Proposed Tech Specs Deleting Verification That Each Upper & Lower Containment Purge Sys Supply & Exhaust Valve Actuates to Isolation Postition on High Relative Humidity Isolation SignalML20063E666 |
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Catawba |
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Issue date: |
01/27/1994 |
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From: |
DUKE POWER CO. |
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To: |
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Shared Package |
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ML20063E608 |
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References |
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NUDOCS 9402100162 |
Download: ML20063E666 (5) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start 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ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation 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Not Be Used for Westinghouse Model D5 Steam Generators in Use at Catawba Unit 2 ML20140A6681997-05-27027 May 1997 Proposed Tech Specs,Removing Surveillance Requirement 4.7.13.3a.2 Which Specifies 112,320 Gallon Min Volume of Borated Water Be Available to Supply Standby Makeup Pump ML20141C2281997-05-0808 May 1997 Proposed Tech Specs Allowing Natural Circulation Testing in Mode 3 Following Steam Generator Replacement for Catawba Unit 1 ML20136G2471997-03-0707 March 1997 Proposed Tech Specs Re SGTR Evaluation ML20133E6801997-01-0303 January 1997 Proposed Tech Specs to Eliminate SI Signal on Low Steam Line Pressure.Unnecessary SI Actuation Causes Unnecessary Challenges to Plant Safety Sys,Unnecessary Thermal Transient & Increases Actuation Cycles ML20132F0631996-12-12012 December 1996 Proposed Tech Specs,Section 3/4.3.3.1,for Units 1 & 2 Clarifying Info Re Operation of Radiation Monitors for Plant Operations ML20134H3281996-11-0404 November 1996 Proposed Tech Specs to Licenses NPF-35 & NPF-52,eliminating During Shutdown Restriction for 18 Month Standby Shutdown Sys DG Insp TS Surveillance 4.7.13.1.c ML20113G4431996-09-21021 September 1996 Proposed Tech Specs 8.3 Re Onsite Power Systems ML20117K1011996-08-29029 August 1996 Proposed Tech Specs,Replacing 960516 Response to Concerns Re Proposed Changes for Diesel Starting Air Sys Surveillance Testing ML20116K4601996-08-0808 August 1996 Proposed Tech Specs 6.9.1.9 Re Listings of Core Operating Limit Methodologies ML20113C7201996-06-21021 June 1996 Proposed Tech Specs 3.9.6,revising Term Lifting Loads to Lifting Force Used in Manipulator Crane TS 3.9.6b.2 & Redefining Auxiliary Hoist Min Capacities ML20112G9961996-06-0606 June 1996 Proposed Tech Specs,Reflecting Separate Volumes ML20112F6311996-06-0505 June 1996 Proposed Tech Specs 3/4.6 Re Containment Systems & 3/4.6.1 Re Primary Containment Integrity ML20112A7571996-05-16016 May 1996 Proposed Tech Specs 3/4.8 Re Surveillance Requirements ML20101M4741996-04-0303 April 1996 Proposed TS 3/4.6.4.3 & Bases Re Hydrogen Mitigation Sys ML20101H6101996-03-15015 March 1996 Proposed Tech Specs Re Replacement of SGs ML20100P0521996-03-0404 March 1996 Proposed Tech Specs Re Rev to 10CFR50,App J Which Provided for Reduced Test Frequency for Qualified Containment ML20096E8611996-01-19019 January 1996 Proposed Tech Specs,Providing Approved Revs to TS 6.9.1.9 to Incorporate Anticipated Revs to TRs DPC-NE-3000P-A & DPC-3002-A ML20096E5951996-01-12012 January 1996 Proposed Tech Specs Re Containment Leak Rate Testing Requirements of 10CFR50 App J,Option B 1999-09-16
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20210N9641999-07-26026 July 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20211C3731999-07-26026 July 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual & List of Effective Pages ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20210A5911999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20216D4061999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitment Manual, List of Effective Pages ML20211C3751999-05-19019 May 1999 5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. Page 1 of 15 in Section 4.1 of Incoming Submittal Not Included ML20195B4181999-05-18018 May 1999 Revised Pages to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206T0571999-05-0505 May 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual. with List of Effective Pages ML20206J4531999-04-22022 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206Q8741999-04-22022 April 1999 Revs to CNS Selected Licensee Commitments Manual,Including Page 5 of List of Effective Pages & Pages 1-11 to Chapter 16.9-13.With ML20206B1271999-04-15015 April 1999 CNS Selected Licensee Commitments Manual, List of Effective Pages ML20206C0391999-04-15015 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20204G2541999-03-16016 March 1999 Revised Pages to Catawba Nuclear Station Licensee Commitments Manual ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20205B1341999-03-11011 March 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20204E7271999-03-0808 March 1999 Chapter 16.5-2,page 1-3 to CNS Selected Licensee Commitments Manual. with List of Effective Pages ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20199H4061999-01-16016 January 1999 Revised CNS Selected Licensee Commitments Manual ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review ML20151T9491998-09-0808 September 1998 Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More Restrictive Surveillance Requirements ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5751998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.2 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A6571998-08-0606 August 1998 TS Page 3/4 8-9 Re Notice of Enforcement Discretion Request from Enforcing TS Surveillance Requirement 4.8.1.1.2i.2 ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236P8671998-07-0606 July 1998 Updated Pages to Catawba Nuclear Station Selected License Commitments Manual ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20249B6221998-06-11011 June 1998 Revised Table of Contents for Chapter 16 of Selected License Commitments Manual ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20247Q9871998-05-11011 May 1998 Revised Chapter 16 to Selected License Commitment Manual ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20216B9721998-04-0808 April 1998 Proposed Tech Specs 3/4.6.5 Re Ice Condenser Reduction of Required Ice Weight ML20217C7121998-03-20020 March 1998 Proposed Improved TS Section 3.6 Re Containment Sys ML20216B7691998-03-0909 March 1998 Proposed Tech Specs Pages Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Also Included ML20217Q3741998-03-0303 March 1998 Proposed Tech Specs Re Catawba Safety Review Group ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR 1999-09-16
[Table view] |
Text
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CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES f LIMITING CONDITION FOR OPERATION u
Y 3.6.3 The containment isolation valves specified in Tables 3.6-2a and 3.6-2b shall be OPERABLE with isolation times as shown in Tables 3.6-2a and 3.6-2b.
At'PLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one or more of the isolation valve (s) specified in Tables 3.6-2a and 3.6-2b d inoperable, maintain at least one isolation valve OPERABLE in each affected peneteation that is open and: ,
- a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or ,
- b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or ;
- c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at '
least one closed manual valve or blind flange, or
- d. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS {
4.6.3.1 The isolation valves specified in Tables 3.6-2a and 3.6-2b shall be
.iemenstrated OPERABLE prior to returning the valve to service after mainte- .
nance, repair or replacement work is performed on the valve or its associated A.
actuator, control or power circuit by performance of a cycling test and verifi- ;
cation of isolation time.
9402100162 940127 e' ~
(-
PDR ADOCK 05000413 P PDR CATAWBA - UNITS 1 & 2 3/4 6-20
_C_ONTAINMENT SYSTEMS i SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve specified in Tables 3.6-2a and 3.6-2b shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
- a. Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position;**
- b. Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position;**
, c. Verifying that on a Containment Radioactivity-High test signal, each purge and exhaust valve actuates to its isolation position -end-- ,
-d. Verifying th:t ca : "igh R:lstiv: Hamidity ([70%) i:01:ti:n t:::
- eign:1, :::h upper and !cwer cent:iament per;e :uaply and exhaust .
1:!v: :stuste: te it: 1:012 tier petition.
4.6.3.3 The isolat'en time of each power-operated or automatic valve of '
Tables 3.6-2a and 3.6-2b shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
l l
1
- This surveillance need not be performed until prior to entering HOT SHUTDCWN I following the Unit 1 first refueling. )
CATAWBA - UNITS 1 & 2 3/4 6-21
i REFUELING OPERATIONS 3/4.9.4 ' CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
- a. The equipment hatch closed and held in place by a minimum of four :
bolts, i
- b. A minimum of one door in each airlock is closed, and j
- c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
- 1) Closed by an isolation valve, blind flange, or manual valve, or
- 2) Exhausting through an OPERABLE Reactor Building Containment Purge System HEPA filters and activated carbon adsorbers. .
APPLICABILITY: During CORT' ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
- a. With the requirements of the above specification not satisfied for reasons other than the heaters tested per 4.9.4.2.a and 4.9.4.2.d.2, ;
immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building. ,
- b. With a heater tested per 4.9.4.2.a and 4.9.4.2.d.2 inoperable, restore the inoperable heater to operable status within 7 days, or file a Special Report in accordance with Specification 6.9.2 within 30 days, specifying the reason for inoperability and the planned actions to- :
return the heater to operable status.
S_URVEILLANCE REQUIREMENTS 4.9.4.1 Each of the above required containment building penetrations shall be determined to be either in its closed / isolated-condition or exhausting through an OPERABLE Reactor Building Containment Purge System with the ::p 2i ity cf -
tcing cutomatically i cleted upon hecter failure within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of ,
irradiated fuel in the containment building by: '
- a. Verifying the penetrations are in their closed / isolated condition, or
- b. Ver fy "; the upper end !cwcr i 4
- nteiment purge :upply end cr%uct-m 1 . , m ,. -1m, a ..mmm
- U4nk Dm1,+4.m Lt . 4 A 4 + . . +mr+ r4mm*1
'ixh];s/b[ Egad fu d} TEN 65[$u';5<2dcj;a,,,J }Wt s%.
CATAWBA - UNITS 1 & 2 3/4 9-4 Amendment No. 90 (Unit 1)
Amendment No. 84 (Unit 2)
7 ,
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FOR INFORMATION ONLY REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 4 9.4.2 The Reactor Building Containment Purge System shall be demonstrated OPERABLEi ;
- a. At least once per 31 days by initiating flow through the HEPA filters and activcted carbon adsorbers and verifying that the system operates ,
for at least 10 continuous hours with the heaters operating; >
- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or activated carbon adsorber housings, or :
(2) following painting, fire, or chemical release in any ventilation ,
zone communicating with the system by:
- 1) Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedures guidance in Regula-tory Positions C.5.a, C.5.c, and C.S.d* of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 25,000 cfm 10% (both exhaust fans operating);
- 2) Verifying within 31 days after removal, that a laboratory analy- ,
sis ** of a representative activated carbon sample'obtained in '
accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, '
Revision 2, March 1978, and tested per ASTM-D3803-89, has a methyl iodide penetration of less than 6%; and
- 3) Verifying a system flow rate of 25,000 cfm 10% (both exhaust l fans operating) during system operation when tested in accordance with ANSI N510-1980. 1
- c. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of activated carbon adsorber operation, by ,
verifying, within 31 days af ter removal, that a laboratory analysis ** >
of a representative activated carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, and tested per ASTM D3803-89 has a methyl iodide penetra-tion of less than 6%;
- d. At least once per 18 months by:
- 1) Verifying that the pressure drop across the combined HEPA fil-ters, activated carbon adsorber banks, and prefilters is less i than 8 inches Water Gauge while operating the system at a flow l rate of 25,000 cfm 10% (both exhaust fans operating); and
- The requirement for reducing refrigerant concentration to 0.01 ppm may be ,
satisfied by operating the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with heaters on and operating.
- Activated carbon adsorber samples are tested at 30 degrees C and 95% RH. j CATAWBA - UNITS 1 & 2 3/4 9-5 Amendment No. 90 (Unit _1)
Amendment No. od (Unit 2)
' 4 NO CHANGES THIS PAGE.
^ ""
REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued)
- 2) . Verifying that the filter train duct heater dissipates ,
120 12 kW at a nominal voltage of 600 vac. i
- e. After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for'a D0P test aerosol while operating the system at a flow rate of 25,000 cfm 10% (both exhaust fans operating); and
- f. After each complete or partial replacement of an activated carbon adsorber bank, by verifying that the cleanup system. bank satisfies the in place penetration and bypass leakage testing acceptance cri-teria of less than 1% in accordance with ANSI N510-1980 for a halo-genated hydrocarbon refrigerant test gas while operating the system at a flow rate of 25,000 cfm 10% (both exhaust fans operating CATAWBA - UNITS 1 & 2 3/4 9-6 Amendment No. 90(Unit 1)
Amendment No. 84 (Unit 2)
, _ _ _