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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20217B5201999-10-0606 October 1999 Amend 193 to License DPR-40,revising TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance Requirements for RCS Flow Rate ML20211L3441999-09-0202 September 1999 Corrected Tech Spec Page 2-50 to Amend 192 to License DPR-40.Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) ML20210G2131999-07-27027 July 1999 Amend 192 to License DPR-40,revising TS Sections 2.2 & 2.10. 2 to Relocate 3 cycle-specific Parameters to Core Operating Limits Repts ML20210D9861999-07-22022 July 1999 Amend 191 to License DPR-40,authorizing Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation Actuation Signal Closure Signal to Reactor Coolant Sys ML20205Q5791999-04-15015 April 1999 Amend 190 to License DPR-40,revising TS 5.2.f & TS 5.11.2 to Change Title of Shift Supervisor to Shift Manager ML20207E9761999-03-0303 March 1999 Errata to Amend 188 to License DPR-40,correcting Incorrect Page Number,Missing Parenthesis & Misspelled Word ML20198S3731998-12-31031 December 1998 Amend 189 to License DPR-40,revising TS 2.1.6 to Restrict Number of Inoperable Main Steam Safety Valves When Reactor Critical & Revising Associated Basis ML20198S4611998-12-31031 December 1998 Amend 188 to License DPR-40,revising TS 2.12, Control Room Sys, to Delete Limiting Condition for Operation & Surveillance for Control Room Temp ML20154M4841998-10-19019 October 1998 Amend 186 to License DPR-40,revising TS 2.3 to Increase Allowed Outage Times for SIT ML20154N2361998-10-19019 October 1998 Amend 187 to License DPR-40,revising TS 3.9 to Clarify Required Flow Paths for Auxiliary Feedwater Sys & Deleting Surveillance Requirement for Specific Auxiliary Feedwater Pump Discharge Pressure ML20217L0521998-03-23023 March 1998 Amend 185 to License DPR-40,revising TS to Implement 10CFR50,App J,Option B & to Allow Performance Based Changes in Conducting ILRT & Local Leak Rate Testing Types B & C & SER ML20203M4121998-02-0303 February 1998 Amend 184 to License DPR-40,revising TS to Reflect Administrative Changes ML20203A4131998-01-26026 January 1998 Amend 183 to License DPR-40,revises TS to Delete Requirements for Toxic Gas Monitoring Sys Contained in TS 2.22 & TS 3.1,table 3-3,item 29,for Toxic Chemicals Except Ammonia ML20203E0171997-12-10010 December 1997 Corrected TS Pages 3-7 & 3-12 to Amend 182 to License DPR-40,adding Words That Were Omitted from TS Pages ML20199L0441997-11-24024 November 1997 Amend 182 to License DPR-40,revising TSs to Correct & Clarify Several Surveillance Test Requirements for Reactor Protection Sys & Other Plant Instrumentation & Control Sys ML20137L6121997-03-27027 March 1997 Amend 181 to License DPR-40,revising Section 5.2 of TS to Relocate Controls for Working Hours to Updated Safety Analysis Rept ML20134N7651997-02-13013 February 1997 Amend 180 to License DPR-40,revises TS to Add Limiting Condition for Operation & Surveillance Test for Safety Related Inverters & Deletes Nonsafety Related Instrument Buses ML20133M6641997-01-15015 January 1997 Errata to Amend 179 to License DPR-40,revising Page 2-22 Which Incorrectly Stated Amount of Active TSP That Shall Be Contained in TSP Baskets ML20133C2741996-12-30030 December 1996 Amend 179 to License DPR-40,revising TSs to Increase Amount of TSP Dodecahydrate Located in Containment Sump Storage Baskets ML20129H3261996-10-25025 October 1996 Amend 178 to License DPR-40,changing Section 4.3.2 of TS to Allow Use of Zircaloy or ZIRLO Fuel Cladding & to Use Depleted U as Reactor Fuel Matl ML20128F6251996-10-0202 October 1996 Amend 177 to License DPR-40,modifying Paragraph 2.B.(2) W/Ref to 10CFR40 Allowing Use of Source Matl,In Form of Depleted or Natural U,As Reactor Fuel ML20129G2911996-09-27027 September 1996 Amend 176 to License DPR-40,revising Sections 2.18,3.14, 3.3 & 5.10 of TS to Relocate Snubber Operability Requirements to USAR ML20059J1671994-01-14014 January 1994 Amend 160 to License DPR-40,changes TS to Implement GLs 86-10 & 88-12 ML20059J2441994-01-14014 January 1994 Amend 159 to License DPR-40,revises TS to Change Setpoint Limit for degraded-voltage Protection Sys Referred to as offsite-power Low Signal ML20058G9301993-12-0303 December 1993 Amend 158 to License DPR-40,changing Operating License Expiration Date to 130809,or 40 Years After Date of Issuance of Operating License Rather than 40 Years from Date of Issuance of CP ML20058F5911993-11-22022 November 1993 Amend 157 to License DPR-40,revising TS to Implement Administrative Changes ML20059G6491993-10-29029 October 1993 Amend 156 to License DPR-40,revising TS 2.10.4 to Establish Limit for cold-leg Temp to Maintain Departure from Nucleate Boiling Ratio Margin During Power Operation Above 15% of Rated Power ML20057F7971993-10-13013 October 1993 Corrected Page 3-20d to Amend 155 to License DPR-40,deleting Word Region I from Item 15 ML20056E5401993-08-12012 August 1993 Amend 155 to License DPR-40,changing TS to Increase Fuel Storage Capacity in Spent Fuel Pool to 1083 Fuel Assemblies ML20056E5361993-08-10010 August 1993 Amend 154 to License DPR-40,changing TS 3.2 (Table 3-5) to Require Charcoal Filter Volumetric Flow Rate of Between 4500 & 12000 Cubic Feet Per Minute ML20056D6711993-07-26026 July 1993 Amend 153 to License DPR-40,increasing Max Bypass Pressure for SG low-pressure Signal Trip Setting from 550 Psia to 600 Psia ML20056C3671993-05-12012 May 1993 Corrected TS Page 2-35 to Amend 150 to License DPR-40, Replacing Word and W/Word or in Spec 2.7.2.m ML20128B8171993-01-26026 January 1993 Amend 149 to License DPR-40,makes Changes to TSs 5.5 & 5.8 to Reflect Implementation of Qualified Reviewer Program for Review & Approval of New Procedures & Changes at Plant ML20062G6611990-11-19019 November 1990 Amend 134 to License DPR-40,addressing Two Administrative Changes ML20062B6101990-10-12012 October 1990 Amend 133 to License DPR-40,modified Tech Specs to Increase Refueling Boron Concentration to 1900 Ppm & Revises Storage Requirements of Spent Fuel Pool Region 2 ML20055G0191990-07-0606 July 1990 Amend 132 to License DPR-40,revising Tech Spec Pages 5-1, 5-5,5-8 & 5-19a to Incorporate Title Changes as Result of Reorganization & Partial Relocation of Emergency Planning Dept ML20248C0791989-06-0202 June 1989 Amend 122 to License DPR-40,extending Surveillance Interval by 25%,defining Regular Surveillance Intervals & Eliminating Need to Perform Surveillance on Inoperable Equipment ML20245L2831989-04-26026 April 1989 Amend 121 to License DPR-40,modifying Tech Specs to Change Containment Spray Sys Surveillance Testing Requirements to Provide Quantitative Value for Min Acceptance Criteria & Reducing Max Power Level on Figure 2-7 ML20245D2261989-04-14014 April 1989 Amend 120 to License DPR-40,changing Min Operating Requirements for Raw Water Pumps to Allow Operation W/One Inoperable Raw Water Pump When River Water Temp Below 60 F ML20235K8751989-02-14014 February 1989 Amend 119 to License DPR-40,deleting Paragraph 3.D & Modifying Tech Specs to Change Safety Injection & Refueling Water Tank Min Temp,Changing Title of Senior Vice President & Correcting Errors in Refs & Mailing Address ML20205S2381988-11-0303 November 1988 Amend 116 to License DPR-40,modifying Tech Specs to Provide Addition of Table of Contents for Tables & Figures & Correct Error to Location Ref in Section 2.19 ML20150A9921988-07-0101 July 1988 Amend 115 to License DPR-40,revising Section 5 of Tech Specs to Incorporate Recent Organizational & Job Title Changes & to Remove Onsite & Offsite Organizational Charts ML20150B2461988-06-28028 June 1988 Amend 114 to License DPR-40 Updating RCS pressure-temp Limits for Heatup & Cooldown to Reflect New Fluence Prediction Developed & More Limiting Chemistry Factor Associated W/Weld 3-410 ML20154A6691988-05-0404 May 1988 Amend 113 to License DPR-40,allowing Licensee to Use Annual Average (Rather than real-time) Meteorological Dispersion Factors to Calculate Doses & Corrects & Clarifies Some Parts of Tech Specs 2.9.1 & 5.9.4 ML20151S0471988-04-19019 April 1988 Amend 112 to License DPR-40,revises Tech Specs to Permit Extension for Next Due Date from 880430 to Refueling Outage Scheduled for Sept 1988 for Performing Insp of Diesel Generator 1 ML20235G8881987-09-24024 September 1987 Amend 111 to License DPR-40,incorporating Revised Surveillance Requirements for Diesel Generators Into Tech Specs,Per Generic Ltr 84-15, Proposed Staff Actions to Improve & Maintain Diesel Generator Reliability ML20215M1491987-05-0404 May 1987 Amend 109 to License DPR-40,modifying Tech Specs to Reflect Changes Necessary to Support Cycle 11 Operation ML20210C3921987-04-28028 April 1987 Amend 108 to License DPR-40,incorporating Revised Limiting Conditions for Operation & Surveillance Requirements for Steam Generator Isolation Signal ML20206B4651987-03-30030 March 1987 Amend 107 to License DPR-40,revising Tech Specs to Delete Hydrogen Fluoride Detectors from Tables 2-11 & 3-3 ML20206B2251987-03-26026 March 1987 Amend 106 to License DPR-40,changing Tech Specs to Modify Surveillance Requirements for Hydrogen & Oxygen Monitoring Sys for Waste Gas Decay Tanks to Clarify That Daily Channel Check Required for Sys When in Svc 1999-09-02
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217B5201999-10-0606 October 1999 Amend 193 to License DPR-40,revising TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance Requirements for RCS Flow Rate ML20211L3441999-09-0202 September 1999 Corrected Tech Spec Page 2-50 to Amend 192 to License DPR-40.Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) ML20210G2131999-07-27027 July 1999 Amend 192 to License DPR-40,revising TS Sections 2.2 & 2.10. 2 to Relocate 3 cycle-specific Parameters to Core Operating Limits Repts ML20210D9861999-07-22022 July 1999 Amend 191 to License DPR-40,authorizing Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation Actuation Signal Closure Signal to Reactor Coolant Sys ML20195B4371999-05-26026 May 1999 Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure- Temp Limits Rept ML20205Q5791999-04-15015 April 1999 Amend 190 to License DPR-40,revising TS 5.2.f & TS 5.11.2 to Change Title of Shift Supervisor to Shift Manager ML20205J7631999-03-31031 March 1999 Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate ML20207E9761999-03-0303 March 1999 Errata to Amend 188 to License DPR-40,correcting Incorrect Page Number,Missing Parenthesis & Misspelled Word ML20203A0991999-01-29029 January 1999 Application for Amend to License DPR-40,relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20198S4611998-12-31031 December 1998 Amend 188 to License DPR-40,revising TS 2.12, Control Room Sys, to Delete Limiting Condition for Operation & Surveillance for Control Room Temp ML20198S3731998-12-31031 December 1998 Amend 189 to License DPR-40,revising TS 2.1.6 to Restrict Number of Inoperable Main Steam Safety Valves When Reactor Critical & Revising Associated Basis ML20195K1771998-11-17017 November 1998 Revised Application for Amend to License DPR-40, Incorporating Addl Restrictions on Operation of MSSVs ML20154N2361998-10-19019 October 1998 Amend 187 to License DPR-40,revising TS 3.9 to Clarify Required Flow Paths for Auxiliary Feedwater Sys & Deleting Surveillance Requirement for Specific Auxiliary Feedwater Pump Discharge Pressure ML20154M4841998-10-19019 October 1998 Amend 186 to License DPR-40,revising TS 2.3 to Increase Allowed Outage Times for SIT ML20154A0661998-09-28028 September 1998 Application for Amend to License DPR-40,allowing Installation of Capability for Override of Containment Isolation Actuation Signal Closure Signal to Containment Isolation Valves for RCS Letdown Flow ML20217L0521998-03-23023 March 1998 Amend 185 to License DPR-40,revising TS to Implement 10CFR50,App J,Option B & to Allow Performance Based Changes in Conducting ILRT & Local Leak Rate Testing Types B & C & SER ML20217B8481998-03-18018 March 1998 Application for Amend to License DPR-40,changing TS 5.2 & 5.11.2 to Change Title of Shift Supervisor to Shift Manager ML20217B8181998-03-18018 March 1998 Application for Amend to License DPR-40,requesting Tech Specs Set Forth in App a to License Amended to Clearly Address Regulatory Requirements for Alternate Shutdown Panel & Auxiliary Feedwater Panel ML20217P1981998-03-0303 March 1998 Application for Amend to License DPR-40,revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20203M4121998-02-0303 February 1998 Amend 184 to License DPR-40,revising TS to Reflect Administrative Changes ML20199L7221998-01-30030 January 1998 Application for Amend to License DPR-40,requesting Deletion of Section 3.E, License Term from License ML20199L8911998-01-30030 January 1998 Application for Amend to License DPR-40,relocating pressure- Temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept (PTLR) ML20203A4131998-01-26026 January 1998 Amend 183 to License DPR-40,revises TS to Delete Requirements for Toxic Gas Monitoring Sys Contained in TS 2.22 & TS 3.1,table 3-3,item 29,for Toxic Chemicals Except Ammonia ML20203G4101997-12-11011 December 1997 Application for Amend to License DPR-40,adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20203E0171997-12-10010 December 1997 Corrected TS Pages 3-7 & 3-12 to Amend 182 to License DPR-40,adding Words That Were Omitted from TS Pages ML20199L0441997-11-24024 November 1997 Amend 182 to License DPR-40,revising TSs to Correct & Clarify Several Surveillance Test Requirements for Reactor Protection Sys & Other Plant Instrumentation & Control Sys ML20199K1221997-11-21021 November 1997 Application for Amend to License DPR-40,revising Tech Specs 5.19 by Incorporating Editoral Changes & Two Exceptions to NEI-94-01,Rev 0, Industry Guideline for Implementing Performance-Based Option of 10CFR50,App J ML20217G4541997-10-0303 October 1997 Application for Amend to License DPR-40,revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0781997-07-25025 July 1997 Application for Amend to License DPR-40,allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance & Implementing Option B of 10CFR50,App J ML20137Y1591997-04-17017 April 1997 Application for Amend to License DPR-40,requesting Rev to Administrative Controls Consistent w/NUREG-1432 Standard TS for Combustion Engineering Plants.Tech Specs Encl ML20137L6121997-03-27027 March 1997 Amend 181 to License DPR-40,revising Section 5.2 of TS to Relocate Controls for Working Hours to Updated Safety Analysis Rept LIC-97-0049, Application for Amend to License DPR-40,incorporating Addl Restrictions on Operation of MSSVs1997-03-26026 March 1997 Application for Amend to License DPR-40,incorporating Addl Restrictions on Operation of MSSVs ML20138L4341997-02-20020 February 1997 Application for Amend to License DPR-40,requesting to Update TS Re Rev to Position Titles & Relocation of Controls for Personnel Working Hours ML20134N7651997-02-13013 February 1997 Amend 180 to License DPR-40,revises TS to Add Limiting Condition for Operation & Surveillance Test for Safety Related Inverters & Deletes Nonsafety Related Instrument Buses ML20133M6641997-01-15015 January 1997 Errata to Amend 179 to License DPR-40,revising Page 2-22 Which Incorrectly Stated Amount of Active TSP That Shall Be Contained in TSP Baskets ML20133C2741996-12-30030 December 1996 Amend 179 to License DPR-40,revising TSs to Increase Amount of TSP Dodecahydrate Located in Containment Sump Storage Baskets ML20134N8491996-11-20020 November 1996 Application for Amend to License DPR-40,requesting Administrative Revisions to Paragraph 3,Table of Contents, Tech Spec 2.15 & Section 5 of Appendix a ML20129H3261996-10-25025 October 1996 Amend 178 to License DPR-40,changing Section 4.3.2 of TS to Allow Use of Zircaloy or ZIRLO Fuel Cladding & to Use Depleted U as Reactor Fuel Matl ML20129E4921996-10-24024 October 1996 Application for Amend to License DPR-40,TS 4.3.2, Reactor Core & Control, Allowing Use of Either Zircaloy or ZIRLO Cladding ML20129C2491996-10-22022 October 1996 Application for Amend to License DPR-40,revising TS 4.3.2, Reactor Core & Control & Adding Ref to WCAP-12610 in TS 5.9.5b ML20128F6251996-10-0202 October 1996 Amend 177 to License DPR-40,modifying Paragraph 2.B.(2) W/Ref to 10CFR40 Allowing Use of Source Matl,In Form of Depleted or Natural U,As Reactor Fuel ML20129G2911996-09-27027 September 1996 Amend 176 to License DPR-40,revising Sections 2.18,3.14, 3.3 & 5.10 of TS to Relocate Snubber Operability Requirements to USAR ML20117B8771996-08-23023 August 1996 Application for Amend to OL Revising Paragraph 2.B of License to Allow Use of Source Matl as Reactor Fuel ML20115F9971996-07-15015 July 1996 Application for Amend to License DPR-40,revising Description of Reactor Core & Control & Adding Westinghouse Topical Rept List of Analytical Methods,Used to Determine Core Operating Limits ML20112D3151996-05-31031 May 1996 Application for Amend to License DPR-40,adding LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6951996-05-20020 May 1996 Application for Amend to License DPR-40,clarifying Surveillance Test Requirements in TS 3,1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5871996-05-17017 May 1996 Application for Amend to License DPR-40,relocating Operability Requirements for Shock Suppressors (Snubbers) from TS to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3031996-02-0101 February 1996 Application for Amend to License DPR-40,allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool ML20100C0161996-01-22022 January 1996 Application for Amend to License DPR-40 Revising TS Re Requirement for Placing Sirw Tank low-level Channels in Bypass Rather than Trip ML20094N8571995-11-16016 November 1995 Application for Amend to License DPR-40,adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses 1999-09-02
[Table view] |
Text
.
c#* *%
p t UNITED STATES
2 NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. soseMoot
. . . . . ,o OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-Z H FORT CALHOUN STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.180 License No. DPR-40
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
l A. The application for amendment by the Omaha Public Power District i (the licensee) dated November 16, 1995, as supplemented by letter i
- dated August 8, 1996, complies with the standards and requirements i 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 Comission; C. There is reasonable assurance: (1) 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 Comission's regulations; D. The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied. '
l 1
9702240433 970213 PDR ADOCK 05000285 P PDR i
i
)
4
- 2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.
. DPR-40 is hereby amended to read as follows:
1 B. Technical Soecificatiqni The Technical Specifications contained in Appendix A, as revised through Amendment No. 180, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
1
- 3. The license amendment is effective as of its date of issuance to be l l implemented within 60 days from the date of issuance.
i 1
FOR THE NUCLEAR REGULATORY COMMISSION
. Raynard Wharton, Project Manager Project Directorate IV-2 l Division of Reactor Projects - III/IV I Office of Nuclear Reactor Regulation l I
Attachment:
Changes to the Technical i Specifications 1 Date of Issuance: February 13, 1997 i
d
i j ATIACHMENT TO LICENSE AMENDMENT NO. 180 FACILITY OPERATING LICENSE NO, DPR-40 ,
l DOCKET NO. 50-285 3
l d
i Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. ,
REMOVE INSERT 2-32 2-32 2-35 2-35 ,
2-36 2-36 2-36a 2-36a l 3-60 3-60 i
i
2.0 LIMITING CONDITIONS FOR OPERATION
- .. 2.7 Electrical Systems Anolicability a
j Appl:es to the availability of electrical power for the operation of plant components.
Obiective To define those conditions of electrical power availability necessary to provide for safe l reactor operation and the continuing availability of engineered safety features.
{ Specifications
] (1) Mmimum Requirements The reactor shall not be heated up or maintained at temperatures above 300'F unless the following electrical systems are operable:
- a. Unit auxiliary power transformers TIA-1 or -2 (4,160 V).
- b. House service transformers TIA-3 and 4 (4,160 V).
- c. 4,160 V engineered safety feature buses I A3 and 1 A4.
- d. 4,160 V/480 V Transformers TIB-3A, TIB-3B, TIB-3C, TIB-4A, TIB-4B, TIB-4C.
- e. 480 V distribution buses IB3A,1B3A-4A, IB4A, IB3B,1B3B-4B, IB4B, IB3C, IB3C4C,1B4C.
- f. MCC No. 3A1, 3B1, 3A2, 3C1, 3C2, 4 A1, 4A2, 4C1 and 4C2.
- g. 125 V d-c buses No.1 and 2 (Panels EE-8F and EE-8G).
- h. 125 V d-c distribution panels AI-41A and AI-41B.
- i. 120V a-c instrument buses A, B, C, and D (Panels AI 40-A, B, C and D).
- j. Inverters A, B, C, and D. l
- k. Station batteries No. I and 2 (EE 8A and EE-8B) including one battery charger on each 125V d-c bus No. I and 2 (EE-8F and EE-8G).
- 1. Two emergency diesel generators (DG-1 and DG 2).
- m. One diesel fuel storage system containing a minimum volume of 16,000 gallons of diesel fuel in FO-1, and an additional 8,000 gallons of diesel fuel in FO-10.
2-32 Amendment No. 117,162,180
2.0 LIMITING CONDITIONS FORDPERATIQN
.' 2.7 Electrical Systems (cantimad)
.. 1. Island buses IB3A-4A, IB3B 4B, and IB3C-4C may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided there are no inoperable required safeguards components which are raan=taar to components on the inoperable bus (es).
- m. Eicher one of the 125V d-c buses No. I or 2 (Panels EE-8F or EE-8G) may be inoperable for up to 8 houn.
- a. Either one of the 125V d<: distribution panels AI-41A or AI-41B may be
! inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
1
) o. One invener (A, B, C, or D) may be inoperable for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i provided the sancte* protective and engineered safeguards systems instnanent channels supplied by the remaining three inveners are all
. operable and the 120V a c instranent bus associated with the inoperable j invener is powered from ks bypass source.
j hait lhe electrical system equipment is arranged so that no single failure can inactivate enough engineered safeguards tojeopardize the plant safety. The 480 V safeguards are arranged on nine bus sections. The 4.16 kV safeguards are supplied from two buses.
The normal source of piriliary power with the plant at power for the safeguards buses is Aom the house service power transformers being fed from the 161 Kv Wit line with on-site emergency power from either one of two diesel generators and off-site
, standby power via the unit anviliary transformers.m The loss of the 161kV incoming line senders the house service transformers (TIA-3 and TIA4) inoperable in that the .
transfonners cannot supply power to the 4.16kV safeguards buses IA3 and 1A4. '
Inoperability of the house service transformer (s) or loss of the 161kV incoming line is not reponable pursuant to 10 CFR 50.72 crheria; however, the NRC will be promptly ,
notined of these events via the NRC Operations Center. t i
The two emergency diesel generators on site do not require outside power for start up or operation.
Upon loss of normal and standby power sources, the 4.16 Ky buses IA3 and iA4 are energized froen the diesel generators. Bus load shedding, transfer to the diesel generator and pickup of critical loads are carried out antamatically.m ,
L When the anbine generator is out of service for an extended period, the generator can be isolated by opening motor operated diacanaaet switch DS-T1 in the bus between the genssator and the main transfonner, aBowing the main transfonner a~.J the unit anviliary power aansfonners (TIA-1 and TI A-2) to be returned to service." The piriliary power transfonners are not considered inoperable during these normal plant startup/ shutdown sealignments.
2-35 Amendment No. ?5, e?, 5^, 52,180
___________._._._______._..._______._.__.._m _ _ _ _ _
- 2.0 LIMITING CONDITIONS FOR OPERATION i . 2.7 Electrical Systems (Contimmi)
] 'Ibe time allowed to repair an inoperable invener is based upon engineering judgement, i ,.
taking into consideration the time required to repair an invener and the additional risk l to which the unit is exposed because of the invener inoperability. In the event of j
invester failure, the load on the invener is automatiemlly transferred to its safety related l bypass source. The associated 120 V a-c instrument bus is considered OPERABLE when it is being p,U fnun its bypass source and during the shon time it takes to mammally or amamatically transfer between sources.
l
! Equipment served by 4.16 kV and 480 V auxiliary buses and MCC's is arranged so that I
loss of an entire 4.16 kV bus does not compromise safety of the plant during DBA '
! mndirians. For example, if 4.16 kV bus IA3 is lost, two raw water pumps, one low i
pressure safety insection pump, two high pressure safety insection pumps, one auxiliary
! feedwater pump, two component cooling water pumps, one enmainment spray pump and j two anntainment air fans are lost. ' Ibis leaves two raw water pumps, one low pressure j safety injection pump, one high pressure safety 'Me pump, one component cooling water pump, two ennrainment spray pumps and two cantainment air fans which is more f
than sufficient to control containment pressure below the design value during the DBA.
Each diesel generator has sufficient capacity to start and run at design load required by engineered safety features equipment. The safety features operated from one diesel generator can adequately cool the core for any loss of coolant accident and also maintain the enntainment pressure within the design value. The engine base tank capacity of 550 gallons on each diesel provides 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> running time (worst case loading) before transfer of fuel oil from the 18,000 gallon capacity emergency diesel generator fuel oil storage tank FO-1 is mandarary. Two fhel oil transfer pumps per diesel, with each being powered from the associated diesel, are available for transferring fuel oil from FO-1 to the day tanks. The minimum diesel fuel oil inventory available to the diesel generators from the emergency diesel generator fuel oil storage tank FO-1 is maintained to assure she operation of either: 1) one diesel generator at full rated design capacity for at least 3.6 dsys, or 2) one diesel generator at post accident load conditions for a minimum of 4.5 days.
A minimum of 8,000 gallons of diesel fuel oil is reserved in the auxiliary boiler fuel oil storage tank FO-10 for transfer to the emergency diesel generator fuel oil storage tank in the event of an emergency to extend the fbel supply for diesel generator operation to 7 days. Methods of transfer of the fuel oil fann this tank to FO-1 have been established and procedures have been developed so that the transfer can be made in a timely manner without adversely impacting diesel generator operation. Therefore, a minimum diesel fuel oil in _ny available to the diesel generators from the total on-site diesel fuel oil storage capacity is maintainad to assure the operation of one diesel generator at the seguired post accident loads for 7 days. The fhel inventory is allowed below the 7 day supply, but above a 6 day supply, for a period of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. This restriction allows suf5cient time fbr obtaining the sacriisite :=pt- volume and performing the analyses required prior to addition of fhel oil to the tank. A period of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is considered sufficient to complete restoration of the required level prior to initiating a 2-36 A==iment No. 444,M2,180
2.0 LIMITING CONDITIONS FOR OPERATION 2.7 Electrical Systems (Continued) 1 plant shutdown as required by Specification 2.7(2). This period is acceptable based on the remaining capacity (more than 6 days), the fact that procedures are in place to obtain replenishment, and the low probability of an event durmg this brief period.
Additional supplies of diesel fuel oil are available in the Omaha area and from nearby terminals. Ample facilities exist to assure deliveries to the site within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
One battery charger on each battery shall be operating so that the batteries will always be at full charge; this ensures that adequate <!-c power will be available for all emergency uses. Each battery has one battery charger permanently connected with a third charger capable of being cs=M to either battery bus. 'the chargers are each rated for 400 amperes at 130 volts. Following a DBA the batteries and the chargers will handle all required loads. Each of the reactor protective channels instrumentation channels is supplied by one of the a-c instrument buses. The removal of one of the a-c instrument buses is permitted as the 2-of-4 logic may be manually changed to a 2-of-3 logic without compromising safety.
The engineered safeguards instrument channels use a-c instrument buses (one redundant bus for each channel) and d-c buses (one redundant bus for each logic circuit). The removal of one of the a-c instrument buses is permitted as the two of four logic automatically becomes a two of three logic.
Required engineered safeguards components, as described in Specirmation 2.7(2), refers to components required to be operable by other Limiting Conditions for Operation within these Technical Specifications. If no other ILO requires a particular ESF component to be operable, then its redundant component is also not required to be operable due to this specification. As an example, Specification 2.3 requires that safety injection pumps be operable prior to the reactor being made critical, and Specification 2.7 applies when ,
the RCS is above 300'F. If the RCS is above 300*F but the reactor is not critical, then l l
no safety injection pumps are required to be operable.
References (1) USAR, Section 8.3.1.2 (2) USAR, Section 8.4.1 (3) USAR, Section 8.2.2 2-36a Amendment No.1C,:52,180
)' 3.0 MJRVEILLANCE REOUIREMENTS l
3.7 F=-,way Power System Perindic Tests (Continued) l l
} .. I
- d. During refueling shutdowns the correct function of all D.C. emergency i transfer switches shall be demonstrated by manual transfer of normal D.C.
- supply breakers at the 125 volt D.C. distribution panels.
)
i
-(3) Emergency lighting
- 'Ibe correct functioning of the emergency lighting system required for plant safe
- shutdown shall be verifwd at least once each year.
(4) 13.8 Ky Transmission line l
< 'Ibe 13.8 Ky transmission line will 1:e energized and loaded to minimum shutdown requirements at each refueling outage following installation.
(5) Inveners A. B. C. and D 1
. 'Ibe conect inverter output (voltage, frequency, and alignment to required
- 120 V a-c instrument buses) shall be verifwd weekly.
Baili f
- The emergency power system provides power requirements for the engineered safety features in the event of a DBA. Each of the two diesel generators is capable of i supplying minimum required safety feature equipment from iadapadant buses. This d redundancy is a factor in establishing testing intervals. The monthly tests specified will i demonstrate operability and load capacity of each diesel generator. These tests are
- conducted to meet the objectives of NRC Generic letter 84-15 regarding the issue of reductions in cold fast starts. For this reason, the test verifying a 10 second start will j be conducted from ambient conditions once per 184 days for each diesel. Other monthly tests will allow for mamifacturer's recommended warm-up to reduce the mechanical stress and wear on the diesel engines. The fuel supply and various controls are continuously monitored and alarmed for off-normal conditions. Automatic starting on loss of off-site power and automatic load shedding, diesel connection, and loading will be verified on a refueling frequency. At the same intervals, capability will be verified for manual emergency control of these functions from the diesel and switch-gear rooms.
Considering system redundancy, the specifud testing intervals for the station batteries should be adequate to detect and correct any malfunction before it can result in system malfunction. Batteries will deteriorate with time, but precipitous failure is extremely unlikely. The surveillance specified is that which has been demonstrated over the years to provide an indication of a cell becoming unserviceable long before it fails.
References (1) USAR, Section 7.3.4.2 (2) USAR, Section 8.4.1 (3) USAR, Section 8.3.4 (4) USAR, Section 8.4.2 3-60 Amendment No. 24,111,157,180
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