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| | number = ML20147D297 | | | number = ML20147D297 |
| | issue date = 09/29/1978 | | | issue date = 09/29/1978 |
| | title = Amend #52 to Facil Oper Lic #DPR-46 Revising Tech Specs Increase in Storage Capacity of Spent Fuel Pool from 740 to 2366 Fuel Assemblies | | | title = Amend 52 to Facil Oper Lic DPR-46 Revising Tech Specs Increase in Storage Capacity of Spent Fuel Pool from 740 to 2366 Fuel Assemblies |
| | author name = Grimes B | | | author name = Grimes B |
| | author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
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| | document type = OPERATING LICENSES & AMENDMENTS, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES & AMENDMENTS, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 4 | | | page count = 4 |
| | | project = TAC:06962, TAC:6962 |
| | | stage = Other |
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MONTHYEARML20147D3301978-09-29029 September 1978 Notice of Issuance of Amend 52 to Facil Oper Lic DPR-46 & Negative Declaration Project stage: Approval ML20147D3201978-09-29029 September 1978 Environ Impact Appraisal for Amend 52 to Facil Oper Lic DPR-46 Concludes That Increase in Storage Capacity for Spent Fuel Pool Will Not Affect Quality of Human Environ Project stage: Other ML20147D2971978-09-29029 September 1978 Amend 52 to Facil Oper Lic DPR-46 Revising Tech Specs Increase in Storage Capacity of Spent Fuel Pool from 740 to 2366 Fuel Assemblies Project stage: Other ML20147D2271978-09-29029 September 1978 Forwards Amend 52 to Facil Oper Lic DPR-46, as Requested in ,Safety Evaluation & Notice of Issuance Project stage: Approval ML20147D3101978-09-29029 September 1978 Safety Evaluation Rept Supporting Amend 52 to Facil Oper Lic DPR-46 Concludes That Installation & Use of New Fuel Racks Can Be Accomplished Safety & Health & Safety of Pub Will Not Be Endangered Project stage: Approval 1978-09-29
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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20147B4911988-02-23023 February 1988 Amend 117 to License DPR-46,revising Tech Specs to Modify Operability Requirements for Rod Sequence Control Sys Rod Worth Minimizer to Allow Banked Position Withdrawal Sys Use Between 10 & 100% Rod Density ML20237E3091987-12-21021 December 1987 Amend 113 to License DPR-46,revising Tech Specs Re Design Features of Fuel Storage Facilities ML20141E8891986-04-10010 April 1986 Amend 98 to License DPR-46,revising Tech Specs to Reflect Addition of Halon Fire Suppression Sys & Fire Detectors in Station Svc Water Pump Room as Part of App R Fire Protection Program ML20147D2971978-09-29029 September 1978 Amend 52 to Facil Oper Lic DPR-46 Revising Tech Specs Increase in Storage Capacity of Spent Fuel Pool from 740 to 2366 Fuel Assemblies 1988-02-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217C7871999-10-0606 October 1999 Application for Amend to License DPR-46,to Revise TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5 to Adopt Implementation Requirements of 10CFR50,App J,Option B,For Performance of Type A,B & C Containment Leakage Rate Testing ML20195J6961999-06-15015 June 1999 Application for Amend to License DPR-46 to Allow USAR Change to Establish Leakage Criteria for Reactor Equipment Cooling (REC) Sys Which Is Sufficiently Conservative to Assure REC Operation at Least Seven Days Following Large Break LOCA ML20195J3961999-06-15015 June 1999 Application for Amend to License DPR-46,revising Containment Overpressure Contribution to ECCS Pump,Revising NPSH Requirement post-LOCA & Revising Encl USAR Section 5.2.6. Proprietary GE Repts Encl.Proprietary Info Withheld ML20195E8951999-06-0808 June 1999 Application for Amend to License DPR-46,correcting Method by Which SGTS Heaters Are to Be Tested ML20205H2831999-03-31031 March 1999 Application for Amend to License DPR-46,modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20236Y4921998-08-0606 August 1998 Application for Amend to License DPR-46,accepting as-built Plant Configuration Involving Unreviewed Safety Question as Specified in Attachment 1 ML20216H0481998-04-15015 April 1998 Application for Amend to License DPR-46,exempting Neutron Detectors from Channel Calibr Requirements Described in TS 4.2.C.Application Supersedes 980402 Request.Revised OL Pages,Encl ML20216H0731998-04-15015 April 1998 Application for Amend to License DPR-46,deleting Max Rated Power for APRM Rod Block Trip Setting in TS Sections 2.1.A.1.d & 3.2.C.Revised OL Pages,Encl ML20217Q2551998-04-0202 April 1998 Application for Amend to License DPR-46,exempting Neutron Detectors from Channel Calibr Requirements Described in TS Table 4.2.C.Revised Operating License Pages,Encl ML20148G2981997-05-30030 May 1997 Application for Amend to License DPR-46,changing TS Re Frequency of Testing RHR Cross Tie Valve Position Indication from Once Per Month to Once Per Operating Cycle ML20138J0691997-05-0505 May 1997 Application for Amend to License DPR-46,relocating Control of Standby Liquid Control Relief Valve Setpoint in TS Section 4.4.A.2.a & Associated Bases ML20148A9971997-05-0202 May 1997 Application for Amend to License DPR-46 Ts,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20147H5441997-03-27027 March 1997 Application for Amend to License DRP-46 Re Proposed Change to TSs to Convert to Improved STS ML20134K3651997-02-10010 February 1997 Application for Amend to License DPR-46 to Provide Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term.. ML20117K3231996-06-0606 June 1996 Application for Amend to License DPR-46,revising TS Section 1.1, Fuel Cladding Integrity, Subsection 1.1.A to Specify New MCPR Value of 1.07.Rev 3 of GE Rept 24A5187, Suppl Reload Licensing Rept for CNS Reload 16 Cycle 17 Encl ML20100R4361996-03-0505 March 1996 Application for Amend to License DPR-46,consisting of Change Request 142,revising TS, DG Enhancements ML20086B7021995-06-28028 June 1995 Application for Amend to License DPR-46.Amend Would Increase RPV Boron Concentration & Mod Surveillance Frequency for SLC Pump Operability Testing ML20085J2571995-06-15015 June 1995 Application for Amend to License DPR-46.Amend Would Extend Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7101995-05-0505 May 1995 Application for Amend to License DPR-46.Amend Would Revise Listed TSs & Associated Bases ML20083A1281995-05-0202 May 1995 Application for Amend to License DPR-46.Amend Would Temporarily Revise SR 4.7.A.2.f.1 to Extend Two Year LLRT Interval Requirement ML20078F4371995-01-27027 January 1995 Suppl to 950126 Proposed Change 135 to License DPR-46 Re Control Room Emergency Filter Sys ML20078S5641994-12-22022 December 1994 Proposed Change 148 to License DPR-46,revising Definition of LCO Consistent W/Guidance Provided in NRC GL 87-09 ML20073J2271994-09-26026 September 1994 Application for Amend to License DPR-46,consisting of Proposed Change 136,revising TS LCOs 3.5.C.1 & 3.5.C.4 to Increase Min Pressure at Which HPCI Sys Required to Be Operable ML20071K1231994-07-26026 July 1994 Application for Amend to License DPR-46,revising CNS TS to Increase Flow Capacity of Control Room Emergency Filter Sys ML20070M6601994-04-26026 April 1994 Proposed Change 126 to License DPR-46,revising TS Tables 3.2.H & 3.2.F,including Associated Notes to Clarify Requirements Re Intermittent Sampling of Hydrogen & Oxygen Concentrations During Normal Plant Operations ML20058N2261993-12-10010 December 1993 Proposed Change 115 to License DPR-46 Ts,Extending Reporting Frequencies of Semiannual Radioactive Matls Release Rept from Semiannual to Annual & Annual Design Change Rept from Annual to Annually or Along W/Usar Updates ML20058N2791993-12-10010 December 1993 Proposed Change 119 to License DPR-46 Ts,Revising Pressure Vs Temp Operating Limit Curves for Plant Based on Results of Testing & Analysis Performed as Part of Util Reactor Vessel Matl Surveillance Program ML20058M2541993-09-28028 September 1993 Application for Amend to License DPR-46,requesting TS Be Revised to Modify Organizational Structure by Removing Mgt Positions of Site Manager & Senior Manager of Operations ML20056G5721993-08-31031 August 1993 Proposed Change 106 to License DPR-46,revising TS Sections Pertaining to Standby Gas Treatment Sys & Secondary & Primary Containment Isolation Valves ML20056G5911993-08-31031 August 1993 Proposed Change 120 to License DPR-46,adding Requirements for Primary Containment Isolation of Drywell Air Sampling Sys to Clarify Requirements for Instrumentation to Initiate Primary Containment Isolation Signals ML20056F3311993-08-23023 August 1993 Proposed Change 121 to License DPR-46,changing TS 6.0, Administrative Controls to Modify Organizational Structure by Creating Mgt Position of Vice President - Nuclear ML20045C8281993-06-14014 June 1993 Proposed Change 117 to License DPR-46,revising TS to Incorporate New Requirements in 10CFR20.Advises That Util Plans to Implement Revised Part 20 on 940101 ML20128E5961993-02-0101 February 1993 Application for Amend to License DPR-46,revising TS to Reflect Current NRC Positions Re Leak Detection & ISI Schedules,Methods,Personnel & Sample Expansion,Per GL 88-01 ML20127B8291993-01-0505 January 1993 Proposed Change 116 to License DPR-46,changing TS to Remove Bus 1 a & 1B Low Voltage Auxiliary Relays for RHR & Core Spray Sys as Result of Plant Mods to Be Implemented During Spring 1993 Refueling Outage ML20115F2591992-10-15015 October 1992 Rev to 920504 Application,Consisting of Proposed Change 100, Eliminating Main Steam Line Radiation Monitor to Accurately Ref Relocation of Mechanical Vacuum Pump Isolation SRs ML20115A3421992-10-0808 October 1992 Application for Amend to License DPR-46,consisting of Proposed Change 111 to Ts,Modifying Onsite Organizational Structure by Creating New Site Mgt Positions to Ensure Acceptable Performance of Util Staff ML20104B2041992-09-0909 September 1992 Proposed Change 110 to License DPR-46,revising TS Table 3.1.1 Re Reactor Protection Sys Instrumentation Requirements to Indicate That MSIV Closure Scram Only Required While in Run Mode & Adding Settings for Core Spray & RHR Sys ML20104A8631992-09-0202 September 1992 Proposed Change 84 to License DPR-46,changing TS to Increase Min Amount of Diesel Fuel Oil Capacity Required to Be Available in Onsite Diesel Fuel Oil Storage Tanks ML20099D4101992-07-28028 July 1992 Proposed Change 109 to License DPR-46,changing TS to Revise pressure-temp Limitation Curves Beyond Current 12 EFPYs & Removing Vessel Matl Surveillance Capsule Withdrawal Schedule from TS Per Guidance in Generic Ltr 91-01 NLS9100589, Application for Amend to License DPR-46,consisting of Proposed Change 99 for Removal of Component Lists from Tss, Per Generic Ltr 91-081992-05-0404 May 1992 Application for Amend to License DPR-46,consisting of Proposed Change 99 for Removal of Component Lists from Tss, Per Generic Ltr 91-08 ML20096D6021992-05-0404 May 1992 Application for Amend to License DPR-46,consisting of TS Change 100 to Eliminate Main Steam Line Radiation Monitor Scram & Isolation Functions ML20090A7861992-02-25025 February 1992 Application for Amend to License DPR-46,consisting of Proposed Change 103,clarifying Dc Power Sys TSs to Better Define Dc Power Sys Operability Criteria NLS9100488, Proposed Change 86 to License DPR-46,revising Tech Specs to Remove Rod Sequence Control Sys from Specs & Reduce Low Power Setpoint for Rod Worth Minimizer from 20% to 10% Power1991-11-15015 November 1991 Proposed Change 86 to License DPR-46,revising Tech Specs to Remove Rod Sequence Control Sys from Specs & Reduce Low Power Setpoint for Rod Worth Minimizer from 20% to 10% Power NLS9100409, Application for Amend to License DPR-46,consisting of Proposed Change 76 to Tech Specs,Adding Operational & Surveillance Requirements for Primary Containment Hydrogen Concentration Analyzer,Per Generic Ltr 83-361991-10-0707 October 1991 Application for Amend to License DPR-46,consisting of Proposed Change 76 to Tech Specs,Adding Operational & Surveillance Requirements for Primary Containment Hydrogen Concentration Analyzer,Per Generic Ltr 83-36 NLS9100581, Suppls 910729 Proposed Change 90 to License DPR-46, Extending Plant Operating Domaine on power-to-flow Map Above Rated Rod Line & Permitting Use of Filter in Rod Block Monitor Sys to Improve Readability of Instrument Table1991-10-0303 October 1991 Suppls 910729 Proposed Change 90 to License DPR-46, Extending Plant Operating Domaine on power-to-flow Map Above Rated Rod Line & Permitting Use of Filter in Rod Block Monitor Sys to Improve Readability of Instrument Table NLS9100058, Application for Amend to License DPR-46,consisting of Proposed Change 93 to Tech Specs Clarifying Terms Sys & Subsystems1991-09-30030 September 1991 Application for Amend to License DPR-46,consisting of Proposed Change 93 to Tech Specs Clarifying Terms Sys & Subsystems NLS9100394, Application for Amend to License DPR-46,consisting of Proposed Change 97 to Tech Specs,Revising Snubber Visual Insp Interval Determination as Provided in Generic Ltr 90-091991-08-0505 August 1991 Application for Amend to License DPR-46,consisting of Proposed Change 97 to Tech Specs,Revising Snubber Visual Insp Interval Determination as Provided in Generic Ltr 90-09 NLS9100187, Application for Amend to License DPR-46,consisting of Proposed Change 90 Re Extended Load Line Limit & ARTS Improvement Program.Rev 1 to Rept NEDC-31892P Encl.Rept Withheld (Ref 10CFR2.790)1991-07-29029 July 1991 Application for Amend to License DPR-46,consisting of Proposed Change 90 Re Extended Load Line Limit & ARTS Improvement Program.Rev 1 to Rept NEDC-31892P Encl.Rept Withheld (Ref 10CFR2.790) NLS9100459, Application for Amend to License DPR-46,consisting of Proposed Change 95 to Provide New Format for Presentation of Info on Page 10 of Tech Spec,Figure 2.1.1 Re Reactor Water Level Indication Correlation1991-07-19019 July 1991 Application for Amend to License DPR-46,consisting of Proposed Change 95 to Provide New Format for Presentation of Info on Page 10 of Tech Spec,Figure 2.1.1 Re Reactor Water Level Indication Correlation NLS9100460, Application for Amend to License DPR-46,consisting of Proposed Change 68 to Tech Spec Section 3.2.D.2, Reactor Bldg Isolation & Standby Gas..., Reflecting Planned Design Change for Two Addl Radiation Monitoring Channels1991-07-18018 July 1991 Application for Amend to License DPR-46,consisting of Proposed Change 68 to Tech Spec Section 3.2.D.2, Reactor Bldg Isolation & Standby Gas..., Reflecting Planned Design Change for Two Addl Radiation Monitoring Channels 1999-06-08
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20566 d
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-NEBRASKA PUBLIC POWER DISTRICT 00CXET NO. 50-298 COOPER NUCLEAR STATION AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. OPR-46
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nebraska Public Power District dated July 22, 1977, as supplemented by letters dated November 30, December 16,1977, June 12, 28, July 5 and 14, 1978, com- .
plies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I;
- 8. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted'in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of l the public; and E. The issuance of this amendment is in accordance with 10 CR Part i 51 of the Ccmmission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the 'iicense is amended by changes to the Technical Soecifications as indicated in the attachment to this license amencment and par & graph 2.C(2) of Facility License No. OPR-46 is hereby amended to read as follows: j (2) Technical Soecifications The Technical Soecifications contained in accendices A and B, as revised througn Amendment No. 52, ara hereby.incorocrated in the license. The licensee '
shal1 operate tne facility in accordance with the
~
Technical Specifications.
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- 3. This license amendment is effective as of the date of its issuance. .E FOR THE NUCLEAR REGULATORY C0tEISSION '
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Brian K. Grimes, Assistant. Director for Engineering and Projects Division of Operating Reactors .
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Attachment:
Changes to the Technical-Specifications SENE*3EE 8 Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT'NO. 52 i FACILITY OPERATING LICENSE NO. DPR-46 0 DOCKET NO. 50-298
- Remove page 218 of Appendix A and replace with revised page 218. Marginal lines indi:: ate area of change. ,
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5.4.C' (contd.)
forth in l
. penetrations shall' be designed in accordance with standards set l
. Section V-2.3.4 of the SAR. .;
i 7 '
5.5 Fuel Storage 4 A. The new fuel' storage facility shall be such that the K,ff dry is less than ) -
0.90 and flooded in less than 0.95.
I
- 3. The spent fuel storage racks are designed and shall be maintained with a ,
nominal 6 9/16 inch center-to-center distance between fuel assemblies placed in the storage racks to ensure a Kegg equivalent to < 0.95 with l the storage pool filled with unborated water. The K f, has been con-servativelycalculatedtobe0.9271whichiswellbu$oOthe=aximum allowable K of. 0.95 as described in Section X-3.5 of Volume IV of the
'SAR. In ad$kfion, fuel'in the storage pool shall have a U-235 loading of 3
< 14.5 grams of U-235 per axial centimeter of fuel assembly. !
C. The spent fuel storage pool is designed and shall be maintained with a f Storage Capacity limited to no more than 2366 fuel assemblies, D. The fuel handling bridge fuel hoist has a load-limit cell set at no more than 1230 pounds. .f 5.6 Seismic Design
[
The seismic design for-Class I structures and equipment is based on dynamic analyses using acceleration response spectrum curves which are based on a ground motion of 0.1.g. The vertical ground acceleration assumed is equal to of the horizontal ground acceleration. For'the design of Class I structures and equipment, the maximum horizontal and vertical accelerations were con- ,
sidered to occur simultaneously. Where' applicable, stresses were added r
directly. !-
The combined stresses resulting from dead, live, pressure, thermal and earthquake having a ground acceleration of 0.2g are such that a safe shut- ;
down can be achieved. [
5.7 Barge Traffie r
Barge traf fic on the Missourt River past the site has been analyzed to i determine that the present size and cargo materials do not create a hazard -
to the safe operation of the plant. Contact will be maintained with the i Corps of Engineers to determine if and when additienal analyses are required due' to changes in barge size or cargo. ,
l i
. +
218
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