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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211H4311999-08-27027 August 1999 Revised Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints ML20210L1631999-08-0404 August 1999 Proposed Tech Specs,Ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification to 4 H Prior to Commencing Backfill Operation ML20212J3041999-06-22022 June 1999 Proposed Tech Specs Re Revised Surveillance Frequency & Action Times Reactor Trip & ESFAS ML20206N3691999-05-0606 May 1999 Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic ML20206G8811999-05-0303 May 1999 Proposed Tech Specs,Increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20206H0301999-05-0303 May 1999 Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing ML20206G8361999-05-0303 May 1999 Proposed Tech Specs,Deleting &/Or Relocating Addl primary- to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20203C8251999-02-0505 February 1999 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Operability ML20198J0971998-12-22022 December 1998 Proposed Tech Specs Bases Changes Re EDG Steady State Frequency to Be Incorporated Into TS During Implementation of Amends 216 & 197 ML20195J4431998-11-18018 November 1998 Proposed Tech Specs Re Revs to Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9461998-11-10010 November 1998 Proposed Tech Specs,Clarifying Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20154P2831998-10-16016 October 1998 Marked-up & Typed Tech Spec Pages to Revise EDG Section to Be Consistent with Station Procedures Associated with Steady State Conditions & W NSAL 93-022,for 980728 Application for Amends to Licenses NPF-4 & NPF-7 ML20153H5341998-09-24024 September 1998 Proposed Tech Specs 3/4.5.1 Re Safety Injection Accumulator Boron Concentration Verification ML20236U8711998-07-28028 July 1998 Proposed Tech Specs,Revising EDG Section to Be Consistent W/ Station Procedures Associated W/Steady State Conditions & W Nuclear Safety Advisory Ltr NSAL 93-022 ML20236U8411998-07-28028 July 1998 Proposed Tech Specs 4.6.2.2.1 & 4.6.2.2.2,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20236U8651998-07-28028 July 1998 Proposed Tech Specs 3/4.1.2 & 3/4.5.5,re RWST & Boron Concentration Ph Range Bases Change to Address Discrepancies Between Previous NRC Issued Ser,Ts Bases & Applicable Sections of SRP ML20249C7211998-06-19019 June 1998 Proposed Improved Tech Specs for North Anna ISFSI ML20217E9011998-03-25025 March 1998 Proposed Tech Specs Re Configuration Risk Mgt Program for risk-informed Allowed Outage Times & Insp Frequency of EDGs ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20202E1551998-02-0909 February 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20202C5871998-02-0303 February 1998 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insps & Loop Flow Straightener Insps ML20202C3381998-02-0303 February 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20199G4161997-11-18018 November 1997 Revised Proposed TS Pages,Establishing 14 Day AOT Applicable Whenever EDG Is Inoperable ML20199H4001997-11-18018 November 1997 Proposed Tech Specs Permitting Quarterly Testing of Turbine Governor & Throttle Valves ML20199A1481997-11-0505 November 1997 Proposed Tech Specs Pages,Providing Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20141F3741997-05-14014 May 1997 Proposed Tech Specs Revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided for TS 3/4.7.1.7 ML20137C8581997-03-18018 March 1997 Proposed Tech Specs Re Containment Gaseous & Particulate Radiation Monitors ML20134J4141997-02-0404 February 1997 Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2 ML20134F1231997-02-0303 February 1997 Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2 ML20132E6211996-12-17017 December 1996 Proposed Tech Specs 3/4.7.3 Re Component Cooling Water Sys ML20132B5111996-12-10010 December 1996 Proposed Tech Specs Re Groundwater Level Exceeding Current Maximum Water Level ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML20134H0051996-11-0606 November 1996 Proposed Tech Specs,Modifying Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves ML20134F8781996-09-0404 September 1996 Proposed Tech Specs Requiring Exemption from Certain Requirements of 10CFR50.44, Stds for Combustible Gas Control Sys in Light Water Cooled Power Reactors & 10CFR50.46, Acceptance Criteria for Eccs.. ML20107L3951996-04-25025 April 1996 Proposed Tech Specs,Providing Suppl Info Re Clarification of TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20101Q0871996-04-0808 April 1996 Proposed Tech Specs Re EDG Allowed Outage Times ML20101F7971996-03-21021 March 1996 Proposed Tech Specs,Clarifying Requirements for Testing Charcoal Adsorbent in Waste Gas Charcoal Filter Sys,Cr Emergency Habitability Sys & Safeguards Area Ventilation Sys ML20097C0171996-01-31031 January 1996 Proposed Tech Specs,Revising Current Minimum EDG Fuel Oil Day Tank Vol & Allowing Credit to Be Taken for Surveillance Testing Performed During Power to Satisfy Portions of SRs Required During Shutdown ML20097J4341996-01-30030 January 1996 Proposed Tech Specs,Modifying Table 3.2-1 of TS 3.2.5 to Increase Minimum Allowable RCS Total Flow Rate from 284,000 Gpm & 275,000 Gpm to 295,000 Gpm ML20096G9871996-01-23023 January 1996 Proposed Tech Specs,Permitting Use of 10CFR50,App J,Option B performance-based Containment Lrt ML20094N7921995-11-20020 November 1995 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Leakage Rate Testing ML20094D0191995-10-25025 October 1995 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Inoperability ML20093K5921995-10-17017 October 1995 Proposed TS 4.4.5.1,Table 4.4-1,reducing from Two to One Min Number of SGs Required to Be Inspected During First ISI Following SG Replacement ML20093K6161995-10-17017 October 1995 Proposed Tech Specs,Allowing Both Containment Personnel Airlock Doors to Remain Open During Refueling Operations ML20092J4231995-09-19019 September 1995 Proposed Tech Specs,Increasing Surveillance Test Interval & Extending Visual & Surface Insps for Turbine Reheat Stop & Intercept Valves ML20092J3051995-09-19019 September 1995 Proposed Tech Specs,Revising Maximum Allowable Power Range Neutron Flux High Setpoints for Operation W/Inoperable MSSV ML20092A2481995-09-0101 September 1995 Proposed Tech Specs,Allowing Single Outage of Up to 14 Days for Each EDG Once Every 18 Months ML20087A1171995-07-26026 July 1995 Proposed Tech Specs,Increasing Pressurizer Safety Valve Lift Setpoint Tolerance as Well as Reduce Pressurizer High Pressure Rt Setpoint & Allowable Value ML20087A1311995-07-26026 July 1995 Proposed Tech Specs,Clarifying TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20087G3471995-03-30030 March 1995 Proposed Tech Specs Re Changes That Allow One of Two Svc Water Loops to Be Isolated from Component Cooling Water Heat Exchangers During Power Operationin Order to Refurbish Isolated Svc Water Headers 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211H4311999-08-27027 August 1999 Revised Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints ML20211D9201999-08-20020 August 1999 Revised Pages to Third Ten Year ISI Program & Relief Requests ML20210L1631999-08-0404 August 1999 Proposed Tech Specs,Ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification to 4 H Prior to Commencing Backfill Operation ML20212J3041999-06-22022 June 1999 Proposed Tech Specs Re Revised Surveillance Frequency & Action Times Reactor Trip & ESFAS ML20195B5881999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna Unit 2 IST Program Plan for Pumps & Valves Second Insp Interval,901214-001214 ML20195B5691999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna,Unit 1 IST Program Plan for Pumps & Valves Second Insp Interval 901214-001214 ML20206N3691999-05-0606 May 1999 Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic ML20206G8361999-05-0303 May 1999 Proposed Tech Specs,Deleting &/Or Relocating Addl primary- to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20206H0301999-05-0303 May 1999 Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing ML20206G8811999-05-0303 May 1999 Proposed Tech Specs,Increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20205P2511999-05-0101 May 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Program Plan for Third Insp Interval:Components & Component Supports ML20205P2341999-05-0101 May 1999 Rev 0 to Vepc North Anna Unit 1 ISI Program for Third Insp Interval Vol 1:ISI Program for Components & Component Supports for Interval 3 990501-090430 ML20203C8251999-02-0505 February 1999 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Operability ML20205P2651999-02-0404 February 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Plan for Third Interval for Sys Pressure Tests ML20198J0971998-12-22022 December 1998 Proposed Tech Specs Bases Changes Re EDG Steady State Frequency to Be Incorporated Into TS During Implementation of Amends 216 & 197 ML20196K1971998-12-22022 December 1998 Rev 0 to NE-1176, North Anna Unit 1,Cycle 14 Startup Physics Tests Rept, Dec 1998 ML20206N8851998-12-14014 December 1998 Rev 0 to ASME Section XI Sys Pressure Test Program,Second Insp Interval ML20206N8711998-11-30030 November 1998 Rev 11,Vol I to ISI Plan for Second Insp Interval for Components & Component Supports ML20195J4431998-11-18018 November 1998 Proposed Tech Specs Re Revs to Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9461998-11-10010 November 1998 Proposed Tech Specs,Clarifying Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20154P2831998-10-16016 October 1998 Marked-up & Typed Tech Spec Pages to Revise EDG Section to Be Consistent with Station Procedures Associated with Steady State Conditions & W NSAL 93-022,for 980728 Application for Amends to Licenses NPF-4 & NPF-7 ML20153H5341998-09-24024 September 1998 Proposed Tech Specs 3/4.5.1 Re Safety Injection Accumulator Boron Concentration Verification ML20236U8411998-07-28028 July 1998 Proposed Tech Specs 4.6.2.2.1 & 4.6.2.2.2,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20236U8711998-07-28028 July 1998 Proposed Tech Specs,Revising EDG Section to Be Consistent W/ Station Procedures Associated W/Steady State Conditions & W Nuclear Safety Advisory Ltr NSAL 93-022 ML20236U8651998-07-28028 July 1998 Proposed Tech Specs 3/4.1.2 & 3/4.5.5,re RWST & Boron Concentration Ph Range Bases Change to Address Discrepancies Between Previous NRC Issued Ser,Ts Bases & Applicable Sections of SRP ML20236H5311998-07-0101 July 1998 Draft Nuclear Control Room Operator Development Program NAPS Module NCRODP-78 Spent Fuel Dry Storage Cask System. Draft Lesson Plans & Job Performance Measures Included ML20236U8891998-06-25025 June 1998 Rev 0 to NE-1163, North Anna Unit 2 Cycle 13 Startup Physics Tests Rept ML20249C7211998-06-19019 June 1998 Proposed Improved Tech Specs for North Anna ISFSI ML20236H5541998-06-0404 June 1998 Rev 5 to Procedure VPAP-0810, Crane & Hoist Program ML20236H5391998-06-0404 June 1998 Rev 1 to Procedure VPAP-0809, NUREG-0612 Heavy Load Program ML20206N8581998-04-30030 April 1998 Rev 5,Vol 1 to ISI Program for Second Insp Interval & Components & Component Supports,For 901214-010430 ML20236H5701998-04-0202 April 1998 Rev 8 to Procedure VPAP-1901, Industrial Safety & Health ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20217E9011998-03-25025 March 1998 Proposed Tech Specs Re Configuration Risk Mgt Program for risk-informed Allowed Outage Times & Insp Frequency of EDGs ML20236H5631998-02-10010 February 1998 Rev 11 to Procedure VPAP-0105, Fitness for Duty Program ML20202E1551998-02-0909 February 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20202C5871998-02-0303 February 1998 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insps & Loop Flow Straightener Insps ML20202C3381998-02-0303 February 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20210Q2051997-12-31031 December 1997 1997 Severe Accident Management Tabletop (Scenario 1) Drill Manual ML20203G5191997-12-29029 December 1997 Ultrasonic Exam Technique for Detection of Microbilogically Induced Corrosion in North Anna Stainless Steel Service Water Piping ML20199G4161997-11-18018 November 1997 Revised Proposed TS Pages,Establishing 14 Day AOT Applicable Whenever EDG Is Inoperable ML20199H4001997-11-18018 November 1997 Proposed Tech Specs Permitting Quarterly Testing of Turbine Governor & Throttle Valves ML20199A1481997-11-0505 November 1997 Proposed Tech Specs Pages,Providing Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20198G5401997-08-31031 August 1997 Rev 0 to NE-1133, North Anna Unit 1,Cycle 13 Startup Physics Tests Rept, Aug 1997 ML20199G5681997-06-30030 June 1997 Rev 5 to VPAP-2001, Station Planning & Scheduling. Even Numbered Pages of Incoming Submittal Not Included ML20210Q1991997-06-10010 June 1997 Rev 0 to VPAP-2604, Severe Accident Mgt Guideline (SAMG) Program Administration ML20141F3741997-05-14014 May 1997 Proposed Tech Specs Revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided for TS 3/4.7.1.7 ML20137C8581997-03-18018 March 1997 Proposed Tech Specs Re Containment Gaseous & Particulate Radiation Monitors ML20134J4141997-02-0404 February 1997 Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2 ML20134F1231997-02-0303 February 1997 Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2 1999-08-04
[Table view] |
Text
- - 4-11-80 O
ADMINISTRATIVE CONTROLS 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall 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 requested in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 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, ' Aichever 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.
ANNUALREPORTN!
6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
- a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 arem/yr and their associated man rem exposure according to work and job functions,2/ e.g. , reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of tr.e individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions. .
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-'/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
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, This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
NORTH ANNA - UNIT 2 6-15 8007240//I.
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ADMINISTRATIVE CONTROLS
- b. The complete results of the steam generator tube inservice inspections performed during the report period (Reference Specification 4.4.5.5.b.).
- c. SEE ATTACMED PME -
MONTHLY OPERATING REPORT -
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6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Ma.,agement and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office, of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the
- - original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate, no later than the first I working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the i event. !
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- a. Failure of the reactor protection system or other systems subject to ;
limiting safety-system settings to initiate the required protective j function by the ' time a monitored parameter reaches the setpoint !
specified as the limiting safety systa setting in the technical -
specifications or failure to complete the required protective function.
NORTH ANNA - UNIT 2 6-16 l l
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- c. A report documenting challenges to pressurizer safety and relief valves, and summarizing failures of pressurizer safety and relief valves shall be prepared annually and submitted by each April 1.
The report will include all such incidents that have occurred during the previous calendar year. The first report will cover the time period April 1, 1980 through December 31, 1980. Subsequent reports will cover the entire calendar year.
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- b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.
- c. Abnormal degradation discovered in fuel cladding, reactor coofant pressure boundary, or primary containment.
- d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady-state conditions during power
- operation greater than or equal to 1% delta k/k; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5%
delta k/k; or occurrence of any unplanned criticality,
- e. Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR.
- f. Personnel errur = p credural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR.
- g. Conditions arising from natural or man made events that, as a direct result of the event, require plant shutdown, operation of safety evstems, or other protective measures required by technical specifications.
- h. Errers discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor ccaration in a manner less conservative than assumed in the analyses.
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Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than that assumed in the accideat analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
j SEE ATTAC6D PME l NORTH ANNA - UNIT 2 6-17 i
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J. Failures of pressurizer safety and relief valves to close as intended, i
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