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MONTHYEARML0400203012003-12-23023 December 2003 Technical Specifications, Logic System Functional Test Project stage: Acceptance Review ML0307300482003-12-23023 December 2003 License Amendment, Issuance of Amendment, No. 216 Logic System Functional Test Dated 12/23/03 Project stage: Approval ML0524200792005-09-0707 September 2005 SONGS 2 & 3, Cancellation of TAC Nos. for Physical Security Plan Change Submitted 5/27/05 TAC MB7214, MB7215 Project stage: Other 2003-12-23
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Category:Technical Specifications
MONTHYEARML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML18347B3592019-01-11011 January 2019 12-13-18-License Transfer Conforming Amendment Markup ML18253A2022018-10-11011 October 2018 Conforming License Amendment Approval of License Transfer Request(License DPR-28, Docket 50-271 and 72-59) ML18156A1812018-08-15015 August 2018 ISFSI Only Tech Spec Amendment Package ML16014A1692016-03-14014 March 2016 Vermont Yankee Nuclear Power Station - Issuance of Amendment No. 265 to Renewed Facility Operating License Re: Cyber Security Plan Implementation Schedule (CAC No. MF6403) ML15117A5512015-10-0707 October 2015 Issuance of Amendment for Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML14304A5882015-02-12012 February 2015 Issuance of Amendment No. 261, Revise Technical Specifications to Eliminate Certain Requirements During Movement of Irradiated Fuel and Core Alterations Consistent with TSTF-51 ML14346A0652015-02-0404 February 2015 Issuance of Amendment No. 261, Revise Site Emergency Plan for Permanently Defueled Condition to Reflect Change in On-Shift Staffing and Emergency Response Staffing ML14217A0722014-12-22022 December 2014 Issuance of Amendment No. 260, Revise and Remove Certain Requirements from Technical Specification Section 6.0, Administrative Controls, No Longer Applicable for Its Permanently Defueled Condition BVY 14-083, Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 32014-12-0505 December 2014 Technical Specifications Proposed Change No. 307, Revision to Technical Specification Administrative Controls for Permanently Defueled Condition - Supplement 3 ML13212A2012013-08-15015 August 2013 Issuance of Amendment No. 258 Change to Licensing Basis Regarding Station Blackout BVY 12-085, Technical Specifications Proposed Change No. 302 Inoperable Control Rods2012-12-17017 December 2012 Technical Specifications Proposed Change No. 302 Inoperable Control Rods CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications BVY 12-005, Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change2012-02-0101 February 2012 Technical Specifications Proposed Change No. 297, Suppression Chamber-Drywell Leak Rate Test Surveillance Frequency Change BVY 11-069, Technical Specifications Proposed Change No. 295 Proposed Emergency License Amendment for Single Loop Operation2011-09-29029 September 2011 Technical Specifications Proposed Change No. 295 Proposed Emergency License Amendment for Single Loop Operation BVY 10-045, Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure2010-08-19019 August 2010 Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure BVY 09-068, Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves2009-12-0303 December 2009 Technical Specifications Proposed Change No. 288 Scram Discharge Volume Vent and Drain Valves ML0917400402009-07-13013 July 2009 License Amendment, Relocation of Reactor Building Crane Technical Specification BVY 09-035, Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages2009-05-20020 May 2009 Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages ML0901206582009-02-11011 February 2009 Issuance of Amendment Battery Systems BVY 08-084, Technical Specifications Proposed Change No. 273, Supplement 5, Response to Request for Additional Information2008-12-18018 December 2008 Technical Specifications Proposed Change No. 273, Supplement 5, Response to Request for Additional Information BVY 08-075, Technical Specifications Proposed Change No. 273, Supplement 4, Response to Request for Additional Information Related to Supplement 22008-12-15015 December 2008 Technical Specifications Proposed Change No. 273, Supplement 4, Response to Request for Additional Information Related to Supplement 2 BVY 08-052, Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements2008-09-22022 September 2008 Technical Specifications Proposed Change No. 278, Changes to Main Steam Isolation Valve Surveillance Requirements BVY 08-062, Technical Specifications Proposed Change No. 273, Supplement 2, Response to Request for Additional Information2008-09-15015 September 2008 Technical Specifications Proposed Change No. 273, Supplement 2, Response to Request for Additional Information BVY 08-053, Technical Specifications Proposed Change No. 279 Sale or Lease of Property within the Exclusion Boundary2008-09-0404 September 2008 Technical Specifications Proposed Change No. 279 Sale or Lease of Property within the Exclusion Boundary BVY 08-047, Technical Specification Proposed Change No. 276, Response to Request for Additional Information2008-07-29029 July 2008 Technical Specification Proposed Change No. 276, Response to Request for Additional Information ML0817601182008-06-23023 June 2008 Technical Specifications, Amendments to Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits ML0811201212008-04-17017 April 2008 Technical Specifications, Amendment No. 231 ML0806602032008-02-12012 February 2008 Vermont Yankee, Technical Specifications Proposed Change No. 273, Instrumentation Technical Specifications BVY 08-007, Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System2008-02-0606 February 2008 Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System BVY 07-056, Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements2007-10-18018 October 2007 Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements BVY 07-063, Technical Specifications Proposed Change No. 275 Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits2007-10-18018 October 2007 Technical Specifications Proposed Change No. 275 Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits ML0708607332007-03-26026 March 2007 Technical Specifications, Modify Requirements for Inoperable Snubbers by Relocating the Current TS Requirements Limiting Condition for Operation (LCO) 3.6.1 and Surveillance Requirement (SR) 4.6.1 ML0629103402006-08-28028 August 2006 Correction to Technical Specification Page 255 Amendment No. 226 BVY 06-067, Correction to Technical Specification Page2006-07-27027 July 2006 Correction to Technical Specification Page ML0603901072006-03-0202 March 2006 Vermont Yankee, Tech Spec Pages for Amendment 229 Regarding Extended Power Uprate BVY 06-018, Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 45, Extended Power Uprate - Revised Technical Specification Pages2006-02-22022 February 2006 Vermont Yankee, Technical Specification Proposed Change No. 263 - Supplement No. 45, Extended Power Uprate - Revised Technical Specification Pages ML0604101192006-02-0303 February 2006 2006/02/03-Vermont Yankee - Technical Specification Proposed Change No. 263 Extended Power Uprate - Regulatory Commitment Information Regarding Potential Adverse Flow Effects BVY 05-105, Vermont Yankee Nuclear Power Station Correction to Technical Specifications Pages2005-12-12012 December 2005 Vermont Yankee Nuclear Power Station Correction to Technical Specifications Pages ML0526400902005-09-20020 September 2005 Technical Specifications, Drywell Spray Header and Nozzle Air Test Frequency BVY 05-083, Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 32 Extended Power Uprate - Additional Information2005-09-10010 September 2005 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 32 Extended Power Uprate - Additional Information ML0522800592005-08-15015 August 2005 Tech Spec Pages for Amendment 226 Administrative Changes ML0519202762005-07-0707 July 2005 Tech Spec Pages for Amendment 225 Regarding Extend Intermediate Range Monitor Surveillance Test Frequencies ML0519202462005-06-30030 June 2005 Attachment 1 - Response to Request for Additional Information - Instrumentation Technical Specifications, Vermont Nuclear Power Station, Technical Specifications BVY 05-032, Vermont Nuclear Power Station - Response to Request for Additional Information Regarding Intermediate Range Monitor Surveillance Test Frequencies2005-03-31031 March 2005 Vermont Nuclear Power Station - Response to Request for Additional Information Regarding Intermediate Range Monitor Surveillance Test Frequencies ML0509003992005-03-29029 March 2005 Technical Specification Pages Re Alternative Source Term ML0508004322005-03-16016 March 2005 TS Pages for Amendment 221 to License DPR-28, Relocating Current Definition of Surveillance Frequency to New Technical Specification (TS) Sections 4.0.2 and 4.0.3 and Revises Requirements for Missed Surveillance in TS Section 4.0.3 ML0435102452004-12-14014 December 2004 Technical Specification Pages, Elimination of Requirements for Hydrogen/Oxygen Monitors ML0514500312004-06-0909 June 2004 E-Mail from R. Ennis of USNRC to Various, Regarding State of Vermont Comments on EPU and AST ML0411202522004-04-14014 April 2004 Technical Specification Pages for Vermont Yankee Nuclear Power Station, License Amendment, Issuance of Amendment Implementation of Arts/Mellla 2019-09-11
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VYNPS 1.0 DEFINITIONS 1.0 DEFINITIONS The succeeding frequently used terms are explicitly defined so that a uniform interpretation of the specifications may be achieved.
A. Reportable Occurrence - The equivalent of a reportable event which shall be any of the conditions specified in Section 50.73 to 10CFR Part 50.
B. Alteration of the Reactor Core - The act of moving any component affecting reactivity within the reactor vessel in the region above the core support plate, below the upper grid and within the shroud. Normal movement of control rods or neutron detectors, or the replacement of neutron detectors is not defined as a core alteration.
C. Hot Standby - Hot standby means operation with the reactor critical and the main steam line isolation valves closed.
D. Immediate - Immediate means that the required action will be initiated as soon as practicable considering the safe operation of the unit and the importance of the required action.
E. Instrument Calibration - An instrument calibration means the adjustment of an instrument signal output so that it corresponds, within acceptable range and accuracy, to a known value(s) of the parameter which the instrument monitors. Calibration shall encompass the entire instrument including actuation, alarm, or trip. Response time as specified is not part of the routine instrument calibration but will be checked once per operating cycle.
F. Instrument Check - An instrument check is qualitative determination of acceptable operability by observation of instrument behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.
G. Instrument Functional Test - An instrument functional test shall be:
- 1. Analog channels - the injection of a signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.
- 2. Bistable channels - the injection of a signal into the sensor to verify the operability including alarm and/or trip functions.
H. Logic System Functional Test - A logic system functional test shall be a test of all logic components required for operability of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify operability. The logic system functional test may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
Amendment No. 4y, -3, 9-, 1i6, , 6-8 216 1
VYNPS 1.0 DEFINITIONS V. Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed. When the mode switch is placed in the shutdown position a reactor scram is initiated, power to the control rod drives is removed, and the reactor protection system trip systems are de-energized.
- 1. Hot Shutdown means conditions as above with reactor coolant temperature greater that 212 0 F.
- 2. Cold Shutdown means conditions as above with reactor coolant temperature equal to or less than 212 0F.
- 3. Shutdown means conditions as above such that the effective multiplication factor (Kff) of the core shall be less than 0.99.
W. Deleted X. Transition Boiling - Transition boiling means the boiling regime between nucleate and film boiling. Transition boiling is the regime in which both nucleate and film boiling occur intermittently with neither type being completely stable.
Y. Surveillance Frequency - Unless otherwise stated in these specifications, periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance intervals. These intervals may be adjusted plus 25%. The operating cycle interval is considered to be 18 months and the tolerance stated above is applicable.
If it is discovered that a surveillance was not performed within its specified frequency, declaring applicable Limiting Conditions for Operation (LCOs) not met may be delayed, from the time of discovery, up to 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> or up to the limit of the specified frequency, whichever is less. This delay period is permitted to allow performance of the surveillance.
If the surveillance is not performed within the delay period, applicable LCOs must immediately be declared not met, and applicable LCOs must be entered.
When the surveillance is performed within the delay period and the surveillance is not met (i.e., acceptance criteria are not satisfied),
applicable LCOs must immediately be declared not met, and applicable LCOs must be entered.
Amendment No. 4, i-24, 49, 197, 216 4
VYNPS BASES:
4.2 PROTECTIVE INSTRUMENTATION (Cont'd)
Since logic circuit tests may result in the actuation of plant equipment, testing of this nature is generally performed during a refueling outage.
In this way, the testing of equipment should not jeopardize plant operation.
These surveillance requirements provide a periodic testing program for protective instrumentation to demonstrate that systems and components function satisfactorily and include schedules for performing functional tests, calibrations, and logic system functional tests. The testing of a subsystem includes a functional test of each relay wherever practicable.
The testing of each relay includes all circuitry necessary to make the relay operate, and also the proper functioning of the relay contacts.
Testing of the automatic initiation inhibit switches verifies the proper operability of the switches and relay contacts. Functional testing of the inaccessible temperature switches associated with the isolation systems is accomplished remotely by application of a heat source to individual switches.
All subsystems are functionally tested, calibrated, and operated in their entirety.
A channel functional test is performed for the Reactor Mode Switch -
Shutdown Position function to ensure that the entire channel will perform the intended function. The surveillance is only required to be performed once per operating cycle during refueling. The Refueling Outage frequeency is based on the need to perform this surveillance under the conditions that apply during a plant outage. Operating experience has shown that this surveillance frequency is adequate to ensure functional operability.
Note 12 of Table 4.2.5 specifies that if the surveillance frequency of every Refueling Outage is not met, functional testing of the Reactor Mode Switch - Shutdown Position function shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the reactor mode switch is placed in the Shutdown position for the purpose of commencing a scheduled Refueling Outage. This allows entry into the Shutdown mode when the surveillance requirement is not met.
Amendment No. 44, 4-, , !0', -8, 241, 216 80a
VYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT OPERATION due to malfunction of the electrical portion of the valve when the reactor is pressurized above 150 psig with irradiated fuel in the reactor vessel, continued reactor operation is permissible only during the succeeding seven days unless such a valve is sooner made operable, provided that during such seven days both the remaining Automatic Relief System valves and the HPCI System are operable.
- 3. If the requirements of Specification 3.5.F cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to < 150 psig within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
G. Reactor Core Isolation G. Reactor Core Isolation Cooling System (RCIC) Coolinq System (RCIC)
- 1. Except as specified in Surveillance of the RCIC Specification 3.5.G.2 System shall be performed as below, the RCIC System follows:
shall be operable whenever the reactor 1. Testing steam pressure is greater than 150 psig and a. A simulated automatic irradiated fuel is in the actuation test of the reactor vessel. RCIC System shall be I performed during each
- 2. From and after the date refueling outage.
that the RCIC System is made or found to be b. Operability testing of inoperable for any the pump and valves reason, reactor operation shall be in accordance is permissible only with Specification during the succeeding 4.6.E.
14 days unless such system is sooner made c. Upon reactor startup, operable, provided that: RCIC operability testing shall be
- a. The HPCI System is performed as required immediately verified by Specification 4.6.E by administrative within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> after means to be operable, exceeding 150 psig and reactor steam pressure.
Amendment No. i&, -7,14-4, 28, 64, 177,
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