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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
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vnto . ,
EO' M VYNPS Du o us 00 I
1.1 SAFETY LIMIT h!O 2.1. LIMITING SAFETY SYSTEM SETTING'
, 9 4
O UHD OtJ cuo For the purpose of performing special
.uOU stability testing' when the mode switch is QNM
, in the RUN position, the APRM flux scram trip setting shall be:
S$ 0.66W + 85%
a For no combination of loop recirculation flow rete.and core thermal power shall the APRM flux scram. trip setting be
. allowed to exceed 120% of rated thermal i power.
During operation under the provisions of :
2.1.A.I.b, the special MAPLHGR limits of-3.11.A shall apply and such operation shall be limited . to the duration of . pump 4
trip and stability. tests. Adjustmente
- for the ratio of MFLPD to FRP greater than 1.0 are not required while conducting special testing under this provision.
- c. Flux Scram ' Trip Setting - (Refuel or Startup and Hot Standby Mode)
When the reactor mode switch ~is in the REFUEL or STARTUP position,' average power range monitor (APRM) scram shall be set down to less than or equal to 15% of rated neutron flux (except as allowed by Note 13 of Table 3.1.1). The IRM flux scram. setting shall be ' set at less than j or equal to 120/125 of full scale.
Sb i
VYNPS -
j- _APRM Flux Scram Trip Setting (Run Mode)
_The scram trip setting must be adjusted to ensure that the LHGR transient peak is not increased for any combination of MFLPD and reactor core thermal povar. LIf the scram requires. a change due .te an abnormal peaking condition, it will be accomplished by. increasing the APRM gain by the ratio in Specification 2.1.A.I.a. thus assuring _a reactor scram at
- j. Icwer than design overpower conditions.
V j Analyses of.the limiting transients show that no scram adjustment is required to assure fuel ~ cladding integrity when i
the transient is initiated f rom the operating limit MCPR (Specification 3.11C).
i Flux Scram Trip Setting'(Refuel or Startup and Hot Standby Mode)
! For operation in the startup mode while the reactor is at low pressure, the reduced APRM scran setting to 15% of rated power provides adequate thermal margin between the setpoint and the safety limit, 25% of the rated. (During an outage
- when it is necessary to check refuel' interlocks, the mode switch must be moved to the startup position. - Since the' APRM reduced scram may be inoperable at that time-due to the disconnection of the LPRMs, it uis required that the IRM l scram and the SRM scram in noncoincidence be in effect. This will ensure that adequate thermal margin is maintained-l between the setpoint and the safety limit.) The margin.is adequate to accommodate anticipated maneuvers associated with station startup. Effects of increasing pressure at zero or low void content are minor, cold water from sources available during startup is not much colder than that already in the system, temperature coefficients are small, and l control rod patterns are constrained to be uniform by operating procedures backed up by the rod worth minimizer.
Worth of individual rods is very low in a uniform rod pattern. ,Thus, of all possible sources of reactivity input, j uniform control rod withdrawal is the most probable cause of significant power rise. Because the flux distribution I associated with uniform rod withdrawals does not involve high local peaks, and because several rods must be moved to
- change power by a significant percentage of rated power, the rate of power rise is very slow. Generally, the heat
- flux is in near equilibrium with the fission rate. -In an assumed uniform rod withdrawal approach to the scram' level,
- the rate of power rise is no more than 5% of rated power per minute, and the APRM system would be more than adequate to assure a scram before the power could exceed the safety limit. The _ reduced APRM scram remains active until the node switch is plac'.d in the RUN position. This switch can occur when reactor pressure is greater than 850 psig. ,
The IRM system consists of 6 chambers, 3 in each of the reactor protection system logic channels. The IRM is a 5-decade instrument which covers the range of power level between that covered by the SRM and the APRM. The 5 decades i are covered by the IRM by means of a range switch and the 5 decades are. broken down into 10 ranges, each being one-half of a decade in size. The IRM scram trip setting of 120/125 of full scale is active in each range of the i IRM. For example, if the instrument were on range 1, the scram setting would be a 120/125 of full scale for that range; likewise, if the instrument were on range 5, the ' scram would be 120/125 of full scale on that range. Thus, as the IRM is ranged up to accommodate the increase in power level, the scram trip setting is also ranged up.- The most significant sources of reactivity change during the power increase are due to control rod withdrawal. For in-sequence control rod withdrawal, the rate of change of power is slow enough due to the physical limitation of withdrawing control rods, that heat flux is in equilibrium with the neutron flux and an IRM scram would result in a reactor
- shutdown well before any-safety limit is. exceeded.
I 14a.
VYNPS , ,
TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT REQUIREMENTS
-Modes in Which -
Functions Must be Minimus Number Required Conditions When Operating Operating Instrument Minimum Conditions For Refuel Startup Run Channels Per Operation Are Not I
Trip Function Trip Settings (1) -(13) Trip System (2) Satisfied (3)- [
1 i X X X 1 A -
- 1. Mode Switch l in Shutdown
$ 2. Manual Scram X X X 1 A
- 3. IRM .
High Flux X X X(11) 2 A
-< 120/125 A INOP X X X(11) 2 l
- 4. APRM High Flux < 0.66W+54%(4) X 2 A or B '
l (flow bias) 2 'A
- High Flux < 15% X X
! (reduced) ,l .
j INOP X 2(5) A or B
. Downscale > 2/125 X~ 2 A or B
- 5. High Reactor <_ 1055 psig X X X 2 A Pressure
- 6. High Drywell < 2.5 psig X X X 2 A Pressure X X 2 A
- 7. Reactor Low (6) >_ 127.0 inches X Water Level
- 8. Scram Discharge <_ 2 A 24 gallons X X X Volume High Level 19
. ~ . . . _ __ _ .
VYNPS- .-
- TABLE 3.1.1 NOTES 1.. When the reactor is subcritical and the. reactor water temperature is less than 2120F,'only the following~ trip functions need to be operable:
a) mode switch in shutdown b) manual scram c) high flux IRM or high flux SRM in coincidence f' d) scram discharge volume high water level .l.
- 2. Whenever an instrument system is found to be inoperable, the instrument system output relay shall be tripped immediately. Except for MSIV & Turbine Stop Valve Position,- this action'shall result in tripping the trip.
system.
- 3. When the requirements in the column " Minimum Number of Operating Instrument Channels Per Trip System" cannot be met for one system, that system shall be tripped. If the . requirements cannot be met for both trip systems, -the appropriate actions listed below shall be taken:
I a) Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
Reduce power level to IRM range and place mode switch in the "Startup/ Hot Standby" position within eight
~
b) hours, i c) Reduce turbine lead and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. ,
d) Reduce reactor. power to less than 30% of rated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
4 "W" is percent rated drive flow where 100% rated-drive flow is that flow equivalent to 48 x 106 lbs/hr core flow.
- 5. To be considered operable an APRM must have at least 2 LPRM inputs per level and at least a total of 13 LPRM inputs, except that channels A, C, D, and F may lose all LPRM inputs from the companion APRM Cabinet plus one additional LPRM input and still be considered operable.
- 6. The top of the enriched fuel has. been designated as 0 inches and provides common reference level for all vessel .
j water level instrumentation. -
- 7. Channel shared by the Reactor Protection and Primary Containment Isolation Systems.
t
. 8 An alarm setting of 1.5 times normal background at rated power shall be established to alert the operator to abnormal radiation levels in primary coolant.
21 ,
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VYNPS . .
i i 9. . Channel signals for the turbine control valve fast closure trip shall be derived from the same event or events which cause the control valve fast closure.
10 A turbine stop valve closure and generator load rejection bypass is permitted when the first stage turbine pressure is less than 30% of normal (220 psta).
- 11. The IRM scram is bypassed when the APRMs are on scale and the mode switch is in the run position.
l 12. For special stability tests, the APRM flux scram shall be < 0.66W + 85% for the duration of testing.
- Adjustments for the ratio of MFLPD to FRP greater than 1.0 are not required while conducting special tests.
y 13. While performing refuel interlock checks which rquire the mode switch to be in Startup, the reduced APRM high
- flux scram need not be operable provided:
- a. The following trip functions are operable:
- 1. Mode switch in shutdown,
- 2. Manual scram
- 3. High flux IRM scram i 4. High flux SRM scram in noncoincidence,
- 5. Scram discharge volume high water level, and; l b. No more than two (2) control rods are withdrawn. The two (2) control rods that can be withdrawn cannot be j faced adjacent or diagonally adjacent.
2I4
i VYNPS 3.1 (cont'd)
High radiation' levels in the main steam line tunnel above that due to the normal nitrogen and oxygen radioactivity is an indication of leaking fuel. A scram is initiated whenever such radiation level exceeds three times normal background. The purpose of this scram is to reduce the source of such radiation to the-extent necessary to prevent release of radioactive materials to the turbine. An alarm is initiated whenever the
- radiation level exceeds 1.5 -times normal background to alert the operator to possible serious radioactivity spikes due to abnormal core behavior. The air ejector off gas monitors serve to back up the main steam line i monitors to provide further assurance against release of radioactive materials to site environs by isolating the main condenser off gas line to the main stack. ,
The main steam line isolation valve closure scram is set to. scram when 'the isolation valves are 10 percent closed from full open in 3-out-of-4 lines. This scram anticipates the pressure and flux transient, which would occur when the valves close. By scraming at this setting, the resultant transient is inaignificant.
A reactor mode switch is provided which actuates or bypasses the various scram functions appropriate to the -
particular plant operating status.
The manual scram function is active in all modes, thus providing for manual means of rapidly inserting control rods during all modes of reactor operation.
The IRM system provides protection against 1short reactor periods and, in conjunction with the reduced APRM system provides protection against excessive power levels in. the startup and intermediate power ranges. A source range monitor (SRM) system is also provided to supply additional neutron level information during startup and can provide scram function with selected shorting links removed during refueling. Thus, the IRM and the reduced APRM are normally required in the startup mode and may be required in the refuel mode. During some refueling activities which require the mode switch in startup; it is ' allowable to disconnect the LPRMs to protect them from damage during under vessel work. In lieu of the protection provided by the reduced APRM scram, both the IRM scram and the SRM scram in noncoincidence are used to provide neutron socitoring protection against excessive power levels. In the power range, the normal APRM . system provides required protection. Thus, t
the IRM system and 15% APRM scram are not required in the run mode. The~ requirement that the IRMs be inserted
} in the core until the APRMs read at least 2/125 of full scale assures that there is proper overlap in the neutron monitoring systems.
If an unsafe failure is detected during surveillance testing, it is desirable to determine as soon as possible if other failures of a similar type have occurred and whether the particular function involved is still operable or capable of meeting the single f ailure criteria. To meet the requirements of Table 3.1.1, it is necessary that all instrument channels in one trip system be operable to permit testing in the other trip system. Thus,
- 29 1
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VYNPS; l
3.1 (Continued) i when failures are detected in the first trip system tested, they would have to be repaired before testing of the other system could begin. In the majority of cases, repairs or replacement can be accomplished quickly. If
- repair or replacement cannot be completed in a reasonable time, operation could continue with one tripped system until the surveillance testing deadline.
The requirement to have all scram functions, except those listed in Table 3.1.1, operable in the " Refuel" mode is to assure that shifting to this mode during reactor operation does~ not diminish the need for the reactor-protection system.
! The ability to bypass one ' instrument channel when necessary to complete surveillance. testing will preclude j continued operation with scrr.m functions which may Se either unable to meet the single . failure criteria or
- completely inoperable. It also eliminates the need for an unnecessary shutdown if the remaining channels and i subsystems are found to be operable. The conditions under which the bypass is permitted require an immediate determination that the particular function is operable. Hewever, during the time a bypass is applied, the l.
i function will not meet the single failure criteria; therefore, it is prudent to limit the. time the bypass is in l effect by requiring that surveillance testing proceed on a continuous basis and that the bypass be removed as
- soon as testing is completed.
- l Sluggish indicator response during the perturbation test will be indicative of a plugged instrument line or I
closed instrument valves. Testing immediately af ter functional testing will assure the operability of the instrument lines. This test assuren the operability of the reactor pressure sensors as well as the reactor level sensors since both parameters are monitored through the same instrument lines.
- . The independence of the safety system circuitry is determined by operation of the scram test switch. Operation of this switch during the refueling outage and following maintenance on these circuits will assure their continued independence.
The calibration frequency, using the TIP system, specified for the LPRMs will provide assurance that the LPRM input to the APRM system will be corrected on a timely basis for LPRM detector depletion characteristics.
i 1
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