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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092K5471995-09-20020 September 1995 Revised Tech Spec Pages 4-31,4-32 & 4-33,incorporating Change in TS Section 4.4.1.5 ML20091L2911995-08-23023 August 1995 Proposed Tech Specs Page 6-11a,incorporating Ref to 10CFR20.1302 ML20087F4921995-08-11011 August 1995 Proposed TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements ML20085N1601995-06-22022 June 1995 Proposed Tech Specs Revising Replacement Pages in Package & Remove Outdated Pages,In Response to NRC Request for Addl Info ML20084L4351995-06-0101 June 1995 Proposed TS 5.3.1.1,describing Use of Advanced Clad Assemblies ML20084N3501995-06-0101 June 1995 Proposed Tech Specs,Deleting RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084B3361995-05-24024 May 1995 Proposed Tech Specs Re Change in Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7841995-05-17017 May 1995 Proposed Tech Specs,Consisting of Change Requests 252, Removing Chemical Addition Sys Requirements from TS to COLR ML20079A7811994-12-23023 December 1994 Proposed Tech Specs Page 3-32a ML20069A6781994-05-20020 May 1994 Proposed Tech Specs,Supporting Cycle 10 Control Rod Trip Insertion Time Testing ML20065M6831994-04-19019 April 1994 Proposed Tech Specs,Reflecting Deletion of Audit Program Frequency Requirements ML20065K0451994-04-11011 April 1994 Proposed Tech Specs Reflecting Relocation of Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR & Providing Direct Ref to Existing Tendon Surveillance Program ML20073C7731994-03-22022 March 1994 Proposed Tech Specs Re Control Rod Trip Insertion Time Testing 1999-09-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] |
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g TABLE 4.1-1 (Continued)
M e.
M CllANNEL DESCRIPTION CllECK TEST CALIBRATE REMARKS CO 00 38. Steam Generator Water Level W NA R
- 39. Turbine Overspeed Trip NA R* NA l
- 40. Sodium Thiosulfate Tank Level NA NA R Indicator *
- 41. Sodium flydroxide Taak Level NA NA R Indicator
- 42. Diesel Generator Protective NA NA R Relaying I
- 43. i KV ES Bus Undervoltage Relays NA M(1) R (1) Relay operation will be checked (Diesel Start) by local test pushbuttons.
- 44. Reactor Coolant Pressure S(1) M R (1) When reactor coolant system is
- Dli Valve Interlock Bistable pressurized above 300 psig of Taves is greater than 200 F.
S - Each Shift T/W - Twice per week R - Each Refueling Period D - Daily B/M - Every 2 months NA - Not Applicable W - Weekly Q - Quarterly B/W - Every two weeks M - Monthly P - Prior to each startup i if not done previous week
- Test to be performed prior to exceeding 20% power during Cycle 5 start up only.
s i
3
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l 4.5 EMERGENCY LOADING SEQUENCE AND POWER TRANSFER, EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.1 E!fERGENCY LOADING SEQUENCE Applicability
-Applies to periodic testing requirements for safety actuation systems.
Obj ective To verify that the Emergency loading sequence and automatic power transfer is operable.
Specifications 4.5.1.l* Sequence and Power Transfer Test
- a. During each refueling interval, a test shall be condo' ted to demonstrate that the emergency loading sequence and power trrasfer is operable.
- b. The test will be considered satisfactory if the following pumps and fans have been successfully started and the following valves have completed their travel on preferred power and tran?ferred to the emergency power as evidenced by the control board ccmponent operating lights, and either the station computer or pressure / flow indication.
- M. U. Pump
- D. H. Pump and D. H. Injection Valves and D. H. Supply Valves
- R. B. Cooling Pump
- R. B. Ventilators
- D. H. Closed Cycle Cooling Pump
- N. S. Closed Cycle Cooling Pump
- D. H. River Cooling Pump .
- N. S. River Cooling Pump
- D. H. and N. S. Pump Area Cooling Fan
- Screen House Area Cooling Fan
- Spray Pump. (Initiated in oincidence with a 2 out of 3 R. B. 30 psi Pressure Test Signal.)
- This test shall be performed prior to Cycle 5 criticality.
l 4.5.1.2 Sequence Test
- a. At intervals not to exceed 3 months, a test shall be conducted to demon-strate that the emergency loading sequence is operable, this test shall be performed on either preferred power or emergency power.
- b. The test will be considered satisfactory if the pumps and fans listed in 4.5.1.lb have been successfully stcrted and the valves listed in 4.5.1.lb have completed their travel as evidenced by the control board conponent operating lights, and either the station computer or pressure / flow indi-cation.
Bases The Emergency loading sequence and automatic power transfer controls the oper-ation of the pu=ps associated with the emergency core cooling system and Reactor Building cooling system.
4-39
T U .t 31 cy m .
- 4.5.2 EMERGENCY CORE COOLING SYSTEM e '
s _ Applicability Applies to. periodic , testing requirement for emergency core cooling systems.
-Objective' s
To verify that the-emergeacy core cooling systems are operable.
t Specification ,
- 4. 5. 2.1' High' Pressure Injection '
- a. During each refueling interval. and following maintenance or modification that affects system flow characteristics, system pumps and system high point vents shall be vented, and a system test shall be conducted to
~
demonstrate that the system is operable.* l
-s .
The M. U. Pump and its required supporting auxiliaries will be started manually by the operator and a test signal will be applied to the
'high p . essure injection valves MU-V-16A, B, C, D to demonstrate actua-tion of the high pressure injection system for emergency core cooling. '
a operation.
- b. The test will be considered satisfactory if the valves have completed their travel and the M.'U. Pumps are running as evidenced by the control board component operating lights. Minimum acceptable injection flow must be greater than or equal to 500 gpm per HPI pump when pump discharge pressure lis 600 psig'or greater (the' pressure
. between the pump- and flow limiting device) and when the RC pressure is equal to or less than 600 psig.
i
- .c. Testing which requires HP1 flow thru MU-V16A, B, C, D shall be con-j ducted only under either of the following condit..ns
- 1) T avg. shall be greater than 3200F.
I
- 2) Head of the Reactor Vessel shall be removed.
- The High Pressure Injection Test shall 'tua performed prior to Cycle 5 criticality. l 1
4.5.2.2 - Low Pressure Injection
- a. During each refueling period. and following maintenance or modification ,
that.affects system flow characteristics, system pumps and high point vents shall be vented, and a system test shall be conducted to demonstrate that the system is operable. The auxiliaries required t for low pressure injection are all included in the emergency loading sequence specified in 4.5.1.** l 1
~
- b. The test will be considered sa'tisfactory if tLe decay heat pumps listed in 4.5.1.lb have been successfully started and the decay heat.
injection valves and the decay heat supply valves have completed their travel as evidenced by the control board component operating lights. Flow shall be verified to b( equal or greater than the v flow assumed in the Safety Analysis for the single corresponding
-RCS~ pressure used in the test.
i -
E 4-41
90 -,
.b. Reactor Building Cooling and Isolation System
- 1. During each refueling. period,~a system test shall be conducted to demonstrate proper operation of the system.* A test signal l will actuate the R.B. emergency cooling system valves to demonstrate operability of the co31ers.
- 2. The test will be considered satisfactory if the valves have completed the'.r expected travel as evidenced by the control board component operating lights, and either the station-couputer or local verification.
- The system test shall be conducted prior to heatup following Cycle 4 refueling.
l 4.5.3.2 cor.ponent Tests
- a. At intarvals not to exceed three months, the components required for reactc r building cooling and isolation will be tested.
- b. The test will be considered satisfactory if the valves have completed their expected travel as evidenced by the control board ccmponent operating lights, and either the station computer or local vetification.
Bases The reactor building cooling and isolation systens ant reactor building spray _
system'are designed to remove the heat in the. containment acrosphere to prevent the building pressure from excaeding the design pressure.
The delivery capability of one reactor building spray pump at a time can be tested by opening the valve in the line from the borated water storage tank, cpening the corresponding valve in the test line, and starting the corresponding pump. _
With the pumps shut down and the borated water storage tank outlet closed, the reactor building spray injection valves can each be opened and closed by the operator action. With the reactor building spray inlet valves closed, low pressure air can be blown through the test connections of the reactor building spray nozzles to demonstrate that the flow paths are open.
The equipment, piping, valves and instrumentation of the reactor building cooling system are arranged so that they can be visually inspected. The cooling units and associated piping are located outside the secondary concrete shield. Personnel can enter the reacter building during power operations to inspect and maintain this equipment.
The reactor building fans are nortally operating periodically, constituting the test that these fans are operable.
Reference (D FSAR, Section 6 4 ,
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4.12__. AIR TREATMENT SYSTEMS 4.12.1 EMERGENCY CONTROL ROOM AIR TREATMENT SYSTEM (
Applicability
- Applies to the emergency control room a treatment system and associated-components.
- Obj ective
- To verify that this system and associated components will be able to perform its design functions.
Specification 4.12.1.] At least every refueling interval or once every 18 months , whichever comes first, the pressure drop across the combined HEPA filters and charcoal adsorber banks of AH-F3A and 33 shall be demonstrar.ed to be less than 6 inches of water at system design flow rate (11G%).
4.12.1.2 a.* The tests and sanole analysis required by Specifice.: ion 3.15.1.2 shall be perforned initially and at least once p c year for standby service or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and following significant painting, steam, fire or chemical release in any ventilation zone cewnunicating with the system that could contaminate the HEPA filters or charcoal adsorbers.
b.* DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the system housing which t.ould affect the HEPA filter bank bypass leakage.
s c.* Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal adsorber bank or af ter any structural maintenance on the system housing which could affect the charcoal adsorber bank bypass leakaya.
- d. Each AH-E18A and B (AH-F3A and B) fan / filter circuit shall be operating at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
i 4.12.1.3 At least once per Tefueling interval or once every 18 months, whichever comes first, automatic initiation of the Control Building isolation and recirculation Dampers AH-D28, 37, 39, and 36 shall be demonstrated as operable.
4.12.1.4 An air distribution test shall be performed on the HEPA filter bank 1- initially, and after any maintenance or testing that could affect the 4
air distribution within the system. The air distribution across the HEPA filter bank shall be uniform within I20%. The test shall be performed at 40,000 cfm (t10%) flow rate.
- Surveillance to be performed prior to Cycle 5 criticality in lieu of once per refueling interval or once per 18 months.
1 4-55 5
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^9 4.12.2'LREACTOR BUILDING PURGE AIR. TREATMENT SYSTEM Applicability ~ , ,
- s. e U -Applies to the reactor building purge air treatment system and associated
-components.
Object!.ve To verify that this system and associated components will-be able to perform
.its design functions.
Specification 4 4.12. 2.~ 1' At least once per refueling interval or once per 18 months , whichever comes first it shall le demonstrated that the pressure drop across
- the combined HEPA filters and charcoal adsorber banks is less than
6 inches of water at system design flow-rate (t10%).
4.12.2.2 a .* The tests and sample analysis required by Specification 3.15.2.2, l shall be performed initially, once per refueling interval or
.18 months, wh!.chever comes first, or after each 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of -
operation ar following significant painting, steam, fire, or chemical rs_ ease in any ventilation zone communicating with the system th2t could contaminate the HEPA filters or churcoal adsorbers.
b .* DOP testing shall be performed after each complete or partial l replacement of a HEPA filter bank or after any structural maintenance ou the system housing which could affect HEPA frame bypass leakage.
. c .* Halogenated hydrocarbon testing shall be performed after each l complete or partial replacement of a charcoal adsorber bank or
.af ter any structural maintenance on the system housing which could affect the charcoal adsorber bank bypass leakage.
d .* The DOP and halogenated hydrocarbon testing shall be performed l at the maximum available flow considering physical restrictions, i.e. , purge valve position, and gaseous radioactive release criteria.
- e. The Reactor Building purge exhaust f ans AH-E7A and B shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month, either during actual purging or using makeup air.
4.12.2.3 An air distribution test shall be performed on the HEPA filter bank initially and after any maintenance or testing that could affect the air distribution within the system. The air distribution across the HEPA filter bank shall be uniform within t20%. The test shall be performed at 25,000 cfm (Il0%) flow rate.
- Surveillance to iie performed prior to Cycle 5 criticality in lieu of once per l 3 refueling interval or once per 18 months.
Bases l
Pressure drop across the combined HEPA filters and charcoal adsorbers of less -l
.than 6 inches of water at the system design flow rate will indicate that the filters and adsorbers 'are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once every refueling interval to .
show system performance capability.
4-55b
. _ . , . _ - _ . -_