|
---|
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
.. . . . - - _ ~ . - - - . . . . - - - - . . - . __ .. - . -. - -. .~
I t
Attachment Technical Specifications Bases Changes EDG Steady State Frequency 1
l i
l i
l f
f.
i l North Anna Power Station ;
I Units 1 and 2 Virginia Electric and Power Company 1
i j
e' 9812300006 981222 PDR P
ADOCK 0 g8 4
1 i
1 1
Unit 1 ,
North Anna Power Station i i
l i
l l
I i
I l
l 4
. - ~ _ _ - . . - _ _ . - - . - _ - . . ~ - ~ - . . ~ - . _ . .
X41 ELECTRICAL POWER SYSTEMS L
BASES.
3/4.8.1 and 3/4.8.2 A.C. and D.C. POWER SOURCES AND DISTRIBUTION (Continued)
The operability requirements for the AAC DG are specified in the Technical Requirements Manual. In addition, to be considered OPERABLE to support the fourteen day action statement the L AAC DG must be capable of providing power to the affected bus (i.e., connectable to the bus with the associated breakers and control power available). If the AAC DG becomes inoperable during the 14 day action statement, the OPERABILITY of the remaining EDGs does not need to be demonstrated since the AAC DG was designed and purchased according to specifications which adequately ensure that common cause fullure is not likely.
The ACTION requirements specified in Modes 5 and 6 address the condition where
! sufficient power is unavailable to recover from postulated events (i.e., fuel handling accident).
Implementation of the ACTION requirements shall not preclude completion of actions to establish l
a safe conservative plant condition. Completion of the requirements will prevent the occurrence of-postulated events for which mitigating actions would be required.
The OPERABILITY of the minimum specified A.C, and D.C. power sources and
, associated distribution systems during shutdown and refueling ensures that 1) the facility can be l maintained in the shutdown or refueling condition for extended time periods,2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status, L and 3) sufficient power is available for systems necessary to recover from postulated events in L these MODES, e.g., the control room emergency ventilation system fans during a fuel handling accident.
The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guide 1.9 " Selection of Diesel Generator Set Capacity for Standby Power Supplies," March 10,1971, and 1.108 " Periodic Testing of Diesel Generator Units Used as Oasite Electric Power Systems at Nuclear Power Plants" Revision 1, August 1977, as modified by Amendment No. 83 issued August 22,1986.
{f The testing of the largest post-accident load rejection in Surveillance Requirement (SR) 4.8.1.1.2.d.2, for demonstrating the OPERABILITY of the EDGs, is in accordance with the testing recommendations of Regulatory Guide 1.9, Revision 1, Section C.S.
L The EDG testing in SRs 4,8.1.1.2.c,4.8.1.1.2.d.5,4.8.1.1.2.d.11.b), and 4.8.1.1.2.e separate
[ the stait reg'uirements for voltage and frequency from the steady state limits. The 10-second start j requires the EDG to meet the minimum values for voltage and frequency. The EDG's voltage must i exceed the 95% value of rated voltage in order for the eutput breaker to automatically close. The minimum frequency requirement is based on the safety analyses assumption for steady state ,
P Amendment No. 203,214, NORTH ANNA - UNIT I B 3/4 8-2 1
- ,,, , ~ ,- - . . , , - - , , . _ .
3/4.8 ELECTRICAL POWER SYSTEMS B ASES -
1 3/4.8.1 and 3/4,8.2 A.C. and D.C. POWER SOURCES AND DISTRIBUTION (Continued) l l
frequency. The steady state voltage and frequency limits are not required to be maintained during L the 10-second start requirement. Following the fast start of the EDG, the time to reach steady state
~ voltage and frequency is periodically monitored in the performance tests. The teste can be used to
[ identify degradation of the governor and voltage regulator performance. The EDG is unloaded in j
! some portions of these surveillance tests and sh6rt-term variations in voltage and frequency, outside the steady state limits may occur in this condition. The safety analyses assume the long-l term steady state electrical power requirements for voltage and frequency to the ECCS equipment is 4160i420 volts and 60i0.5 Hz.
I In lieu of actual accident loading demonstration during the performance of SRs 4.8.1.1.2.d.4 and 4.8.1.1.2.d.6, the EDGs are allowed to supply the required loads by a combination l of evolutions. This testing may include a series of sequential, overlapping, or total steps so that the l entire connection and loading sequence is verified. This method of testing adequately verifies the !
capability of each EDG system to energize the emergency bus and supply the power necessary for )
the required safety equipment to mitigate analyzed events.
- The Surveillance Requirements for demonstrating the OPERABILITY of the Emergency ;
i Diesel Generator batteries and' the Station batteries are based on the recommendations of Regulatory Guide 1.129,'" Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std. 450-1980, "IEEE Recommended Practice for Maintenance, Testing and Replacement of Large Lead Storage Batteries for Generating Stations and Substations," as modified by Amendment No. 97 issued March 25,1988.
1 l
I f
i a
k i.i L NORTH ANNA - UNIT I B 3/4 8-3 Amendment No.
1 4 i
Unit 2 North Anna Power Station i
i l
l 6
(
t 4
3/4.8 ELECTRICAL POWER SYSTEMS BASES.-
during the 14 day action statement, the OPERABILITY of the remaining EDGs does not need to be demonstrated since the AAC DG was designed and purchased according to specifications which
' adequately ensure that common cause failure is not likely.
1 The ACTION requirements specified in Modes 5 and 6 address the condition where sufficient power is unavailable to recover from postulated events (i.e., fuel handling accident).
L Implementation of the ACTION requirements shall not preclude completion of actions to establish l a safe conservative plant condition. Completion of the requirements will prevent the occurrence l postulated events for which mitigating actions would be required. !
The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods,2) sufficient l - instrumentation and control capability is available for monitoring and maintaining the unit status, and 3) sufficient power is available for systems necessary to recover frcm postulated events in these MODES, e.g., a fuel handimg accident. )
l \
The Surveillance Requirements for demonstrating the OPERABILITY of the Emergency Diesel Generators are in accordance with the recommendatbns of Regulatory Guide 1.9 " Selection of Diesel Generator Set Capacity for Standby Power Supplies," March 10,1971, and 1.108
" Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear l Power Plants" Revision 1, August 1977, as modified by Amendment No. 48 issued August 22, l 1986.
l The testing of the largest post-accident load rejection in Surveillance Requircaent (SR) 4.8.1.1.2.d.2, for demonstrating the OPERABILITY of the EDGs, is in accordance with tha testing recommendations of Regulatory Guide 1.9, Revision 1, Section C.5.
The EDG testing in SRs 4.8.1.1.2.c,4.8.1.1.2.d.5,4.8.1.1.2.d.11.b), and 4.8.1.1.2.e separate the start requirements for voltage and frequency from the steady state limits. The 10-second start i requires the EDG to meet the minimum values for voltage and frequency. The EDG's voltage must exceed the 95% value of rated voltage in order for the output breaker to automatically close. The l minimum frequency requirement is based on the safety analyses assumption for steady state
( frequer.cy. The steady state voltage and frequency limits are not required to be maintained during j the 10-second start requirement. Following the fast start of the EDG, the time to reach steady state
- voltage and frequency is periodically monitored in the performance tests. The tests can be used to
} identify degradation of the governor and voltage regulator performance. The EDG is unloaded in
- _ some portions of these surveillance tests and short-term variations in voltage and frequency,
{ outside the steady state limits may occur in this condition. The safety analyses assume the long-1 i.
l . NORTH ANNA - UNIT 2_ B 3/4 8-2 Amendment No. l33,134,195, 4
I-
.- .- --- . - - - . - . ~ . - - - - .. . - _ . - . - .. - - _ - - -
+ .
3/4.8 ELECTRICAL POWER SYSTEMS BASES term steady state electrical power requirements for voltage and frequency to the ECCS equipment is 4160 i420 volts and 6010.5 Hz.
In lieu of actual accident loading demonstration during the performance of SRs 4.8.1.1.2.d.4 and 4.8.1.1.2.d.6, the EDGs are allowed to supply the required loads by a combination of evolutions. This testing may include a series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified. This method of testing adequately veriiles the capability of each EDG system to energize the emergency bus and supply the power necessary for the required safety equipment to mitigate analyzed events.
= The Surveillance Requirements for demonstrating the OPERABILITY of the Emergency Diesel Generator batteries and the Station batteries are based on the recommendations of Regulatory Guide 1.129," Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std 450-1980,"IEEE Recommended Practice
. for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations," as modified by Amendment No. 84 issued March 25,1988.
Containment electrical penetration and penetraticn conductors are protected by either de-energizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during period surveillance.
The surveillance frequency applicable to molded case circuit breakers and/or buses provides assurance of breaker and/or fuse reliability by testing at least one representative sample of each manufacturer's brand of circuit breaker and/or fuse. Each manufacturer's molded case circuit breakers and/or fuses are grouped into representative samples which are then tested on a l rotating basis to ensure that all breakers and/or fuses are tested. If a wide variety exists within any manufacturer's brand of molded case circuit breakers and/or fuses,it is necessary to divide that manufacturer's break.ers and/or fuses into groups and treat each group as a sepamte type of breaker l or fuse for surveillance purposes.
The OPERABILITY of the motor-operated valves thermal and overload protection and/or bypass devices ensures that these devices will not prevent safety elded valves from performing their function. The Surveillance Requirements for demonstrating the OPERABILITY of these devices are in accordance with Regulatory Guide 1.106 " Thermal Overload Protection for Electric Motors on Motor-Operated Valves," Revision 1, March 1977.
i i.
i a
j i NORTH ANNA - UNIT 2 B 3/4 8-3 Amendment No. 495,
.. . -_,- -, - ,- . - - -