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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20072T0521994-09-0606 September 1994 Proposed Tech Specs Modification to Append a of Operating License DPR-35 Re Maintenance of Filled Discharge Pipe ML20072S0501994-09-0606 September 1994 Proposed Tech Specs Re Instrumentation That Initiates Primary Containment Isolation & Initiates or Controls Core & Containment Systems ML20072S0081994-09-0606 September 1994 Proposed Tech Specs Re Primary Containment,Oxygen Concentration & Vacuum Relief ML20072S0861994-09-0606 September 1994 Proposed Tech Specs Re Standby Gas Treatment & Control Room High Efficiency Air Filtration Sys Requirements ML20069M3311994-06-0909 June 1994 Proposed Tech Specs,Increasing Allowed out-of-service Time from 7 Days to 14 Days for Ads,Hpci & RCIC Sys,Including Section 4.5.H, Maint of Filled Discharged Pipe ML20067B7111994-02-0909 February 1994 Proposed Tech Specs Revising Wording for Page 3 of License DPR-35,clarifying Words to Aid Operators & Removing Obsolete Mechanical Snubber Acceptance Criterion BECO-93-156, Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3)1993-12-10010 December 1993 Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3) ML20059A9361993-10-19019 October 1993 Proposed Tech Specs for Removal of Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors BECO-93-132, Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint1993-10-19019 October 1993 Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint ML20046D0441993-08-0909 August 1993 Proposed Tech Specs,Proposing 24 Month Fuel Cycle ML20044G1331993-05-20020 May 1993 Proposed Tech Specs Reducing MSIV Low Turbine Inlet Pressure Setpoint from Greater than or Equal to 880 Lb Psig to Greater than or Equal to 810 Psig & Reducing Min Pressure in Definition of Run Mode from 880 Psig to 785 Psig BECO-93-016, Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively1993-02-11011 February 1993 Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively 1999-06-16
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20205A1451999-03-23023 March 1999 Core Shroud Insp Plan ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20151S3851998-08-31031 August 1998 Long-Term Program:Semi-Annual Rept ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211N6871997-09-16016 September 1997 Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20211G2381997-09-15015 September 1997 Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20216C0631997-08-29029 August 1997 Semi-Annual Long Term Program Schedule ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20210K3551997-07-0101 July 1997 Rev 16 to Procedure 7.8.1, Water Quality Limits ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20092C4331995-09-0101 September 1995 Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test 1999-06-16
[Table view] |
Text
l ATTACHMENT B Station and Switchyard Batteries Revised Surveillance Test and Bases Paaes 195 196 no changes - included for re-pagination 201 i.
9208180140 920810 PDR ADOCK 05000293 P pop Ek
A J
11MITING 30NDITIONS FOR OPERATION SUPUILLANCE REOUIREMENTS
'3.9.A AUXILIARY ELECTRICAL EOUIPMENI 4.9.A AUXILIARY ELECTU CAL EOUIPMENT (Cont'd)- SURVEILL/MCf (Cont'd)
- 4. 4160 volt buses A5 and A6 are d. Once a month the quantity of energized and the associated 480 diesel fuel available shall vcit busc> are energized. be logged.
- 5. The station and switchyard 125 and e. Once a month a sample of 250 volt batteries are operable. diesel fuel shall be checked Each battery shall have an for quality in accordance operabie battery charger, with ASTM 04057-81 or D4177-82. ihe quality shall
- 6. Emergency Bus Degraded Voltage be within the acceptable Annunciation System as specified limit; specified in Table 1 in Table 3.2.B.1 is operable, of ASTM D975-81 and logged.
- 7. Spgi fi cation 2. Station and Switchyard Batteries Two redundant RPS Electrical a. E'rery week the specific Protection Assemblies (EPAO shall gravity, the voltage and be operable at all times on both temperature of the pilot cell inservice power supplies. and overall battery voli +N shall be measured and la. @ d.
- b. Every three months the
- a. Hith one EPA on an inservice measurements shall be made of power supply inoperable, voltage of each cell to continud operation is nearest 0.1 volt, specific permissible provided that the grivity of each ceil, and EPA is returned to operable temperature of every fifth status or power is transferred cell. These measurements to a source with two operable shall be logged.
EPAs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If this requirement cannot be met, trip c. Once each operating cycle, the power source. the stated batteries shall be subjected to a 5..vice l
- b. With both RPS EPAs found to be Discharge Test (load [
inoperable on an inservice profile). The specific l power supply, continued- gravity ana voltage of each operation is permissible, cell shall be determined provided at least one EPA is after the discharge t.nd restored to operable status or logged.
power is transferred to a source with at least one d. Once every five years, the I operable EPA within 30 stated t,atteries shall be l minutes. If this requirement subjected to a Performance l cannot be met, trip the power Discharge Test (capacity). I source. This test will be performed I in lieu of the Service l NOTE: Only applicable if tripping the Discharge Test requirement of I power source would not result in a 4.9.A.2.c above. l scram, t
195 Amendment No. 42, 67, 96, 127
LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.5 Ooeration with Inocerable 4.9.A Auxiliary Electrical Eautoment Eggioment Surveillance (Cont'd)
Whenever the reactor is in Run 3. Emergency 4160V Buses A5-A6 Mode or Startup Mode with the- Degraded Voltage Annunciation rea: tor not in a Cold Condition, System. .
the availability of electric power shall be as specified in 3.9.B.1, a. Once each operating cycle, 3.9.B.2, 3.9.B.3, 3.9.B.4, and calibrate the alarm sensor.
3.9.B.5.
- b. Once each 31 days perform a
- 1. From and after the date that channel functional test on incoming power is not available the alarm system.
from the startam or shutdown transformer, contin A' m ctor c. In the event the alarm system operation is permissible unaer is determined inoptrable this condition for seven days, under 3.b above, commence During this period, both diesel logging safety related bus generators and associated voltage every 30 minutes emergency buses must be until such time as the alarm "
demonstrated to be operable, is restored to operable status.
- 2. Frora and after the date that y incoming power is not available 4. RPS Electrical Protection from both startup and shutdown Assemblies transformers, continued operation is permissible, provided both a. Each pair of redundant RPS diesel generators and associated EPAs shall be determined to emergency buses are demonstrated be operable at least once per g to be operable, all core and 6 months by performance of an containment cooling systems are instrument functional test.
operable, reactor power level is reduced to 251.-of_ design and the b. Once per operating cycle, NRC is notified within-one (1) each pair of redundant RPS hour as required by 10CFR50.72. EPAs shall be determined to be operable by performanca of
- 3. From and after the date that one an instrument calibration and -
of the diesel generators-or by verifying tripping of the associated emergency bus is made circuit breakers upon the-or found to be~ inoperable for any simulated conditions for reason,' continued reactor automatic actuation of the operation i_s permissible in protective relays within the accordance with Specificatic, following limits:
3.5.F if Specificatior. 3.9. A.1 and
.3.9.A.2.a are satisfied. Overvoltage 1 132 volts Undervoltage 1 108 volts
- 4 .- From and after the date-that one Underfrequency 1 57H z of the diesel generators or
- ssociated emergency buses and either the shutdown or startup transformer power source are made Amendment No. 88, 127 196
4 b1SJji: (Cont'd) 4.9 deliver full flow. Periodic testing of the various components, plus a functional test once per cycle, is sufficient to maintain adequate reliability.
Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure. The type of surveillance described in this specification has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
The Service Discharge Test provides indication of the batteries' ability to satisfy the design requirements (battery duty cycle) of the associated de system. This test will be performed using simulated or actual lot.is at the rates and for the duration specified in the design load profile. A once per cycle testing interval was chosen to coincide with planned outages.
The Performance Discharge Test provides adequate indication and assurance that the batteries have the specified ampere hour capacity. The results of these tests w;11 be logged and compared with the manufacturer's recommendations of acceptability. This test is performed once every five '
years in lieu of the Service Discharge test that would normally occur within that time frame.
The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators. Water content should be minimized because water in the fuel could contribute to excessive damage to the diesel engine.
The electrical protection assemt' lies (EPAs) on the RPS inservice power supplies, either two motor generator sets or one motor generatoc and the alternative supply, consist of protective relays that trip their incorporated circuit breakers on overvoltage, undervoltage, or underfrequancy conditions.
There are two EPAs in series per power source.- It is necessary to periodically test the relays to ensure the sensor is operating correctly and to ensure the trip unit is operable. Rasea on experience at conventional and nuclear power plants, a six-month frequency for the channel functional test is established. This frequency is consistent with the Standard Technical Specifications.
The EPAs of the power sources to the RPS shall be determined to Se operable by performance of a channel calibration of the relays once per op' crating cycle. During calibration, a transfer to the alternative power soune is required; however, prior to switching to alternative feed, de-energization of the applicable MG set power source must be accomplished. This results in a half scram on the channel being calibrated until the alternative power sourt is connected and the half scram is cleared. Based on operating experience, drift of the EPA protective relays is not significant. Therefore, to avoid possible spurious scrams, a calibration frequency of once per cycle io established.
Amendment flo. 127, 135, 141 201
9 ATTACliMENT C Station and Switchyard Battgr_ig Markec-Up Technical Specification and Ba;es Page_1 195 201
. . . ' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIRENENTS 1
3.9.A AUXILIARY ELECTRICAL EOUIPMEMr 4.9.A AUXILIARY ELECTRICAL EOUIPMENT (Cont'd) _
SURVEILLANCE (Cont'd)
- 4. 4160 volt buses A5 and A6 are d. Once a month the quantity of energized and the associated 480 diesel fuel available shall
-volt buses are energized. be logged.
- 5. The station and switchyard 125 and e. Once a month a sample of 250 volt batteries are operable. diesel fuel shall be checked Each b;ittery shall have an for quality in accordance operable battery chargtr. wi+h ASTN D4057-81 or D4177-82. The quality shall j 6. Emergency Bus Degraded Voltage be within the acceptable j Annunciation System as specified limits specified in Table 1 in Table 3.2.B.1 is operable, of ASTM 0975-81 and logged.
V ' 7. Snecification 2. Station and Switchyard Batteries Two redundant RPS Electrical a. Every week the specific Protection Assemblies (EPAs) shall gravity, the voltage and be operable at all t~mes on both . temperature of the pilot cell inservice power supplies. and overall battery voltage shall be measured and logged.
Action i _
- b. Every three months the
- a. With one EPA on an inservice measurements shall be made of j power supply inoperable, voltase of each cell to continued operation is nearest 0.1 volt, specific permissible provided that the gravity of aach cell, and EPA is returned to operable temperature of every fifth status or power is transferred cell. These measurements I' to a source with two operable shall be logged.
I EPAs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If this m, f requirement cannot be met, trip c. Once each operating cycle the power source. the stated batt.eJ i e M pg b p .g subjected to a'hted lesd j
! b. With both RPS EPAs found to be d45 darge-test. The specific g7s,/, -
{ inoperable on an inservice gravity and voltage of each power supply, continued cell shall be determined operation is permissible, after the discharge and
{ , provided at least one EPA is logged.
\ restored to operable status or d. g power is transferred to a 3. Emergency 4160V Buses AS-A6 source with at least one Degraded Voltage Annunciation
!' operable EPA within 30 System.
minutes. If this requirement cannot be met, trip the power a. nce each operating cycle, source. calibrate the alarm sensor.
NOTE: Only applicable if tripping the . Once each 31 days perform a channel functional test on
/ power scram. source would not result in a the alarm system.
O st s t e- s
a , ,h f.d bafra...> .1im /4,)
Rev3stonM36 #* Y *#0 # * ~ ' ' ' '
A.nendment No. 42, 61, 96. A27' T J 6 e " E )- /l" 195 1 f n / .. u e r / # /* - < # e' I~ #l' l ga fn . O., u t. ., r % l m "' * ~ d
fLA1LS: (Cont'd) i
. 4.9 deliver full flow. Periodic tescing of the various components, plus a functional test once per cycle, is sufficient to maintain adequate reliability' Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure. The type of y' surveillance described in thi. sne.;fication has been demonstrated over the 6 years to provide an indication of a c~ ell becoming irregular or unserviceable U l_on_g before it_becom_es_ a failjur fin addHTon, thT~cheHs describ'EU7150
~
~c;.2_-
'provid&~ adequate indicaTron that the batteries have the specified ampere hp (xapabi1ity.f-c s
N ____._
(o o / The diesel fuel oil quality must be checked to ensure proper operation of the p [ diesel generators. Hater content should be minimized because water in the fuel could con' ibute to excessive damage to the diesel engine.
The electrical protection assemblies (EPAs) on the RPS inservice power d l
supplies, either two motor generator sets or one motor generator and the f alternative supply, consist of protective relays that trip their incorporated I circuit breakers on overvoltage, undervoltage, or underfrequency conditions. l There are two EPAs in series per power source. It is necessary to l]
periodically test the relays to ensure the sensor is operating correctly and >
to ensure the trip unit is operable. Based on experience at conventional and nuclear power plants, a six-ronth frequency for the channel functional test is (
established. This frequency is consistent with the Standard Technical Specifications.
The EPAs of the power sources to the RPS shall be determined to be operable by performance of a channel calibration of the relays once per operating cycle.
During calibration, a transfer to the alternative power source is required; '
however, prior to switching to alternative feed, de-energi2ation of the h applicable MG set power source must be accomplished. This results in a half a scram on the channel being calibrated until the alternative power source is connected and the half scram is cleared. Based on operating experience, drif t I
of the EPA protective relays is not significant. Therefore, to avoid possible spurious scrams, a calibration frequency of once per cycle is established.
l l
l l
ww' ,
Amendment No. 127. 12f, f.O 201
~
V INSERT "A" TO BASES The Service Discharge Test provides indication of the batteries' ability to satisfy the design requirements (battery duty cycle) of the associated dc system. This test will be performed using simulated or actual loads at the rates ano for the duration specified in the design load profile. A once per cycle testing interval was chosen to coincide with planned outages.
The Performance Discharge Test provides adequate indication and assurance that the batteries have the specified ampere hour capacity. The results of these tests will be logged and compared with the manufacturer's recommendations of acceptability. This test is performed once every five years in lieu of the Service Discharge test that would normally occur within that time frame.
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