Proposed Tech Specs,Modifying Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent W/Bwrog Long Term Solution Option 1.DML20065E885 |
Person / Time |
---|
Site: |
Vermont Yankee |
---|
Issue date: |
03/31/1994 |
---|
From: |
VERMONT YANKEE NUCLEAR POWER CORP. |
---|
To: |
|
---|
Shared Package |
---|
ML20065E877 |
List: |
---|
References |
---|
NUDOCS 9404110137 |
Download: ML20065E885 (15) |
|
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217N3001999-10-21021 October 1999 Proposed Tech Specs,Correcting Two Textual Errors & Changing Designation of Referenced Figure ML20217K8731999-10-18018 October 1999 Proposed Tech Specs Revising Activated Charcoal Testing Methodology IAW Guidance Provided in GL 99-02 ML20212F6941999-09-21021 September 1999 Proposed Tech Specs,Increasing Required Vol of Stored Fuel in Diesel Fuel Oil Storage Tank ML20211J0211999-08-31031 August 1999 Proposed Tech Specs Bases Page 91,allowing Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line (Predicted) Uncorrected Solution & on-line (Measured) 3D-Monicore Exposure Corrected Solution ML20211B7051999-08-18018 August 1999 Proposed Tech Specs Revising Reactor Core Spiral Reloading Pattern to Begin Around SRM ML20211B6781999-08-18018 August 1999 Proposed Tech Specs Revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance ML20210D2481999-07-20020 July 1999 Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems ML20210D3371999-07-20020 July 1999 Proposed Tech Specs Re Enhancements to Support Implementation of Increased Core Flow ML20209G1671999-07-12012 July 1999 Proposed Tech Specs Revising Value for SLMCPR & Deleting Wording Which Specifies These as Cycle 20 Values ML20196K2951999-06-29029 June 1999 Proposed Tech Specs Pages for Proposed Change 220,revising Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 for Main Steam Line Isolation Valves ML20196H2881999-06-24024 June 1999 Proposed Tech Specs Revising & Clarifying Terminology Re Certain RPS Scram Bypass Permissives ML20195J8691999-06-15015 June 1999 Proposed Tech Specs Increasing Stis,Adding Allowable OOS Times,Replacing Generic ECCS Actions for Inoperable Instrument Channels with function-specific Actions & Relocating Selected Trip Functions from TS ML20195F9531999-06-0909 June 1999 Proposed Tech Specs,Supplementing Proposed Change 213, Allowing Use of ASME Code Case N-560,per GL 88-01 ML20195C8841999-05-26026 May 1999 Proposed Tech Specs Clarifying Suppression Chamber Water Temp SR 4.7.A, Primary Containment & Modifying Associated TS Bases ML20206H3771999-05-0606 May 1999 Proposed Tech Specs Pages ,Eleting Specific Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 ML20206J7231999-05-0505 May 1999 Proposed Tech Specs Pages for Proposed Change 212,modifying TS to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to SLC Sys ML20205S9431999-04-20020 April 1999 Proposed Tech Specs,Revising Reactor Core Spiral Reloading Pattern Such That It Begins Around Source Range Monitor ML20205T4721999-04-19019 April 1999 Marked-up Tech Specs Pages Re Suppl to 990201 Request for Amend to License DPR-28,revising Portions of Proposed Change 208 ML20205S4081999-04-16016 April 1999 Proposed Tech Specs Modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 ML20205S3121999-04-15015 April 1999 Proposed Tech Specs Revised Bases Pages 90,227,164 & 221a, Accounting for Change in Reload Analysis,Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20202E5451999-01-25025 January 1999 Proposed Tech Specs Re Technical Requirements Manual Content ML20206S0661999-01-22022 January 1999 Proposed TS to Change Number 189,proposing Relocation of Fire Protection Requirements from TSs to TRM ML20198D5381998-12-15015 December 1998 Proposed Tech Specs Page 142,correcting Wording to Reflect Previously Approved Wording,Last Revised in Amend 160 ML20198B7421998-12-11011 December 1998 Proposed Tech Specs Changing Wording of Primary Containment Integrity Definition to State That Manual PCIVs Which Are Required to Be Closed During Accident Conditions May Be Opened Intermittently Under ACs ML20197J4631998-12-10010 December 1998 Proposed Tech Specs Section 4.9.2,revising Info Re Calibr of Augmented Offgas Sys Hydrogen Monitors ML20197H0031998-12-0707 December 1998 Proposed Tech Specs Change 209,resolving Emergency Concern Re Potential Operation Outside of LCO Contained in Current TS & Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation ML20155F7421998-11-0303 November 1998 Proposed Tech Specs Incorporating Minor Corrections or Clarifications Which Enhance Clarity of TSs Without Materially Changing Meaning or Application ML20155G5061998-11-0202 November 1998 Proposed Tech Specs Re ECCS Actuation Instrumentation - LPCI A/B RHR Pump Start Time Delay Requirements & CS Sys A/B Pump Start Delay Requirements ML20151U0131998-09-0404 September 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity of Util Spent Fuel Pool from 2,870 to 3,355 Fuel Assemblies ML20236H4551998-06-30030 June 1998 Proposed Tech Specs Modifying Table 4.2.1 to Delete ECC Actuation Instrumentation Re Core Spray Sys & LPCI Sys Auxiliary Power Monitor Calibr Requirement ML20247E5671998-05-0808 May 1998 Proposed Tech Specs Page 270,containing Wording Inadvertently Deleted from TS Proposed Change 202 ML20247J8121998-05-0808 May 1998 Proposed Tech Specs Reducing Normal Operating Suppression Pool Water Temp Limit & Adding Time Restriction for Higher Temp Allowed During Surveillances That Add Heat to Suppression Pool ML20217P4171998-05-0101 May 1998 Proposed Tech Specs Re Administrative Controls Section ML20217G7131998-04-23023 April 1998 Proposed Tech Specs Change 200 Revising Station SW & Alternate Cooling Sys Requirements ML20217C4591998-03-20020 March 1998 Proposed Tech Specs Re Containment Purge & Vent ML20217A1271998-03-13013 March 1998 Proposed Tech Specs Bases Section 3.10.B,updated to Require That Station Battery,Eccs Instrumentation Battery,Or Uninterruptable Power Sys Battery Be Considered Inoperable If Any One Cell Is Below Specification Cell Voltage ML20202H2611998-02-0606 February 1998 Revised TS Pages Re Change 190,w/typos Corrected ML20197E8481997-12-22022 December 1997 Replacement Pages 160 & 279 & mark-up Pages to Proposed TS Change 190 Containing Editorial Changes ML20203F0131997-12-11011 December 1997 Proposed Tech Specs Revising Current Value for SLMCPR for Cycle 20,next Operating Cycle ML20199K8501997-11-21021 November 1997 Replacement Pages 147,156,157 & mark-up Pages to Proposed TS Change 190,removing Ref to Documents Outside of TS That Define Components to Which Program Applies ML20199J7661997-11-20020 November 1997 Proposed Tech Specs Pages,Revising Requirements for Main Station Batteries ML20217H6931997-10-10010 October 1997 Proposed Tech Specs Revising & Clarifying Requirements for Offsite Power Sources ML20211A6461997-09-18018 September 1997 Proposed Tech Specs,Providing marked-up Pages for Proposed Changes 192 & 193 ML20217Q3311997-08-22022 August 1997 Proposed Tech Specs Pages 245 & 252,amending App a to Modify TS to More Clearly Describe Separation of Switchgear Room Into Two Fire Areas & Incorporate Specifications for New Low Pressure CO2 Suppression Sys ML20217N4111997-08-20020 August 1997 Proposed Tech Specs Pages 270 & 270a,updating Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle-specific Thermal Operating Limits to COLR ML20141H1171997-07-11011 July 1997 Proposed Tech Specs,Replacing Pages 147,156 Through 161,168 & 279 of Util TS W/Corrected Pages ML20148J1861997-06-0909 June 1997 Proposed Tech Specs Change 191,updating Section 6.0 Administrative Controls ML20132B5771996-12-10010 December 1996 Proposed Tech Specs 3.13 Re Fire Protection Sys ML20129C4521996-10-17017 October 1996 Proposed Tech Specs,Revising Pages 89,89a & 90 to Incorporate Changes from Amends 148 & 149 ML20128N6031996-10-11011 October 1996 Proposed Tech Specs,Revising Existing Requirements Re Amount of Foam Concentrate Required to Support Operability of Recirculation Motor Generator Set Foam Sys in TS 3.13.G.1 & 3.13.G.2 1999-09-21
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3001999-10-21021 October 1999 Proposed Tech Specs,Correcting Two Textual Errors & Changing Designation of Referenced Figure ML20217K8731999-10-18018 October 1999 Proposed Tech Specs Revising Activated Charcoal Testing Methodology IAW Guidance Provided in GL 99-02 ML20212F6941999-09-21021 September 1999 Proposed Tech Specs,Increasing Required Vol of Stored Fuel in Diesel Fuel Oil Storage Tank ML20211J0211999-08-31031 August 1999 Proposed Tech Specs Bases Page 91,allowing Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line (Predicted) Uncorrected Solution & on-line (Measured) 3D-Monicore Exposure Corrected Solution ML20211B6781999-08-18018 August 1999 Proposed Tech Specs Revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance ML20211B7051999-08-18018 August 1999 Proposed Tech Specs Revising Reactor Core Spiral Reloading Pattern to Begin Around SRM ML20210D2481999-07-20020 July 1999 Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems ML20210D3371999-07-20020 July 1999 Proposed Tech Specs Re Enhancements to Support Implementation of Increased Core Flow ML20209G1671999-07-12012 July 1999 Proposed Tech Specs Revising Value for SLMCPR & Deleting Wording Which Specifies These as Cycle 20 Values ML20196K2951999-06-29029 June 1999 Proposed Tech Specs Pages for Proposed Change 220,revising Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 for Main Steam Line Isolation Valves ML20196H2881999-06-24024 June 1999 Proposed Tech Specs Revising & Clarifying Terminology Re Certain RPS Scram Bypass Permissives ML20195J8691999-06-15015 June 1999 Proposed Tech Specs Increasing Stis,Adding Allowable OOS Times,Replacing Generic ECCS Actions for Inoperable Instrument Channels with function-specific Actions & Relocating Selected Trip Functions from TS ML20195F9531999-06-0909 June 1999 Proposed Tech Specs,Supplementing Proposed Change 213, Allowing Use of ASME Code Case N-560,per GL 88-01 ML20195C8841999-05-26026 May 1999 Proposed Tech Specs Clarifying Suppression Chamber Water Temp SR 4.7.A, Primary Containment & Modifying Associated TS Bases ML20206H3771999-05-0606 May 1999 Proposed Tech Specs Pages ,Eleting Specific Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 ML20206J7231999-05-0505 May 1999 Proposed Tech Specs Pages for Proposed Change 212,modifying TS to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to SLC Sys ML20205S9431999-04-20020 April 1999 Proposed Tech Specs,Revising Reactor Core Spiral Reloading Pattern Such That It Begins Around Source Range Monitor ML20205T4721999-04-19019 April 1999 Marked-up Tech Specs Pages Re Suppl to 990201 Request for Amend to License DPR-28,revising Portions of Proposed Change 208 ML20205S4081999-04-16016 April 1999 Proposed Tech Specs Modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 ML20205S3121999-04-15015 April 1999 Proposed Tech Specs Revised Bases Pages 90,227,164 & 221a, Accounting for Change in Reload Analysis,Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20202E5451999-01-25025 January 1999 Proposed Tech Specs Re Technical Requirements Manual Content ML20206S0661999-01-22022 January 1999 Proposed TS to Change Number 189,proposing Relocation of Fire Protection Requirements from TSs to TRM ML20198D5381998-12-15015 December 1998 Proposed Tech Specs Page 142,correcting Wording to Reflect Previously Approved Wording,Last Revised in Amend 160 ML20198B7421998-12-11011 December 1998 Proposed Tech Specs Changing Wording of Primary Containment Integrity Definition to State That Manual PCIVs Which Are Required to Be Closed During Accident Conditions May Be Opened Intermittently Under ACs ML20197J4631998-12-10010 December 1998 Proposed Tech Specs Section 4.9.2,revising Info Re Calibr of Augmented Offgas Sys Hydrogen Monitors ML20197H0031998-12-0707 December 1998 Proposed Tech Specs Change 209,resolving Emergency Concern Re Potential Operation Outside of LCO Contained in Current TS & Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation ML20155F7421998-11-0303 November 1998 Proposed Tech Specs Incorporating Minor Corrections or Clarifications Which Enhance Clarity of TSs Without Materially Changing Meaning or Application ML20155G5061998-11-0202 November 1998 Proposed Tech Specs Re ECCS Actuation Instrumentation - LPCI A/B RHR Pump Start Time Delay Requirements & CS Sys A/B Pump Start Delay Requirements ML20196A7851998-10-0909 October 1998 Rev 19 to Vynp IST Program Plan ML20151U0131998-09-0404 September 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity of Util Spent Fuel Pool from 2,870 to 3,355 Fuel Assemblies ML20237E9571998-08-27027 August 1998 Start-Up Test Rept Vynp Cycle 20 ML20236H4551998-06-30030 June 1998 Proposed Tech Specs Modifying Table 4.2.1 to Delete ECC Actuation Instrumentation Re Core Spray Sys & LPCI Sys Auxiliary Power Monitor Calibr Requirement ML20247J8121998-05-0808 May 1998 Proposed Tech Specs Reducing Normal Operating Suppression Pool Water Temp Limit & Adding Time Restriction for Higher Temp Allowed During Surveillances That Add Heat to Suppression Pool ML20247E5671998-05-0808 May 1998 Proposed Tech Specs Page 270,containing Wording Inadvertently Deleted from TS Proposed Change 202 ML20217P4171998-05-0101 May 1998 Proposed Tech Specs Re Administrative Controls Section ML20217G7131998-04-23023 April 1998 Proposed Tech Specs Change 200 Revising Station SW & Alternate Cooling Sys Requirements ML20217C4591998-03-20020 March 1998 Proposed Tech Specs Re Containment Purge & Vent ML20217A1271998-03-13013 March 1998 Proposed Tech Specs Bases Section 3.10.B,updated to Require That Station Battery,Eccs Instrumentation Battery,Or Uninterruptable Power Sys Battery Be Considered Inoperable If Any One Cell Is Below Specification Cell Voltage ML20202H2611998-02-0606 February 1998 Revised TS Pages Re Change 190,w/typos Corrected ML20197E8481997-12-22022 December 1997 Replacement Pages 160 & 279 & mark-up Pages to Proposed TS Change 190 Containing Editorial Changes ML20203F0131997-12-11011 December 1997 Proposed Tech Specs Revising Current Value for SLMCPR for Cycle 20,next Operating Cycle ML20199K8501997-11-21021 November 1997 Replacement Pages 147,156,157 & mark-up Pages to Proposed TS Change 190,removing Ref to Documents Outside of TS That Define Components to Which Program Applies ML20199J7661997-11-20020 November 1997 Proposed Tech Specs Pages,Revising Requirements for Main Station Batteries ML20217H6931997-10-10010 October 1997 Proposed Tech Specs Revising & Clarifying Requirements for Offsite Power Sources ML20211A6461997-09-18018 September 1997 Proposed Tech Specs,Providing marked-up Pages for Proposed Changes 192 & 193 ML20217Q3311997-08-22022 August 1997 Proposed Tech Specs Pages 245 & 252,amending App a to Modify TS to More Clearly Describe Separation of Switchgear Room Into Two Fire Areas & Incorporate Specifications for New Low Pressure CO2 Suppression Sys ML20217N4111997-08-20020 August 1997 Proposed Tech Specs Pages 270 & 270a,updating Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle-specific Thermal Operating Limits to COLR ML20141H1171997-07-11011 July 1997 Proposed Tech Specs,Replacing Pages 147,156 Through 161,168 & 279 of Util TS W/Corrected Pages ML20148J1861997-06-0909 June 1997 Proposed Tech Specs Change 191,updating Section 6.0 Administrative Controls ML20149M7451997-01-24024 January 1997 Startup Test Rept,Vermont Yankee Cycle 19 1999-09-21
[Table view] |
Text
. - . . . . . _ .. . . --. - ..
F l
! Appendix 1 Proposed Technical Specification Changes
! Affected Pages 14 110 110-a 110-b 110 c l 110 d l 110-j 111-c 124-a
! 124 b l 125 125-a (New Page) 209 209-d l
l I
l l
l i
l l
i l
l l
1
-1 C43\1 940411o137 DR 940331 p ADOCK 05000271' PDR, ..
VYNPS .
BASES:
2.1 FUEL CLADDING INTEGRITY A. Trio Settings The bases for individual trip settings are discussed in the following paragraphs.
- 1. Neutron Flux Trio Settings
- a. APRM Flux Scram Trio Setting (Run Mode)
The average power range monitoring (APRM) system, which is calibrated using heat balance data taken during steady state conditions, reads in percent of rated thermal power . (1593 MWt). Because fission chambers provide the basic' input signals, the APRM system responds directly to average neutron flux. During transients, the instantaneous _ rate of heat transfer from the fuel (reactor thermal power) is less than the instantaneous neutron flux due to the time constant of the fuel.
Therefore, during abnormal operational transients, the thermal power of the fuel will be less than that indicated by the neutron flux at the scram setting. Analyses are performed to demonstrate that the APRM Flux Scram over the range of settings. from a maximum of 120% to the minimum flow biased setpoint of 54% provide protection from the fuel safety limit for all abnormal operational transients including those that may result in a thermal hydraulic instability.
An increase in the APRM scram trip - setting would decrease the margin present before -the fuel cladding integrity Safety Limit is reached. The APRM scram trip setting was determined by. an
-analysis of margins required to provide a reasonable range for maneuvering. during operation.
' Reducing this operating margin would increase the frequency of spurious scrams which have an adverse effect on reactor safety because of the resulting thermal stresses. Thus, the APRM scram trip setting was selected because .it provides adequate margin for the fuel cladding integrity Safety Limit yet allows operating margin-that reduces the possibility of unnecessary scrams.
14 Amendment No. 47
VYNPS -
3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT .
G. Single loop Operation
- 1. The reactor may be started and operated or '
operation may continue with a single '
recirculation loop provided that:
- a. The designated adjustments for APRM flux scram and rod block trip settings (Specifications 2.1.A.1.a and 2.1.B.1 Table 3.1.1 and Table 3.2.5), rod block monitor trip setting (Table 3.2.5). MCPR fuel cladding integrity safety limit (Specification 1.1.A), and MCPR operating limits and MAPLHGR limits.
provided in the Core Operating Limits Report, are initiated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
. During the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, either -these adjustments must be completed or the reactor brought to Hot Shutdown.
- b. The requirements for avoiding potentially unstable thermal hydraulic conditions defined in Technical Specification 3.6.J are met.
Amendment No. 09, 94, 116 .
110
_ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -______ _ _ . . __ __. v e -- a -- e __ ___ _ _ _ . _ _ _ _ __ _ _ _ _ _ _ _ . ____ . - _ _ _
VYNPS 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT ..
This page has been deleted.
110-a Amendment No. 94
VYNPS 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT ..
- c. The idle loop is isolated by electrically disarming the breaker to the recirculation pump motor generator set drive motor prior to startup or, if disabled during reactor operation, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and until such time as the inactive recirculation loop is to be returned to service.
- d. The recirculation system controls will be placed in the manual flow control mode.
110-b-Amendment No. 94
_ _ _ _ _ _ . _ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ . - _m_ _ _ _ ._
VVNPS 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT -
This page has been deleted.
Amendment No. E9, 9E, 94 110-c
UYNPS 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT H. Recirculation System
- 1. Operation with one recirculation loop is permitted according to Specification 3.6.G.I.
- 2. With no reactor coolant system recirculation loops in operation, initiate measures such that the unit is in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
110-d Amendment No. 94
VYNPS l
3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE RE0VIREMENT
- l. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
- 2. Snubber bleed ' or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
J. Thermal Hydraulic Stability J. Thermal Hydraulic Stability
- 1. When the reactor mode switch is in RUN:
- a. Under normal operating conditions the reactor shall not intentionally be operated within the power flow exclusion region defined in Core Operating Limits Report (COLR):
- b. If the reactor has entered the power flow exclusion region (COLR), tt :
operator shall immediately insert control rods and/or increase recirculation flow to establish operation outside of the region.
Amendment No. 24, 39, 64, 69, 90. 94 -110-j
VYNPS This page has been deleted.
lll-C Amendment No. 94
VVNPS BASES: 3.6 and 4.6 (Cent'd)
G. Single Loop Operation Continuous operation with one recirculation loop was justified in " Vermont Yankee Nuclear Power Station Single Loop Operation". NE00-30060. February 1983, with the adjustments specified in Technical Specification 3.6.G.I.a.
During single loop operation. . the idle recirculation loop is isolated by electrically disarming the recirculation pump motor generator set drive motor, until ready to resume two loop operation. This is done to prevent a cold water injection transient caused by an inadvertent pump startup.
Under single loop operation, the flow control is placed in the manual mode to avoid control oscillations which may occur in the recirculation flow control system under these conditions.
124-a Amendment No. 9&
VYNPS BASES: 3.6 and 4.6 (Cont *d)
H. Recirculation System Twelve hours is a reasonable period of time to reach hot shutdown conditions.
Operation of the reactor may not occur without forced recirculation flow.
I t
5 I
i 124-b Amendment No. 94
i VYNPS I .
! BASES: 3.6 and 4.6 (Cont *d)
I
- 1. Shock Suppressors (Snubbers)
All snubbers are required operable to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections preformed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are (1) of a specific make or model. (2) of the same design, and (3) similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration. These characteristics of the snubber installation shall be evaluated to determine if further functional testing of similar snubber installations is warranted.
When a snubber is -found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure. . in order to determine if any safety-related component-or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested once each operating cycle. Observed failures of these sample snubbers shall require functional testing of additional units.
Amendment No. 24, 39. 09, 94 :125
VYNPS BASES: 3.6 and 4.6 (Cont *d)
J. Thermal Hvdraulic Stability The reactor is designed such that thermal hydraulic oscillations are prevented or can be readily detected and suppressed without exceeding specified fuel design limits. To minimize the likelihood of an instability, a power / flow exclusion region to be avoided during normal operation is calculated using the-approved methodology as stated in 6.7.A.4 Since the exclusion region may change each fuel cycle the limits are contained in the Core Operating Limits Report. Specific directions are provided to avoid operation in this region and, to immediately exit upon an entry. Entries into the exclusion region are not part of normal operation. An entry may occur as the result of an abnormal event such as a single pump trip. In these events, operation in the exclusion region may be needed to prevent equipment damage, but actual time spent inside the exclusion. region is minimized. Though each operator action can prevent the occurrence and protect the reactor f rom an instability, the APRM flow biased scram function will suppress oscillations prior to exceeding the fuel safety limit.
P 1
Amendment No. 125-a 4
- - _ _ _ _ _ . - _ . - _ - _ _ < w ? ..e - - ---_-.a -n _ _ - _--~~
VYNPS
- 2. Annual Report An annual report covering the previous calendar year shall be submitted prior to March 1 of each year. The annual report shall include a tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and job functions, 1/ e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter TLD or film badge measurement. Small exposures totaling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
- 3. Monthly Statistical Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Management Information and Program Control. U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the appropriate Regional Office, to arrive no later than the fifteenth of each month following the calendar month covered by the report. These reports shall include a narrative summary of operating experience during the report period which describes the operation of the facility.
- 4. Core Operatino limits Report The core operating limits shall be established and documented in the Core Operating Limits Report (COLR) before each reload cycle or any remaining part of a reload cycle for the following: (a) The Average Planar Linear leat Generation Rates (APLHGR) for Specifications 3.11.A and 3.6.G.la, (b) The Kf core flow adjustment factor for Specification 3.11.C., (c) The Minimum Critical Power Ratio (MCPR) for Specifications 3.11.C and 3.6.G.la, (d)
The Linear deat Generation Rates (LHGR) for Specifications 2.1. A.la, 2.1.B.1, and 3.11.B. and (e) The Power / Flow Exclusion Region for Specifications 3.6.J.la and 3.6.J.lb. The analytical methods used to determine the core j operating limits shall be those previously reviewed and approved by the NRC in:
Report E. E. Pilat. " Methods for the Analysis of Boiling Water Reactors Lattice Physics," YAEC-1232. December 1980 (Approved by NRC SER, dated September 15. 1982).
Report. D. M. VerPlanck, ' Methods for the Analysis of Boiling Water Reactors Steady State Core Physics,"
YAEC-1238, March 1981 (Approved by NRC, SER, dated September 15, 1982).
1/ This tabulation supplements the requirements of 20.407 of 10CFR Part.20.
Amendment No. +e, 63, 95, 116 209
' VVNPS l
l Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, "LOCA-Related. Responses to Open Issues on FROSSTEY-2 Fuet
- Performance Code," BVY 32-39, dated March 27, 1992 (Approved by NRC SER, dated September 24. 1992).
Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, "FROSSTEY-2 Fuel Performance Code - Vermont Yankee Response to Remaining Concerns " BVY 92-54, dated May 15, 1992 (Approved by NRC SER, dated September 24, 1992).
Report, " Loss-of-Coo' ant Accident Aralysis for Vermont Yankee Nuclear Power Station," NED0-21697 August 1977, as amended (Approved by NRC SER, dated November 30, 1977).
Report, " General Electric Standard Application for Reactor Fuel (GESTARII)," NEDE-24011-P-A, GE Company Proprietary (the latest NRC-approved version will be listed in the COLR).
Report, General Electric Nuclear Energy, "BWR Owner's Group Long-Term Solutions Licensing Methodology."
NE00-31960. June 1991 (Approved by NRC SER, dated July 12, 1993).
Report, General Electric Nuclear Energy, "BWR Owner's Group Long-Term Solutions Licensing Methodology "
NED0-31960. Supplement 1 March 1992. (Approved by NRC'SER, dated July 12. 1993).
The ' core operating limits shall be determined so that .all applicable limits (e.g., fuel thermal-mechanical limits, core thermal- hydraulic limits ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The COLR, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
B. Reportable Occurrences This section deleted.
Amendment No. 135 209d i
__________._________.___.m___ _ _ _ _ _ _ _ _ _ _ _