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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7811989-09-14014 September 1989 Proposed Tech Specs,Documenting Design Features for Defueling Phase of Operation ML20247L1721989-09-14014 September 1989 Proposed Tech Specs Re Reactivity Control ML20247J2371989-09-14014 September 1989 Proposed Tech Specs Re Fuel Handling & Storage ML20247G7341989-09-14014 September 1989 Proposed Tech Specs Deleting Fire Protection Limiting Condition of Operation & Surveillance Requirements from Tech Specs ML20246K9921989-07-14014 July 1989 Proposed Tech Specs Documenting Improvements to Battery Surveillance Procedures ML20246L0231989-07-14014 July 1989 Proposed Tech Specs,Rewording Basis for Limiting Condition for Operation 4.2.2 Re Operable Circulator ML20244B3771989-06-0909 June 1989 Proposed Tech Specs Re Early Shutdown of Plant ML20245B3211989-04-14014 April 1989 Proposed Tech Specs Re Radiation Monitors & Noble Gas Monitors ML20155J6281988-10-14014 October 1988 Proposed Tech Specs Concerning Administrative Controls ML20155J6111988-10-14014 October 1988 Proposed Tech Specs Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20204E8171988-10-13013 October 1988 Proposed Tech Specs Re Linear channel-high Neutron Flux Trip Setpoints ML20207E1591988-08-0505 August 1988 Proposed Tech Specs Re Auxiliary Electric Sys Involving Proposed Change of Dc Batteries ML20155J7181988-06-14014 June 1988 Revised Draft Tech Specs 3/4.6.5.2,deleting Charcoal Filter Test Exceptions After Painting W/Low Solvent paints,6.5.1.2 & 6.2.3.3,reflecting Recent Util Reorganization & 3/4.7.1.5 & 3/4.7.1.6,requiring One Operable Valve Per Loop ML20151R8191988-04-20020 April 1988 Proposed Tech Specs,Deleting 10CFR51.5(b)2 ML20151S2471988-04-20020 April 1988 Proposed Tech Spec Pages 4.6-4 & 4.6-8,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery ML20148N2751988-03-29029 March 1988 Proposed Tech Specs,Deleting Requirement to Monitor Ambient Temp in Instrument Penetrations Housing Flow Sensors for Dewpoint Moisture Monitoring Sys ML20149M2901988-02-0808 February 1988 Proposed Tech Spec Re Plant Protective Sys Trip Setpoint & Operating Requirements ML20149N0391988-02-0505 February 1988 Proposed Tech Specs Re Changes to Administrative Controls to Reflect Organizational Changes in Util & NRC ML20238C3481987-12-23023 December 1987 Proposed re-drafted Tech Specs,Upgrading Sections Re safety- Related Cooling Sys.Related Info Encl ML20236C6361987-10-15015 October 1987 Proposed Tech Specs,Deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements ML20235W8611987-10-0101 October 1987 Proposed Tech Specs,Clarifying Actions on Inoperable Halogen or Particulate Monitors & Conditions Requiring Weekly Gamma Spectral Analysis on Inservice Gas Waste Tank ML20235B0091987-08-28028 August 1987 Proposed Tech Specs Re Trip Setpoints & Operating Requirements ML20216H7301987-06-25025 June 1987 Proposed Tech Specs,Adding Definition of Calculated Bulk Core Temp & Core Average Inlet Temp for Determination of Core Temp ML20210B7081987-04-23023 April 1987 Proposed Tech Specs Re Surveillance & Calibr Requirements of Plant Protective Sys Parameters ML20206P3931987-04-0808 April 1987 Proposed Tech Specs,Revising 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserve Shutdown Sys,Per Rev 4 to FSAR, Section 3.5.3.3 ML20207P9911987-01-15015 January 1987 Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs ML20207D2421986-12-23023 December 1986 Proposed Tech Specs Deleting Snubber Tables & Correcting Typos ML20212A0661986-12-19019 December 1986 Proposed Tech Specs Re Steam Line Rupture Detection/ Isolation Sys 1996-02-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys 1997-06-17
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ATTAC10fENT 1 PROPOSED CHANGE TO LCO 4.3.10. TABLE 4.3.10-1 AND REASON FOR CHANGE t
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. T S 6 j\\ @JU6uSmu "AI:.I 4. 3.10-1 (een:i=uedl C: ASS I E!DRAr!IC SNUB 3IES (continued) .
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3eiler Teed Scubbers Generaters 325-31-4 375-32-1 375-32-4 375-31-1 375-32-5 375-31-2 375-31-5 375-32-2 373-31-6 375-32-3 375-32-6 375-Il- 3 3eiler 7eed Snubbers 375-526 375-377 375-54 375-421 325-528 375-614 375-138 . 375-422 375-425 375-529 375-641 375-139 375-679 3M-142 375-434-1 375-530 575-532 375-711 373-149 3'75-434-2 375-434-3 3?S-334 375-763 375-152 375-764 175-153 375-435 375-536 3I3-537 375-796 375-297 375-437 375-451 375-553-1 375-820 375-352 375-323 375-397 375-477 375-553-2 375-479 323-556 375-524 375-398 375-843 375-400 375-498 373-563 375-500 375-564 375-844 375-402 375-870 3?S-412 373-501 373-566 315-516 375-572 375-871 375-416 BFS-166 375-420 375-523 375-573 3ciler 7eed Snubbers '-artene-375-89I 375-21?I 3?S-399I 373-14I 3?S-405I 375-15I 375-122I 375-22BI 375-141I 373- 229I 375-414I 3?S-16I 375-417I 375-26I 375-142I 3?S-243I 375-143I 3?S-244I 375-419I 3?S-29I 375-421 375-30I 375-15EI 3PS-245I 375-167I 375-257I 375-422I i'
' 375-31I 375-423I 375-47I 375-181I 375-26CI 375-1973 375-263I 375-430I 375-53I 375-431I 375-56I 375-203I 3?S-264I 375-204I 375-265I 375-432I 373-57I 375-442I 375-74I 375-210E , 375-269I 375-216I 375-444I 375-76I HFSr154I 375-77I 3?S-21SI 375-39 EI
REASON FOR CHA' IGE Audit program for 21/2" and larger piping has identified BFS-166 and BFS-154E, which are located on Class I piping as defined by SR 6-1, but not included in Table 4.3.10-1. Snubbers were apparently omitted f rom the list of Class I snubbers due to an oversight on the part of personnel who per-formed the initial analysis of piping supports. This change corrects that error and fulfills the requirements of LCO 4.3.10(e).
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ATTACIDfENT 2 PROPOSED CHANGE TO SR 5.5.3a)
AND BASIS AND REASON FOR CHANGE I
.- . - - . =. _ . . - . . = _
Fort St. Vrain #1 Technical Specifications Amendment Page 5.5-3 Basis for Soecification SR 5.5.2 The reactor building pressure relief device is designed to protect the building in the evcnt that pressure in the Reactor Building exceeds the turbine building pressure by 3 inches of water. The device consists of louvers installed in a number of individual modules operated by mechanical linkages to pneumatic actuators (see FSAR Section 6.1.3.4). The specified test frequency shall ensure the operability of the reactor building relief system.
Specification SR 5.5.3 - Reactor Building Exhaust Filters, Surveillance The exhaust filters in the reactor building ventilation system shall be tested ;
as follows:
a) A laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Posit.on d C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shall be performed af ter each 4400 hours0.0509 days <br />1.222 hours <br />0.00728 weeks <br />0.00167 months <br /> of l
l cperation of the unit, or following painting, fire, or chemical
- l l release in any ventilation zone co=municating with the unit. The
( results of laboratory carbon sample analysis from the unit shall shew > 90% radioactive = ethyl icdide removed when tested in ac-l cordance with ANSI N510-1975 (130*C, 95% R.H.).
- Defined as any material which could reasonably be expected to interfere with the charcoal to adsorb methyl iodide.
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Fort St. Vrain #1 Technical Specifications
! Amendment Page 5.5-4 b) A halogenated hydrocarbon test shall be performed once per calendar year or af ter each replacement of a charcoal adsorber bank or af ter structural maintenance on the filter housing. Halogenated hydro-carbon removal by the charcoal filters shall be > 99% when conducted at normal flow conditions in accordance with the applicable portions of ANSI N510-1975.
c) The HEPA filters shall be leak tested in place once per calendar year, af ter each complete or partial replacement of a HEPA filter bank, or af ter any structural =aintenance on the filter housing, using cold DOP. Cold DOP removal by the HEPA filters shall be
?. 99% when tested in accordance with the applicable portions of ANSI N510-1975.
d) Flow distribution across the HEPA and charcoal filters will be tested with initial operation of the system and following any struc-cural modification to the filter housings. Air distribution shall be demonstrated within i 20% across the HEPA and charcoal filters I
when tested in accordance with ANSI N510-1973.
i e) Total pressure drop across the combined HEPA filter and charcoal adsorber banks shall be less than 6" 2H O at filter design flow
+ 10%.
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Fort St. Vrain >?1 Technical Specifications Amendment
- Page 5.5-5 Basis for Specification SR 5.5.3 The reactor building exhaust filter system is designed to filter the reactor building atmosphere prior to release to the facility vent stack during both nor=al and accident conditions of operation. The system consists of three 50% capacity units, two of whien are in continuous operation, with the third on standby.
i High efficiency particulate air (HEPA) filters are installed before the char-i J
coal adsorbers to remove particulate matter froE the air stream to prevent
! clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential release of radiciodine to the at=osphere. Bypass leakage for the charcoal adsorbers and particulate removal efficiency for HEPA fil-ters are determined by halogenated hydrocarbon and DOP respectively. The i
i laboratory carbon sa=ple test results indicate a radioactive methyl iodide recoval efficiency for expected accident conditions. The surveillance test I frequencies specified establishes system performance capabilities. If system conditions are specified, the calculated doses will be less than the guide-lines stated in 10 CFR 100 for the accidents analyzed, as indicated in Sec-
! tions 14.S and 14.12 of the FS AR. Pressure drop across the combined HEPA fil-I ter and charcoal adsorber of less than 6 inches of water at the filter de-l sign ficw rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign =atter.
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Fort Se. Vrain #1 Technical Specifications Amendment Page 5.5-6 The activated carbon adsorber in the affected unit should be replaced if a representative sample f ails to pass the iodine removal efficiency test. Any HEPA filters found defective should be replaced.
If painting, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated f rom the fumes, chemicals, or f oreign materials, the same tests and sample analysis should be performed, as required, for operational surveillance.
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i Public Service Company Change Notice No. 868 added external carbon sample canisters across the charcoal adsorbers in the reactor building ventilation system exhaust filters to allow periodic sampling of charcoal effectiveness
- without affecting the integrity of the adsorber beds.
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, This change reflects the NRC staff practice described in Regulatory Guide 1.52, j Revision 2, March 1978.
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