License Amendment Request No. 326 to Adopt TSTF-490-A, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical....2009-07-0202 July 2009 Response to Request for Additional Information Related to License Amendment Request No. 326 to Adopt TSTF-490-A, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical.... ML0831201222008-11-0606 November 2008 License Amendment Request No. 326 to Adopt TSTF-490-A, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification Using the Consolidated Line Item Improvement.. ML0828001742008-09-29029 September 2008 Technical Specification Change Request No. 342 Control Rod Drive Control System Upgrade and Elimination of the Axial Power Shaping Rods ML0827402962008-09-15015 September 2008 Supplement: Technical Specification Change Request for Technical Specification Change Request (Tscr) No. 86 Deletion of Technical Specification Sections 6.5, Review and Audit ML0824703052008-08-28028 August 2008 Technical Specifications, TSTF Change Traveler TSTF-479 & TSTF-497 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0821301362008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Tech Spec Pages for Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008 Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours. ML0809101272008-04-16016 April 2008 Technical Specifications to Amendment ML0807700842008-03-14014 March 2008 Additional Information for Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008 Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications ML0727100352007-09-27027 September 2007 Tech Spec Pages for Amendment 261 Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process and Generic Letter 2006-01 ML0726904252007-09-26026 September 2007 Tech Spec Pages for Amendment 260 Regarding Relocation of Technical Specification Requirements for Refueling and Spent Fuel Pool Area Radiation Monitors ML0725402542007-09-0404 September 2007 Additional Information - Technical Specification Change Request No. 331: Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators2007-07-19019 July 2007 Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML0718003192007-06-29029 June 2007 Tech Spec Pages for Amendment 259, One-Time Type a Test Interval Extension ML0715606022007-06-0505 June 2007 Response to Request for Additional Information Concerning Technical Specifications Change Request No. 334 - One-Time Type a Test Interval Extension ML0715202332007-05-31031 May 2007 Response to Request for Additional Information - Technical Specification Change Request No. 331 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0715202292007-05-31031 May 2007 Additional Information - Technical Specification Change Request No. 333, Relocation of Technical Specification Requirements for Refuel and Spent Fuel Pool Area Radiation Monitors. ML0712302682007-04-27027 April 2007 Submittal of Changes to Technical Specification Bases ML0708609682007-03-22022 March 2007 Technical Specification Change Request No. 335, Incorporating Revised Limit or the Variable Low Reactor Coolant System Pressure-Temperature Core Protection Safety Limit ML0628303312006-10-0606 October 2006 Response to Request for Additional Information, Technical Specification Change Request No. 331: Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0626800402006-09-15015 September 2006 Technical Specifications Change Request No. 334 - One-Time Type a Test Interval Extension ML0614202942006-05-15015 May 2006 Technical Specification Change Request No. 331 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0610100612006-04-0808 April 2006 Technical Specification Page Allowed Outage Time Extension from 7 Days to 10 Days for Emergency Diesel Generator EG-Y-1A ML0528702192005-10-13013 October 2005 Issuance of Amendment Elimination of Containment Equipment Hatch Closure Requirement During Refueling, Technical Specifications ML0522703622005-08-12012 August 2005 Tech Spec Pages for Amendment 256 Missed Surveillance Criteria Requirements and Addition of a Technical Specifications Bases Control Program ML0522304032005-08-10010 August 2005 Technical Specification Pages Extension of Reactor Trip System and Reactor Trip Device Functional Test Intervals ML0517506582005-06-17017 June 2005 Tech Spec Pages for Amendment - Monthly Operating Reports and Annual Occupational Radiation Reports 2023-01-27
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3.24 Reactor Vessel Water Level Indication Aniolicability Applies to the operability requirements for the Reactor Vessel Water Level Indication when the reactor is critical.
Objectives To assure operability of the Reactor Vessel Water Level instrumentation which may be useful in diagnosing situations which could represent or lead to inadequate core cooling.
Specification Two channels of the Reactor Vessel Water Level Instrumentation System shall be OPERABLE.
If one channel becomes INOPERABLE that channel shall be returned to OPERABLE within 30 days. If the channel is not restored within 30 days, within 14 days, submit a special report to the NRC providing the details of the inoperability, to include cause, action being taken and projected date for return to OPERABLE status.
With no channels OPERABLE, one channel shall be restored to OPERABLE status within 7 days. If at least one channel is not restored within 7 days, within 14 days, submit a special report to the NRC providing the details of the inoperability, to include cause, action being taken and projected date for return to OPERABLE status.
Bases The Reactor Vessel Water Level Indication (Reference 1) provides indication of the trend in water inventory in the hot legs and reactor vessel during the approach to inadequate core cooling (ICC). In this manner additional information may be available to the operator to diagnose the approach of ICC and to assess the adequacy of responses taken to restore core cooling.
Each Reactor Vessel Water Level channel is comprised of a hot leg level indication and a reactor vessel level indication.
The system is required to be operable (as defined previously) when the plant is critical.
The system is an information system to aid the operator during the approach to inadequate core cooling. There is not regulatory limit for this system.
Inoperability of the system removes the availability of an information system. Other useful instrumentation for inadequate core cooling will be available. The Subcooling Margin Indication System is relied upon to determine subcooling margin when the reactor coolant pumps are operating or when natural circulation can be verified. When natural or forced circulation cannot be verified, the margin to saturation is determined by manual calculation, based on reactor coolant temperature (incore thermocouples) and pressure indications available in the control room and steam tables. See Tech. Spec. 3.5.5.
3-128 Amendment No. 147, 1',, 191, 254
6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Administrator of the NRC Region 1 Office unless otherwise noted.
6.9.1 Routine Reports A. Startug Report. A summary report of plant startup and power escalation testing shall be submitted following (1)receipt of an operating license, (2)amendmemi to the license involving a planned increase in power level, (3)installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4)modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests Identified in the UFSAR, Chapter 13 and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
Startup reports shall be submitted within (i) 90 days following completion of the startup test program, (2)90 days following resumption or commencement of commercial power operation, or (3)9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
B. Annual Reports. Annual reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 1of each year. (Asingle submittal maybe made for the station. The submittal should combine those sections that are common to both units at the station.)
- 1. DELETED
- 2. The following information on aircraft movements at the Harrisburg International Airport:
- a. The total number of aircraft's movements (takeoffs and landings) at the Harrisburg International Airport for the previous twelve-month period.
- b. The total number of movements of aircraft larger than 200,000 pounds at the Harrisburg International Airport for the previous twelve-month period, broken down into scheduled and non-scheduled (including military) takeoffs and landings, based on a current estimate provided by the airport manager or his designee.
6-12 Amendment No. 42, 37, 77, 157, 180, 254
- 3. The following information from the periodic Leak Reduction Program tests shall be reported:
- a. Results of leakage measurements,
- b. Results of visual inspections, and
- c. Maintenance undertaken as a result of Leakage Reduction Program tests or inspections.
- 4. The following information regarding pressurizer power operated relief valve and pressurizer safety valve challenges shall be reported:
- a. Date and time of incident,
- b. Description of occurrence, and
- c. Corrective measures taken if incident resulted from an equipment failure.
- 5. The following information regarding the results of specific activity analysis in which the primary coolant exceeded limits of Technical Specifications 3.1.4.1 shall be reported:
- a. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded;
- b. Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radioiodine concentrations;
- c. Cleanup system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample Inwhich the limit was exceeded;
- d. Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and
- e. The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
C. DELETED 6.9.2 DELETED 6-13 (Pages 6-14, 6-15, and 6-16 deleted)
Amendment No. 11, 37,72, 7-7, 82, 117, 129, 254