|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers ML20065K1931994-04-12012 April 1994 Proposed Tech Specs,Reflecting Removal of Definitions 1.0.Z.B.1 Through 5,change to LCO 3.21.B.1.a (Line 5) Re Ref to 10CFR20.106 & Change to Paragraphs 1,4,5 & 6 (Lines 6,3,8 & 2 Respectively) Re Ref to 10CFR20.106 ML20058N2321993-12-10010 December 1993 Proposed Tech Specs 3/4.21, Environ/Radiological Effluents, 6.5, Station Reporting Requirements & 6.5.1.C.2 Re 10CFR50.59(b) Rept ML20058N2881993-12-10010 December 1993 Proposed Tech Specs for Pressure Vs Temp Operating Limit Curves ML20058M2591993-09-28028 September 1993 Proposed Tech Specs Modifying Organizational Structure by Removing Mgt Positions of Site Manager & Senior Manager of Operation ML20056G5971993-08-31031 August 1993 Proposed TS Re Primary Containment Isolation Valve Tables ML20056G5821993-08-31031 August 1993 Proposed TS Re Primary & Secondary Containment Integrity ML20056G2341993-08-25025 August 1993 Proposed Tech Specs Bases Section to Reflect Operational & Design Changes Made to CNS Svc Water Sys During 1993 Refueling Outage ML20056F3331993-08-23023 August 1993 Proposed Tech Specs 6.0, Administrative Controls, Reflecting Creation of Mgt Position of Vice President - Nuclear ML20045D8991993-06-23023 June 1993 Proposed TS SR 4.9.A.2 Re Determination of Particulate Concentration Level of Diesel Fuel Oil Storage Tanks ML20045C0031993-06-14014 June 1993 Proposed Tech Specs Associated W/Dc Performance Criteria ML20045C8301993-06-14014 June 1993 Proposed Tech Specs Incorporating New Requirements of 10CFR20 ML20128L5561993-02-12012 February 1993 Proposed TS Table 4.2.D, Min Test & Calibr Frequencies for Radiation Monitoring Sys & TS Pages 81 & 84 Re Notes for Tables 4.2.A Through 4.2.F ML20128E6201993-02-0101 February 1993 Proposed Tech Specs Reflecting Current NRC Positions Re Leak Detection & ISI Schedules,Methods,Personnel & Sample Expansion,Per GL 88-01 ML20127B8331993-01-0505 January 1993 Proposed TS Pages 53,55,70 & 71,removing Bus 1A & 1B Low Voltage Auxiliary Relays ML20115F8531992-10-15015 October 1992 Proposed Tech Specs Page 48,reflecting Relocation of Mechanical Vacuum Pump Isolation SRs ML20115A3481992-10-0808 October 1992 Proposed TS Section 6.1.2 Re Offsite & Onsite Organizations, Delineating Responsibilities of Site Manager & 6.2.1.A Re Min Composition of Station Operations Review Committee ML20104B2091992-09-0909 September 1992 Proposed TS 3.1.1 Re Reactor Protection Sys Instrumentation Requirements & TS Table 3.2.D Re Radiation Monitoring Sys That Initiate &/Or Isolate Sys ML20104A8691992-09-0202 September 1992 Proposed TS 3.9 & 4.9 Re Auxiliary Electrical Sys ML20099D4151992-07-28028 July 1992 Proposed TS 3.6 Re LCO for Primary Sys Boundary & 4.6 Re Surveillance Requirements for Primary Sys Boundary ML20113G8241992-05-0404 May 1992 Proposed Tech Spec Pages for Removal of Component Lists,Per Generic Ltr 91-08 ML20096D6111992-05-0404 May 1992 Proposed Tech Specs Change 100 to Eliminate Main Steam Line Radiation Monitor Scram & Isolation Functions ML20090A8061992-02-25025 February 1992 Proposed Tech Specs Re Dc Power Sys 1999-06-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20207A0761999-05-14014 May 1999 Rev 3 to CNS Strategy for Achieving Engineering Excellence ML20206J2661999-04-22022 April 1999 CNS Offsite Dose Assessment Manual (Odam) ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20206P9051998-07-0707 July 1998 Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216D8971998-04-0808 April 1998 Rev 1 to Strategy for Achieving Engineering Excellence ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20203G4271998-02-24024 February 1998 Rev 0 to First Ten-Year Interval Containment Insp Program for Cns ML20202H5311998-02-11011 February 1998 Strategy for Achieving Engineering Excellence ML20216G1571997-09-0505 September 1997 Rev 2.1 to Third 10-Yr Interval Inservice Insp Program ML20210H5641997-08-0707 August 1997 Rev 2 to NPPD CNS Third Interval Inservice Testing Program ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20148G8531997-05-0909 May 1997 Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20138H3861997-04-29029 April 1997 Rev 1.2 to CNS Third Interval IST Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20134E1091996-10-25025 October 1996 NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1 ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20101L8381995-12-31031 December 1995 Reactor Containment Bldg Integrated Leak Rate Test. W/ ML20113B0531995-12-29029 December 1995 Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20093L1901995-10-18018 October 1995 Rev 0 to Third Ten-Yr Interval ISI Program for Cns ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086H7341995-07-14014 July 1995 Rev 7 to CNS Second Ten Yr Interval IST Program ML20086H7601995-06-30030 June 1995 Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20083M0401995-01-20020 January 1995 Rev 1 to Restart Readiness Program ML20083M0901995-01-13013 January 1995 Rev 2 to Startup & Power Ascension Plan ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20083M0141994-11-0909 November 1994 Rev 3 to Phase 1 Plan, ML20083M0321994-11-0808 November 1994 Rev 0 to Restart Readiness Program ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20149F9921994-09-15015 September 1994 Rev 1 to CNS Startup Plan ML20071K9311994-07-27027 July 1994 Diagnostic Self Assessment (DSA) Implementation Plan ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers 1999-06-08
[Table view] |
Text
-
Attachmsnt 1 Revised Technical Specifications for Surveillance Requirements of Radiological Effluent Monitoring Instrumentation Revised Pages 216q 216v 216r 216w Section 3.21.A.2 of Cooper Nuclear Station (CNS) Technical Specifications provides.the limiting condition for operation for gaseous effluent monitoring instrumentation. Specification' 3.21. A.2.a and Table 3.21. A.2 require these various instruments to be operable only during monitored system operation (i.e. Steam Jet Air Ejector and Augmented Off-Gas) or r'eleases via the monitored pathway. ;7ecification 4.21.A.2.b says the instrumentation shall be demonstrated operable by performance of the channel check, source check, channel calibration, and channel. functional test operations during the modes and at the frequencies shown in Table 4.21.A.2. However, Table 4.21.A.2 gives the applicable conditions for performing.the channel-check only. This leaves uncertainty about what the applicable conditions are for performing the other three operations. The channel check conditions are the same as the applicability conditions given in Table 3.21. A.2 for the instruments. The District believes these conditions should apply to the source check, channel calibration, and channel functional test as well. This is based on: 1) The instruments are required to be operable during the conditions specified in Table 3.21.A.2 and all four instrument operations are required to demonstrate operability, 2) Specification 1.Y says surveillance requirements shall be applicable during the operational conditions associated with individual LCO's' unless otherwise stated. It does not follow that the lack of conditions given for the three instrument operations implies they are to be performed at all
' times whether the instruments are required to be operable or not.
Uncertainty in the surveillance requirements for gaseous effluent monitors was
~
a contributing cause of an inspection violation the District received (Inspection Report 50-298/85-26). Although the applicable Technical Specifications have recently been superseded by RETS, the District believes the new RETS should be clarified to prevent any repeat violation. As part of corrective actions, the District is proposing this change to ensure that explicit guidelines are provided which relate s'urveillance requirements with the various modes of plant operation.
Nebraska Public Power District requests to change CNS Technical Specifications to clarify the applicable conditions for performing the source check, channel calibration, and channel functional test operations for the gaseous effluent monitors. The revision involves the following:
- 1. Add an Applicability column to Table 4.21.A.2 for the various monitoring instrumentation that applies to all instrument test operations.
- 2. Add the # note to Table 4.21.A.2 and explained on page 216w.
For reasons similar to the above, the District also requests to change the CNS Technical Specifications to clarify the applicable conditions for performing the source check, channel calibration, and channel functional test operations for the liquid effluent monitors. Specificaion 3.21.A.1.a and Table 3.21.A.1 require these instruments to be operable only during releases via the monitored pathway. Specification 4.21.A.I.a states what performance tests are required to demonstrate operability, however, Table 4.21.A.1 gives the j
8610240025 861017 PDR ADOCK 05000298 PDR
f, applicable ' conditions for performing the channel . check only. The District believes these conditions apply to the source check, channel calibration, and channel functional as well for the same reasons given for the gaseous instruments above. The revision involves the following:
- 1. . Add an Applicability column to Table 4.21. A.1 for the various liquid monitoring instrumentation . that applies to all instrument test operations.
- 2. Add the # note to Table 4.21.A.1 and explained on page 216r.
Evaluation of this Revision with Respect to 10CFRSO.92 The enclosed _ Technical Specification change is judged to involve no significant hazards based on the following:
- 1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Evaluation The proposed amendment clarifies the surveillance requirements of the radiological effluent monitoring instruments. It does not change these instruments' operability requirements or their limiting condition for operation. Performance of the various surveillance tests are still required to demonstrate instrument operability. During operation when releases are being made, the monitoring instrumentation is in operation-i and subject to the various surveillance tests to verify operability.
~
Monitoring capability will be present as assumed in previous evaluations of accidents to enable accurate determination of any risk to member of the public offsite. Any gaseous radiological release will continue to be monitored as before. Because of this, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed license amendment create the possibility for a new or different kind of accident from any accident previously evaluated?
Evaluation The proposed amendment will not allow any new plant mode of operation so it does not create the possibility of a new or different kind of accident.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Evaluation The proposed amendment clarifies the surveillance requirements and does not change the operability or limiting conditions of operation for the radiological monitoring instrumentation. These instruments are still required to have their operability demonstrated by the performance of their surveillance requirements. Monitoring capability during releases will not be reduced from that assumed in previous evaluations. The proposed license amend =ent does not involve a significant reduction in a margin of safety.
t .
TABLE 4.21.A.1 -
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS- .,
i i
, CHANNEL
! CilANNEL SOURCE CllANNEl. FUNCTIONAL- 'APPLIC-INSTRUMENT CllECK CllECK CALIBRATION TEST ABILITYi *
- 1. Gross Beta or Gamma Radioactivity Monitors Providing Alarm and Automatic Isolation R(3) *
- a. Liquid Radwaste Effluents Line D P Q(1)
- 2. Gross Beta or Gamma Radioactivity Monitors Providing Alarm but not Providing Auto-j matic Isolation l a. Service Water System Effluent Line D M R(3) Q(2)
\ u%
i E j i
! 3. Flow Rata Heasurement Devices
- a. Liquid Radwaste Effluent Line D(4) NA R SA
l i
I
E NOTES FOR TABLE 4.21.A.1
- During releases via this pathway.
J Channel (s) shall be.0PERABLE and in-service as indicated except that outages for maintenance and required tests, checks, or calibrations are permitted.
'(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs.for Conditions 1 and 2 below and control room alarm annunciation occurs for Conditions 1, 2, and 3 below.
- 1. Instrument-indicates measured' levels ab'ove the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
(3) The CHANNEL CALIBRATION shall be performed according to established station calibration procedures.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
FREQUENCY NOTATION:
S = At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W = At least once per 7 days.
M = At least once per 31 days.
= At least once per 92 days.
Q SA = At least once per 184 days.
A = At least once per year.
R = At least once per 18 months.
-S/U = Prior to each reactor startup.
P = Completed prior to each release.
NA = Not applicable.
-216r-
TABLE 4.21.A.2
- RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ,
CHANNEL CHANNEL SOURCE CliANNEL FUNCTIONAL APPLIC-INSTRUMENT CHECK CIIECK CALIBRATION TEST ABILITY #
- 1. Steam Jet Air Ejector
- a. Noble Gas Activity Monitor D M R(3) Q(2) R(1) ***
a
- b. Effluent System Flow Rate Measuring Dev' ice D NA R Q *
- 2. Augmented Offgas Treatment System Explosive Gas Monitoring System
- a. Ilydrogen Monitor (2% Monitor) D NA Q(4) M **
- 3. Reactor Building Ventilation Monitoring System
/, a. Noble Gas Activity Monitor (KAMAN) D M R(3) Q(S)
- E j b. Iodine Sampler Cartridge W NA NA NA *
- c. Particulate Sampler Filter W NA NA NA
Effluent System Flow Rate Measuring Device D NA R Q. *
- e. Sampler Flow Rate Measuring Device D NA .R Q- *
- 1. Isolation Monitor (CE)
D Q R(3) R(1) *
- 4. (****)
- a. Noble Gas Activity Monitor (KAMAN) D M R(3)
- b. Iodine Sampler W NA NA 'NA *
- c. Particulate Sampler W NA NA NA *
- d. Effluent System Flow Rate Measuring Device D NA R Q. *
- e. Sampler Flow ' Rate Monitor D NA R Q
,- r r - -
NOTES'FOR TABLE 4.21.A.2
- During releases via this pathway.
- During augmented offgas treatment system operation.
- Elevated Release Point (ERP) Monitoring System, Radwaste Ventilation Monitoring System, and Turbine Building Ventilation Monitoring System
- Channels shall be operable and in service as indicated except that outages are
~
permitted for the purpose of required tests, checks, calibration, or for maintenance.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that' control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument. controls not set in operate mode.
(3) The CHANNEL CALIBRATION shall be established in accordance with established station calibration procedures.
(4) The CHANNEL CALIBRATION shall include the use of a standard gas sample containing a percentage of hydrogen to verify accuracy of the monitoring channel in its operating range.
(5) Same as (2) except Parts 3 and 4 are deleted.
FREQUENCY NOTATION:
S = At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W = At least once per 7 days.
M = At least once per 31 days.
Q = At least once per 92 days.
SA = At least once per 184 days.
A = At least once per year.
R = At least once per 18 months.
S/U =
Prior to each reactor startup.
P = Completed prior to each release.
NA = Not applicable.
-216w-i