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Category:CONSTRUCTION PERMITS-APPLICATION & AMENDMENTS TO APP
MONTHYEARML20113D5421985-01-11011 January 1985 Application for Amend to CPPR-108 & CPPR-109,exempting Applicant from Requirements of 10CFR50,App A,Gdc 4 Re Dynamic Effects Associated W/Rcs Main Loop Pipe Breaks.Fee Paid ML20091J5141984-05-29029 May 1984 Amend 7 to OL Application,Consisting of Revised Pages to FSAR ML20078K5031983-10-14014 October 1983 Application for Amend to CPPR-108 & CPPR-109,authorizing Sale of Addl 5% Undivided Interest to Municipal Electric Authority of Georgia ML20052B3931982-04-28028 April 1982 Application to Amend CPPR-108 & CPPR-109 Extending Completion Dates of Unit 1 to Mar 1986 (Earliest Date) & Mar 1988 (Latest Date) & Unit 2 to Sept 1987 (Earliest Date) & Sept 1989 (Latest Date) ML20003H5061981-05-0101 May 1981 Application for Amend to Licenses CPPR-108 & CPPR-109 to Modify Plant Chlorine Discharge Structure & Delete Conditions 3(E)(5)(a),(b) & (D).Army Corps of Engineers Ltr Re Discharge Structure Encl ML19343B3021980-12-19019 December 1980 Application for Amend to CPPR-108 & CPPR-109 to Reflect Mod in Plant Design.Mod Would Substitute More Restrictive Primary Leakage Containment for Encl Bldg.Class I & III Fees & Cost/Benefit Assessment Encl ML19254A7911979-08-21021 August 1979 Suppl 6 to Application for CP & Ol.Includes Revised Analysis of Radiological Consequence of LOCA ML20148L4551978-11-0303 November 1978 Suppl 5 to Gap Appl for Constr Permit & Operating Lic for Subj Facil 1985-01-11
[Table view] Category:CONSTRUCTION PERMITS-APPLICATION TO AMEND EXISTING CP
MONTHYEARML20113D5421985-01-11011 January 1985 Application for Amend to CPPR-108 & CPPR-109,exempting Applicant from Requirements of 10CFR50,App A,Gdc 4 Re Dynamic Effects Associated W/Rcs Main Loop Pipe Breaks.Fee Paid ML20078K5031983-10-14014 October 1983 Application for Amend to CPPR-108 & CPPR-109,authorizing Sale of Addl 5% Undivided Interest to Municipal Electric Authority of Georgia ML20052B3931982-04-28028 April 1982 Application to Amend CPPR-108 & CPPR-109 Extending Completion Dates of Unit 1 to Mar 1986 (Earliest Date) & Mar 1988 (Latest Date) & Unit 2 to Sept 1987 (Earliest Date) & Sept 1989 (Latest Date) ML20003H5061981-05-0101 May 1981 Application for Amend to Licenses CPPR-108 & CPPR-109 to Modify Plant Chlorine Discharge Structure & Delete Conditions 3(E)(5)(a),(b) & (D).Army Corps of Engineers Ltr Re Discharge Structure Encl ML19343B3021980-12-19019 December 1980 Application for Amend to CPPR-108 & CPPR-109 to Reflect Mod in Plant Design.Mod Would Substitute More Restrictive Primary Leakage Containment for Encl Bldg.Class I & III Fees & Cost/Benefit Assessment Encl 1985-01-11
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217G6441999-10-13013 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2.Non-proprietary & Proprietary TS & Info Encl.Proprietary Encl Withheld ML20217B1121999-10-0404 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,to Revise TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 ML20212F3521999-09-22022 September 1999 Supplemental Application for Amend to Licenses NPF-68 & NPF-81,proposing Change to SR 3.8.1.13 to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5441999-08-30030 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,proposing to Raise Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7211999-08-26026 August 1999 Rev to 990413 Application for Amend to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 to Be IAW Versions of LCO 3.0.4 & SR 3.0.4 as They Appear in Rev 1 to NUREG-1431 ML20211E9031999-08-24024 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3111999-05-18018 May 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SRs 3.8.1.3 & 3.8.1.13 to Reduce Loading Requirements for DGs ML20206D6831999-04-28028 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,changing Licensing Basis from Present Requirement to Establish Containment Hydrogen Monitoring within 30 Minutes of Initiation of Safety Injection to within 90 Minutes of LOCA ML20205S3731999-04-19019 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS ML20205Q7781999-04-13013 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 That Appear in Existing TS to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as in Rev 1 to NUREG-1431 ML20154M9911998-10-15015 October 1998 Application for Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Short Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys.Ts Pages Encl ML20236R4631998-07-13013 July 1998 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protection Channels ML20236F1541998-06-26026 June 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K4891998-05-15015 May 1998 Suppl Application for Amend to Licenses NPF-78 & NPF-81 Ts. Amend Will Revise New Program 5.5.18 to Extent That Items B,C & D Ref to LCO Action Statement & Revises Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9371998-05-0808 May 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 5.5.7, RCP Flywheel Insp Program, by Specifying Alternate Flywheel Insp Once Every Ten Years ML20199A4041998-01-22022 January 1998 Application for Amends to Licenses NPF-68 & NPF-81,adding Conditions for DGs for Extended DG Completion Time of Fourteen Days ML20199J6591997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Change Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20199G3721997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes That Would Facilitate Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20217H8981997-08-0808 August 1997 Revised Application for Amends to Licenses NPF-68 & NPF-81, Revising TS Re Credit for Boron & Enrichment Increase for Fuel Storage ML20141A8121997-06-13013 June 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.4.10, Pressurizer Safety Valves, to Reduce Nominal Set Pressure by 1% to 2460 Psig & Increase Tolerance to +2% ML20128G9881996-10-0404 October 1996 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20117N6401996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81,changing TS Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6311996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81, Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20101D4081996-03-0505 March 1996 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing TS to Improve for Westinghouse Plants as Represented by NUREG-1431 ML20094N3821995-11-20020 November 1995 Rev to 950501 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Convert Existing TS to Format & Content of NUREG-1431,Westinghouse Improved STS ML20093K2021995-10-16016 October 1995 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J ML20098A4801995-09-22022 September 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20083M0551995-05-12012 May 1995 Application for Amend to License NPF-68,changing TS SR 4.6.1.2 to Support one-time Exemption from Section III.D.1(a) of 10CFR50,App J,Extending Interval for Type a Test from Scheduled 36 Months to Approx 54 Months ML20082T5591995-05-0101 May 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting TSs to Improved TSs for Westinghouse Plants as Represented in NUREG-1431 ML20081J4901995-03-17017 March 1995 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3.9.4 Re Containment Bldg Penetrations,To Allow Personnel Airlock to Be Open During Core Alterations or Movement of Irradiated Fuel within Containment ML20080F7781995-01-20020 January 1995 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 6.4.2 Re Plant Review Board Composition ML20079B1961994-12-29029 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Requesting to Add Automatic Load Sequencer to Plant ML20079A9411994-12-27027 December 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Ts,By Revising Leak Test Frequency for Valves W/Resilient Seals ML20077F2131994-12-0606 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Containment Spray Additive Sys ML20073K3761994-10-0303 October 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS Reactor Pressure Limits as Results of New Analyses That Account for Nonconservatisms Identified in NRC Info Notice 93-058 & Results of RPV Surveillance Capsule Exams ML20073B7181994-09-13013 September 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing Elimination of Containment Spray Additive Sys ML20072F1981994-08-16016 August 1994 Application for Amend to License NPF-68,eliminating Article 2.C.(6) & Associated Attachment 1 of License Re Diesel Maint & Surveillance ML20072F2151994-08-16016 August 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3/4.7.1.1 & Bases Re Setpoint Tolerance for Main Steam Safety Valves ML20070A9841994-06-24024 June 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Values of Z & for Pressurizer Pressure Reactor Trip Instrumentation Trip Setpoints to Allow Use of Alternate Types of Pressure Transmitters ML20069C7271994-05-20020 May 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Heat Flux Channel Factor,Fq(Z),Penalty of 2 Percent in Spec 4.2.2.2.f to cycle-specific COLR to Allow for burnup-dependent Values of Penalty in Excess of 2% ML20070M6711994-04-28028 April 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 3/3.8.1.1, AC Sources Operating, Based on GL 93-05,RG 1.9 & NUMARC 87-00,Rev 1 ML20065F8631994-03-31031 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Revising TS 3/4.7.1.1 & Bases Re Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML20064L7341994-03-18018 March 1994 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes to Ts,Incorporating Technical Substance of Corresponding Spec (LCO 3.3.3) from NUREG-1431,Rev 0 ML20064C7181994-03-0101 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Reinstating Exception 3.0.4 for TS 3.2.4, Quadrant Power Tilt Ratio, ML20063E0591994-02-0303 February 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.7.10,area Temp Monitoring to Section 16.3 of FSAR ML20059D2381993-12-30030 December 1993 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Allow One Time Extension of AOT for RHR Pumps from 3 to 7 Days.One Time Extension Necessary to Allow Mods to RHR Sys While Plant in Mode 1 ML20058A9451993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Table 3.3-2,stating That ESFAS Not Required in Mode 2 When AFW Operating to Supply Sfs.Footnote Will Be Applied to Applicable Modes for Functional Unit 6.e ML20058A9291993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,proposing Revs to TS Re Dc Sources,Including Rev of SRs of Paragraphs 4.8.2.1.e & F & Table 4.8-2, Battery Srs ML20058H9971993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.3.4, Turbine Overspeed Protection to Section 16.3 of Fsar.Ge Proprietary Rept GET-8039 Encl.Proprietary Rept Withheld,Per 10CFR2.790 1999-09-22
[Table view] |
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Q ;9 h.3 December 19, 1980 ,c , a di w
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- 5 Director of Nuclear Reactor Regulation 0 s
-E Attn: Darrell C. Eisenhut, Director Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 ALVIN W. V0GTLE NUCLEAR PLANT-UNITS 1 AND 2 APPLICATION FOR AMENDMENT
Dear Mr. Eisenhut:
Georgia Power Company (GPC) acting on its own behalf and agent for Oglethorpe Electric Membership Corporation, Municipal Electric Authority Of Georgia, and the City Of Dalton by this application requests amendment of CPPR-108 and CPPR-109, Construction Permits for the Alvin W. Vogtle Nuclear Plant, Units 1 and 2, to reflect a modification in plant design.
The modification would substitute for a structure and associated systems described genernlly as'an enclosure building in the application for Vogtle licenses, a more restrictive primary containment leakage commit-ment which, together with onsite meteorological data, ensures more reliably attained offsite post-accident doses which are less than, or comparable to, doses judged to be acceptable for design now and at the time construction was initially authorized.
In support of this application for amendment, Georgia Power Company relies on information submitted in Supplement 6, dated August 12,1979, to its application for Construction Permit and Operating License, which included a description of the associated physical modifications. These modifications would entail removal of the upper portion of the enclosure building and its related equipment described in Sections 1. 2.6, 3.8.4.1.1, and 6.6 of the Vogtle PSAR, while retaining from grade to the 270-foot level an equipment building described in Sections 1.2.6 and 3.8.4.1.1 of Supplement 6.
In further support of this request for amendment, Georgia Power Company will submit under a separate cover on December 30, 1980, Supplement 8 to the application, additional information on the more restrictive primary containment leak rate and the resultant projected offsite. doses for a design basis accident if the requested modifications are authorized.
As was discussed at a meeting with the NRC on December 1,1980, Georgia Power Company, as a part of this amendment request, is prepared to commit to a containment leak rate of 0.2 weight percent per day if the - .
enclosure building is modified. Employing this leakage rate, and dispersion factors derived using NRC methocology and the latest onsite meteorological
/ 8 012230 $ -
f
Mr. Darrell C. Eisenhut Page 2 data, Georgia Power Company has calculated the following design basis accident offsite doses for the Vogtle units, as modified.
Exclusion Area Boundary Thyroid (Rem) 111 Whole Body (Rem) 3 Low Population Zone Thyroid (Rem) 73 Whole Body (Rem) 1 These doses, calculated without taking any credit for leakage filtration even though the majority of the containment penetrations are included within a safety-related negative pressure and filtration boundary, are comparable to, or less than, the projected doses calculated and determined acceptable now and at the time the Vogtle construction was authorized. These dose projections, moreover, would be achieved under the requested modification by increased reliance on the passive primary containment and more restric-tive technical specification requirements rather than the passive / active system comprised of an enclosure building and filtration equipment.
Approval of the requested modification will result in reduced incre-mental environmental impact due to construction and operation. An assessment of the minimal incidental environmental costs and benefits is included as Attachment 1 to this amendment request.
In view of the potential impact on actual construction progress which could result from the NRC's action on the amendment request, and recognizing the limited technical issues presented by the request, we request consideration of our application by January 30, 1981. Three(3) signed originals and forty (40) copies of the application are provided for your use.
The class of this proposed amendment is designated according to 10 CFR 170 requirements. Since this change is deemed not to involve a -
significant hazard consideration and does involve a single issue.it is considered a Class III change for Unit 1 and a Class I change for Unit 2.
A check for $4,400 is enclosed to cover the fees involved.
l fW. E. Ehrenspepjer CAJA4C h
/
Senior Vice Pfesident Power Supply Georgia Power Company Sworn to and subscribed before me this /f day of December,1980.
Y // Y Notary Public sum My Commission Loires Sept. 20,1983
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! Page 1 of 3 ATTACHMENT 1
COST / BENEFIT ASSESSMENT (1) Description of Change:
The proposed design utilizes the existing steel-lined, prestressed, post-tensioned concrete containment building and a revised commitment to i 0.2% per day post-accident leak rate, and assumes no credit for filtration of leakage which enters the penetration area's filter boundary where a j majority of containment penetrations are located. This proposed design modifies the original plant design by not implementing the upper portion of the enclosure building while retaining the lower structure as the equipment building, and deleting the associated filtration system. !
This cost / benefit assessment is based upon: !
Original Design Proposed Design o Prestressed, post-tensioned o No change concrete containment building o Enclosure building o Equipment building (lower portion of original enclosure building) l o 0.3% per day primary contain- o 0.2% per day primary contain-ment leak rate ment leak rate o Two-minute enclosure build- o Not applicable (no credit ing drawdown time taken for existing penetration
- filtration boundary) i (2) Construction Impacts
The proposed design will result in savings in construction man-hours and resource commitments. The original plant design requires a commitment of the following resources that would not be required in the proposed design:
o Construction 350,000 manhours o Engineering No impact i
i
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1 Attachment 1 Page 2 of 3 Cost / Benefit Assessment Resource Commitment -
4 o Structural steel 4,000 tons 2
o Metal siding 200,000 ft o Embeds 120 tons o Ducting 600,000 lbs.
o Conduit 7,000 feet o Cabling 11,200 feet (3) Operational Impacts:
The enclosure building filtration system filters would require periodic testing for filtration capability and leakage, and would require periodic maintenance and possible repair during the life of the plant. Operation and maintenance of the original design would require periodic leak testing of the structure, with consequent building sealing efforts required if sealant deterioration prevents the enclosure building filtra-tion system from attaining a negative 0.25 in. H20 pressure within 2 minutes of initiation. Both features increase the probability of a potential Technical Specification conflict during plant operation that may result in unscheduled outages. These efforts and potential negative impacts are avoided with the proposed design.
l Both the original and proposed plant designs require maintaining specified primary containment leak rates (i.e., 0.3% per day and 0.2% per day, respectively) . Achieving these leak rates requires similar maintenance operations, with a greater effort needed to achieve 0.2% per day.
The proposed design results in generally comparable or lower post-accident doses than are attained with the original design.
Modification of the enclosure building has no impact on doses during normal operation and does not change the plant vent release point. The original enclosure building filtration system was not designed to operate during normal operation, and thus no credit would be taken for any dose reduction afforded by continuous or intermittent operation of this filtra-tion system. The plant vent location and height does not change by modifying the enclosure building.
No significant environmental impacts such as heat rejection to the en-vironment or increase in station water use results by modifying the enclosure building. Heat generated from the operation of enclosure building filtration system equipment would be small, and modifying the enclosure building deletes this equipment from the design.
The external appearance of the station will be enhanced by modifying the enclosure building as it will provide a smaller profile and improves the integration of the facility into the environmental setting. The original
Attachment 1 Page 3 of 3 Cost / Benefit Assessment enclosure building would appear as a large box-like structure nearly 190 feet high and 175 feet wide. The modified building design appears as a cylindrical concrete shell with a smooth hemispherical concrete dome approximately 180 feet high and 150 feet wide.
The operational impact on the air and water quality, due to the effluents, in the vicinity of the plant site was judged to be insignificant for the original design,and implementation of the proposed design will not affect these effluents at all .