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| | ,i GENERAL 0FFICE |
| | .. Nebraska Public Power District "S 8 |
| | " * ""EeAfo1*E #s"0^85^""*" |
| | NLS8400076 February 29, 1984 Office of Nuclear Reactor Regulation Operating Reactor Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention : Mr. D. B. Vassallo, Chief - |
| | |
| | ==Dear Mr. Vassallo:== |
| | |
| | ==Subject:== |
| | Proposed Change No.11 to Technical Specifications Cooper Nuclear Station: 0737 NRC Docket No. 50-298, DPR-46 In accordance with the applicable provisions specified in 10CFR50, Nebraska Public Power District requests that the Technical Specifications for Cooper Nuclear Station (CNS) be revised to incorporate the miscellaneous changes listed below: |
| | Attachment Subject 1 |
| | NUREG-0737 (Generic Letter 83-36) 2 Fire Detection Instruments 3 Editorial Change A discussion and the applicable revised Technical Specification pages are contained in each attachment. Each modification to the Technical Specifications within this proposed change has been Q-evaluated with respect to the requirements of 10CFR50.92. The results of individual evaluations are included within each attachment. |
| | mn O |
| | Ox By copy of this letter and attachments the appropriate State of Nebraska Official is being notified in accordance with 10CFR50.91(b) . |
| | oc g These changes have been reviewed by the necessary Safety e$ Review Committees and payment for a Class II amendment in the man. |
| | amount of $1,200 is submitted, b |
| | I 4 ,'soo Mh . |
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| | l P ge 2 F:brutry 29, 1984 Should you have any questions or require additional information, please contact me. |
| | In addition to . three signed originals, 40 copies are also submitted for your use. |
| | Sincerely, L, G. Kuncl |
| | ' Assistant General Manager - Nuclear LGK/gmc:emz1/10 Attachments |
| | - cc: II. E. Simmons Department of Ilecith State of Nebraska e- |
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| | 2 Pcg3 3 Ftbrutry 29, 1984 STATE OF NEBRASKA) |
| | )ss PLATTE COUNTY ) |
| | L. _G. Kuncl, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to submit this request on behalf of Nebraska Public Pcwer District; and that the statements contained herein are true to the best of his knowledge and belief. |
| | 1 W |
| | U G. Kuncl Subscribed in my presence and sworn to before me thisfpd day of % CPinnnu , 1984. |
| | O Co&>D 7n. k'a NOTARY PUBAIC eu ry ChN !Y, |
| | * l ,fY055Ej nr s . . |
| | .] ! NOTARY \ |
| | ! COU#tsSION i 'f, g ft i y, EXPtfES ! N j,[ |
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| | Attachment 1 Rev1;ed Technical Specifications for NUREG-0737 (Generic Letter 83-36) |
| | ' Revised Pages: 1, iv, 49, 65, 66, 67a 67b, 80, 82a, 87a, 227 Nebraska Public Power District requests a revision to the Technical |
| | ' Specifications to incorporate the changes due to NUREG-0737 requested under Generic Letter 83-36. A discussion of each individual item covered under 83-36 is included as follows: |
| | : 1. Reactor Coolant System Vents (II.B.1,) |
| | As the NRC. stated in Generic Letter 83-36, no changes in Technical |
| | . Specifications are required for Boiling Water Reactors (BWR's) that do not have isolation condensers. Accordingly, no changes will be submitted |
| | -for this item. |
| | : 2. Postaccident Sampling (II.B.3) |
| | L Page 227 of the Technical Specifications was revised to establish an administrative' program which will implement and maintain postaccident sampling capability. |
| | : 3. Noble Gas Effluent Monitor (II.F.1.1) |
| | Page 49 of the Technical Specifications .has been revised and new pages 67a, 67b, and 82a - have been added. These pages define the instrumentation and calibration requirements for the noble gas effluent monitors and also actions required when these operational limitations are not met. |
| | : 4. Sampling and Analysis of Plant Effluents (II.F.1.2) ; , |
| | This item was implemented on revised page 227 of the Technical ' |
| | Specifications consistent with that shown on Item 2 above. |
| | : 5. Containment High-Range Monitor (II.F.1.3) , |
| | This item was implemented in the same manner as was Item 3 above. |
| | : 6. Containment Pressure Monitor (II.T.1.4) |
| | Pages 65, 66, and 80 are revised. These pages define the instrumentation and calibration requirements for the containment pressure monitor and also actions required when these operational limitations are not met. |
| | : 7. Containment Water Level Monitor (II.F.1.5) |
| | This item was implemented in the same manner as was Item 6 above. |
| | i f |
| | = |
| | A |
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| | c' |
| | : 8. Cencainment Hydrogen Monitor (II.F.1.6) |
| | In a letter from T. J. Dente to D. G. Eisenhut dated August 12, 1982, |
| | " Interim Requirements Related to Hydrogen Control", the BWR Owners Group submitted a technical evaluation which determined that the installation of hydrogen recombiner capability is not necessary for combustible gas control at Cooper Nuclear Station. This is due to the fact that the inerted containment design is adequate for control of combustible gases without a need for recombiners. SECY 83-292 dated July 19, 1983, was written in support of this position. Concerning the Containment Hydrogen Monitor (II.F.1.6), the BWR Owners Group submitted comments in a letter from T. J. Dente to D. G. Eisenhut dated May 6,1983, in which Mr. Dente stated in Comment 9 "There is no need to monitor containment hydrogen levels during Power Operation or Startup Modes because combustible gas control is not based on control of hydrogen." Additional requirements have been proposed for hydrogen monitoring by Regulatory Guide 1.97. |
| | Because of this fact, and in accordance with the Owners Group position (i.e., no need to monitor containment hydrogen levels), the District intends to defer implementation of this Technical Specification until the requirements of Regulatory Guide 1.97 are addressed. |
| | : 9. Control Room Habitability Requirements (II.D.3.4) |
| | In a letter from D. B. Vassallo to J. M. Pflant dated February 24, 1982, the NRC transmitted an SER which found acceptable NPPD's response to Item III.D.3.4. |
| | The District's response was made in a letter from J. M. ,Pilant to D. G. Eisenhut dated December 30, 1980. In this communication we stated that no modification wculd be necessary to meet the intent of III.D.3.4. |
| | In reviewing the District's CNS Technical Specifications against those contained in Generic Letter 83-36, the District feels that the present Technical Specifications meet the intent of the STS contained in 83-36. |
| | t . |
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| | ' EVALUATION OF TECHNICAL SPECIFICATIONS WITH RESPECT TO 10CFR50.92 The ' enclosed Technical Specification change is judged to involve no significant hazards based upon the following: |
| | 1.. 'Does the_ proposed-license amendment lavolve a significant increase in the probability or consequences of an accident previously evaluated? |
| | Evaluation Because the proposed change imposes new limitations, and also brings the Technical Specifications into agreement w'.th the GE Standard Technical |
| | ' Specifications, it does not involve a significant increase in - the |
| | * probability or consequences of an accident previously evaluated. |
| | : 2. Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previously evaluated? |
| | Evaluation |
| | .., Because this proposed change defines Technical Specification requirements concerning NUREG-0737 and is in conformance with the GE Standard Technical Specifications, it does not create the possibility for a new or different accident from any accident previously evaluated. |
| | -3. Does the proposed amendment involve a significant reduction in a. margin of safety? . |
| | Evaluation Because this proposed change adds new limitations concerning NUREG-0737 imposed changes and is in agreement with GE Standard Technical Specifications, it does not involve a significant reduction in a margin l ofi safety. , |
| | Additional basis for. proposed no significant hazards consideration determination: |
| | The Commission has provided guidance concerning the application of the standards fer ' determining whether a significant hazards consideration exists by providing examples (48FR14870). The examples include: "(11) A |
| | . change that constitutes an additional limitation, restriction, or control not presently' included in the Technical Specifications. . ." |
| | The proposed change which adds new limitations for components added under NUREG-0737 is clearly encompassed by Example (ii).}} |
Application for Amend to License DPR-16,changing Tech Specs Re Fire Detection Instruments to Comply w/NUREG-0737 (Generic Ltr 83-36),Items II.B.1,II.B.3,II.F.1 & II.D.3.4ML20081B424 |
Person / Time |
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Site: |
Cooper |
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Issue date: |
02/29/1984 |
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From: |
Kunck L, Kuncl L NEBRASKA PUBLIC POWER DISTRICT |
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To: |
Vassallo D Office of Nuclear Reactor Regulation |
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Shared Package |
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ML20081B427 |
List: |
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References |
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RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.3, TASK-2.D.3, TASK-2.F.1, TASK-TM GL-83-36, NLS-8400076, NUDOCS 8403090100 |
Download: ML20081B424 (6) |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
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 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 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 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
[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
[Table view] |
Text
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,i GENERAL 0FFICE
.. Nebraska Public Power District "S 8
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NLS8400076 February 29, 1984 Office of Nuclear Reactor Regulation Operating Reactor Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention : Mr. D. B. Vassallo, Chief -
Dear Mr. Vassallo:
Subject:
Proposed Change No.11 to Technical Specifications Cooper Nuclear Station: 0737 NRC Docket No. 50-298, DPR-46 In accordance with the applicable provisions specified in 10CFR50, Nebraska Public Power District requests that the Technical Specifications for Cooper Nuclear Station (CNS) be revised to incorporate the miscellaneous changes listed below:
Attachment Subject 1
NUREG-0737 (Generic Letter 83-36) 2 Fire Detection Instruments 3 Editorial Change A discussion and the applicable revised Technical Specification pages are contained in each attachment. Each modification to the Technical Specifications within this proposed change has been Q-evaluated with respect to the requirements of 10CFR50.92. The results of individual evaluations are included within each attachment.
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Ox By copy of this letter and attachments the appropriate State of Nebraska Official is being notified in accordance with 10CFR50.91(b) .
oc g These changes have been reviewed by the necessary Safety e$ Review Committees and payment for a Class II amendment in the man.
amount of $1,200 is submitted, b
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l P ge 2 F:brutry 29, 1984 Should you have any questions or require additional information, please contact me.
In addition to . three signed originals, 40 copies are also submitted for your use.
Sincerely, L, G. Kuncl
' Assistant General Manager - Nuclear LGK/gmc:emz1/10 Attachments
- cc: II. E. Simmons Department of Ilecith State of Nebraska e-
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2 Pcg3 3 Ftbrutry 29, 1984 STATE OF NEBRASKA)
)ss PLATTE COUNTY )
L. _G. Kuncl, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to submit this request on behalf of Nebraska Public Pcwer District; and that the statements contained herein are true to the best of his knowledge and belief.
1 W
U G. Kuncl Subscribed in my presence and sworn to before me thisfpd day of % CPinnnu , 1984.
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Attachment 1 Rev1;ed Technical Specifications for NUREG-0737 (Generic Letter 83-36)
' Revised Pages: 1, iv, 49, 65, 66, 67a 67b, 80, 82a, 87a, 227 Nebraska Public Power District requests a revision to the Technical
' Specifications to incorporate the changes due to NUREG-0737 requested under Generic Letter 83-36. A discussion of each individual item covered under 83-36 is included as follows:
- 1. Reactor Coolant System Vents (II.B.1,)
As the NRC. stated in Generic Letter 83-36, no changes in Technical
. Specifications are required for Boiling Water Reactors (BWR's) that do not have isolation condensers. Accordingly, no changes will be submitted
-for this item.
- 2. Postaccident Sampling (II.B.3)
L Page 227 of the Technical Specifications was revised to establish an administrative' program which will implement and maintain postaccident sampling capability.
- 3. Noble Gas Effluent Monitor (II.F.1.1)
Page 49 of the Technical Specifications .has been revised and new pages 67a, 67b, and 82a - have been added. These pages define the instrumentation and calibration requirements for the noble gas effluent monitors and also actions required when these operational limitations are not met.
- 4. Sampling and Analysis of Plant Effluents (II.F.1.2) ; ,
This item was implemented on revised page 227 of the Technical '
Specifications consistent with that shown on Item 2 above.
- 5. Containment High-Range Monitor (II.F.1.3) ,
This item was implemented in the same manner as was Item 3 above.
- 6. Containment Pressure Monitor (II.T.1.4)
Pages 65, 66, and 80 are revised. These pages define the instrumentation and calibration requirements for the containment pressure monitor and also actions required when these operational limitations are not met.
- 7. Containment Water Level Monitor (II.F.1.5)
This item was implemented in the same manner as was Item 6 above.
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- 8. Cencainment Hydrogen Monitor (II.F.1.6)
In a letter from T. J. Dente to D. G. Eisenhut dated August 12, 1982,
" Interim Requirements Related to Hydrogen Control", the BWR Owners Group submitted a technical evaluation which determined that the installation of hydrogen recombiner capability is not necessary for combustible gas control at Cooper Nuclear Station. This is due to the fact that the inerted containment design is adequate for control of combustible gases without a need for recombiners. SECY 83-292 dated July 19, 1983, was written in support of this position. Concerning the Containment Hydrogen Monitor (II.F.1.6), the BWR Owners Group submitted comments in a letter from T. J. Dente to D. G. Eisenhut dated May 6,1983, in which Mr. Dente stated in Comment 9 "There is no need to monitor containment hydrogen levels during Power Operation or Startup Modes because combustible gas control is not based on control of hydrogen." Additional requirements have been proposed for hydrogen monitoring by Regulatory Guide 1.97.
Because of this fact, and in accordance with the Owners Group position (i.e., no need to monitor containment hydrogen levels), the District intends to defer implementation of this Technical Specification until the requirements of Regulatory Guide 1.97 are addressed.
- 9. Control Room Habitability Requirements (II.D.3.4)
In a letter from D. B. Vassallo to J. M. Pflant dated February 24, 1982, the NRC transmitted an SER which found acceptable NPPD's response to Item III.D.3.4.
The District's response was made in a letter from J. M. ,Pilant to D. G. Eisenhut dated December 30, 1980. In this communication we stated that no modification wculd be necessary to meet the intent of III.D.3.4.
In reviewing the District's CNS Technical Specifications against those contained in Generic Letter 83-36, the District feels that the present Technical Specifications meet the intent of the STS contained in 83-36.
t .
' EVALUATION OF TECHNICAL SPECIFICATIONS WITH RESPECT TO 10CFR50.92 The ' enclosed Technical Specification change is judged to involve no significant hazards based upon the following:
1.. 'Does the_ proposed-license amendment lavolve a significant increase in the probability or consequences of an accident previously evaluated?
Evaluation Because the proposed change imposes new limitations, and also brings the Technical Specifications into agreement w'.th the GE Standard Technical
' Specifications, it does not involve a significant increase in - the
- probability or consequences of an accident previously evaluated.
- 2. Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Evaluation
.., Because this proposed change defines Technical Specification requirements concerning NUREG-0737 and is in conformance with the GE Standard Technical Specifications, it does not create the possibility for a new or different accident from any accident previously evaluated.
-3. Does the proposed amendment involve a significant reduction in a. margin of safety? .
Evaluation Because this proposed change adds new limitations concerning NUREG-0737 imposed changes and is in agreement with GE Standard Technical Specifications, it does not involve a significant reduction in a margin l ofi safety. ,
Additional basis for. proposed no significant hazards consideration determination:
The Commission has provided guidance concerning the application of the standards fer ' determining whether a significant hazards consideration exists by providing examples (48FR14870). The examples include: "(11) A
. change that constitutes an additional limitation, restriction, or control not presently' included in the Technical Specifications. . ."
The proposed change which adds new limitations for components added under NUREG-0737 is clearly encompassed by Example (ii).