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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
f> l
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,/ %, UNITED STATES g g NUCLEAR REGULATORY COMMISSION
- 7. j WASHINGTON, D. C. 20655
~s. ... ./
OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 103 License No. DPR-40
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Omaha Public Power District (the licensee) dated January 8, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the
, Commission; h
C. There is reasonable assurance (i) that the activities authorized l 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 the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l 8703230189 870309 PDR ADOCK 05000285 P PDR i
V
~
2-
- 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.
OPR-40 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.103, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This Itcense amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION guadw Ashok C. Thadani, Director PWR P oject Directorate #8 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: March 9,1987
e--
3 ATTACHMENT TO LICENSE AMENDMENT NO.103 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amend.ent number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 2 2 2-18 2-18 2-20 2-20 2-22 2-22 2-39 2-39 2-62 2-62 4-4 4-4 l
p DEFINITIONS ,
REACTOR OPERATING CONDITIONS (Continued) goldShutdownCondition(OperatingMode4)
The reactor coolant T cold is less than 210*F.and the reactor coolant is at shutdown boron concentration.
i:
Refueling Shutdown Condition (Operating Mode 5)
The reactor coolant is at refueling boron concentration and Tcold is less i
than 210*F.
l' Refueling Operation Any operation involving the shuffling, removal, or replacement of nuclear
, fuel, CEA's, or startup sources.
l The Refueling Boron Concentration A reactor coolant boron concentration of at least 1800 ppm, which corre- l sponds to a shutdown margin of not less than 5% with all CEA's withdrawn.
i
! Shutdown Boron Concentration i
j The boron concentration required to make the reactor subcritical by the amount defined in paragraph 2.10.
( Refueling Outage or Refueling Shutdown l
l A' plant outage or shutdown to perform refueling operations upon reaching the planned fuel depletion for a specific core.
Plant Operating Cycle The time period from a Refueling Shutdown to the next Refueling Shutdown, i
i Amendment No. 24,32,4J,#3,103 2 L.
2.0 LIMITING CONDITIONS FOR OPERATION 2.2 Chemical and Volume Control System (Continued)
- a. One of the operable charging pumps may be removed from service provided two charging pumps are operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. Both boric acid pumps may be out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. One concentrated boric acid tank may be out of service provided a minimum of 68 inches of 6-1/4 percent to 12 percent by weight boric acid solution at a temperature of at least 20*F above saturation temperature is contained in the operable tank and provided that the tank is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- d. Only one flow path from the concentrated boric acid tanks to the reactor coolant system may be operable provided that either the other flow path from the concentrated boric acid tanks to the reactor coolant system or the flow path from the SIRW tank to the charging pumps is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- e. One channel of heat tracing may be out of service provided it is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- f. One level instrument on each concentrated boric acid tank may be out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e Basis The chemical coolant system and volume boron control 11 inventory. (system provides This is nomallycontrol of the reactor accomplished by using any one of the three charging pumps in series with one of the two boric acid pumps. An alternate method of boration will be to use the charging pumps directly from the SIRW storage tank. A third method will be to depressurize and use the safety injection pumps. There are two sources of borated water available for injection through three different paths.
'(1) The boric acid pumps can deliver the concentrated boric acid tank
! contents (6-1/4 - 12 weight percent concentration of boric acid) j to the charging pumps. The tanks are located above the charging pumps so that the boric acid will flow by gravity without being pumped.
(2) The safety injection pumps can take suction from the SIRW tank
- (at least 1800 ppm boron solution). I l
l Amendment No. #,103 2-18 I
1 l
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2.0 LIMITING CONDITIONS FOR OPERATION '
2.3 Emergency Core Cooling System Applicability Applies to the operating status of the emergency core cooling system.
Objective To assure operability of equipment required to remove decay heat from the core.
Specifications (1) Minimum Requirements The reactor shall not be made critical unless all of the following conditions are met:
- a. The SIRW tank contains not less than 283,000 gallons of water with a boron concentration of at least 1800 ppm at a temperature l not less than 40*F.
- b. One means of temperature indicati.on (local) of the SIRW tank is operable.
- c. All four safety injection tanks are operable and pressurized to at least 240 psig with a tank liquid of at least 116.2 inches (67%) and a maximum level of 128.1 inches (74%) with refueling boron concentration.
- d. One level and one pressure instrument is operable on each safety injection tank.
- e. One low-pressure safety injection pump is operable on each bus.
- f. One high-pressure safety injection pump is operable on each bus.
- g. Both shutdown heat exchangers and three or four component cooling heat exchangers are operable.
- h. Piping and valves shall be operable to provide two flow paths from the SIRW tank to the reactor coolant system.
- i. All valves, piping and interlocks associated with the above components and required to function during accident conditions are operable. HCV-2914, 2934, 2974, and 2954 shall have power removed from the motor operators by locking open the circuit breakers in the power supply lines to the valve motor operators.
FCV-326 shall be locked open.
Amendment No.17.32,M.103 2-20
- 2. 0 LIMITING CONDITIONS FOR OPERATION 2.3 Emergency Core Cooling System (Continued)
(3) Protection Against Low Temperature Overpressurization The following limiting conditions shall be applied during scheduled heatups and cooldowns. Disabling of the HPSI pumps need not be required if the reactor vessel head, a pressurizer safety valve, or a PORV is removed.
Whenever the reactor coolant system cold leg temperature is below 320*F, at least one (1) HPSI pump shall be disabled.
Whenever the reactor coolant system cold leg temperature is below 312*F at least two (2) HPSI pumps shall be disabled.
Whenever the reactor coolant system cold leg temperature is below 271 F, all three (3) HPSI pumps shall be disabled.
In the event that no charging pumps are operable, a single HPSI pump may be made operable and utilized for boric acid injection to the core.
Basis The normal procedure for starting the reactor is to first heat the reactor coolant to near operating temperature by running the reactor coolant pumps.
The reactor is then made critical by withdrawing CEA's and diluting boron in the reactor coolant. With this mode of start-up, the energy stored in the reactor coolant during the approach to criticality is substantially equal to that during power operation and therefore all engineered safety features and auxiliary cooling systems are required to be fully operable.
During low power physics tests at low temperatures, there is a negligible amount of stored energy in the reactor coolant; therefore, an accident comparable in severity to the design basis accident is not possible and the engineered safeguards systems are not required.
The SIRW tank contains a minigum of 283,000 gallons of usable water contain-ing at least 1800 ppm boronill. This is sufficient boron concentration to l provide a shutdown margin of 5%, including allowances for uncertainties, with all control rods withdrawn and a new core at a temperature of 60*F.(2)
The limits for the safety injection tank pressure and volume assure the required amount of water injection during an accident and are based on values used for the accident analyses. The minimum 116.2 inch level corresponds to a volume of 825 ft3 and the maximum 128.1 inch level corresponds to a volume of 895.5 ft 3.
Prior to the time the reactor is brought critical, the valving of the safety injection system must be checked for correct alignment and appropriate valves locked. Since the system is used for shutdown cooling, the valving will be changed and must be properly aligned prior to start-up of the reactor.
2-22 Amendment No. J7 )$,f),f/,54,74,77,JS0,103
{
2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refueling Operations (Continued) incident could occur during the refue]ing operations that would resalt in a hazard to public health and safety tl 1 Whenever changes are not being made in core geometry one flux monitor is sufficient. This permits maintenance of the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condi-tion. The shutdown cooling pump is used to maintain a unifonn boron concentration.
The shutdown margin as indicated will keep the core subcritical even if all CEA's were withdrawn from the core. During refueling operations, the reactor refueling cavity is filled with approximately 250,000 gallons of burated water. The boron concentration of this water (at least 1800 ppm l boron) is sufficient to maintain the reactor subcritical by more than 5%,
including g withdrawn.lgowanceforuncertainties,inthecoldconditionwithallrods Periodic checks of refueling water boron concentration ensure the proper shutdown margin. Communication requirements allow the control room operator to inform the refueling machine operator of any impending unsafe condition detected from the main control board indicators during fuel movement.
In addition to the above engineered safety, features, interlocks are utilized during refueling operations to ensure safe handling. An excess weight interlock is provided on the lifting hoist to prevent movement of more than one fuel assembly at a time. In addition, interlocks on the auxiliary building crane will prevent the trolley from being moved over storage racks containing irradiated fuel, except as necessary for the handling of fuel. The restriction of not moving fuel in the reactor for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the power has been removed from the core takes advantage of the decay of the short half-life fission products and allows for any failed fuel to purge itself of fission gases, thus reducing the consequences of fuel handling accident.
The ventilation air for both the containment and the spent fuel pool area flows through absolute particulate filters and radiation monitors before discharge at the ventilation discharge duct. In the event the stack discharge should indicate a release in excess of the limits in the technical specifications, the containment ventilation flow paths will be closed automatically and the auxiliary building ventilation flow paths will be closed manually. In addition, the exhaust ventilation ductwork from the spent fuel storage area is equipped with a charcoal filter which will be wgually put into operation whenever irradiated fuel is being handled.LiJ References
- 1) FSAR, Section 9.5
- 2) FSAR, Section 6.5.1.2 2-39 Amendment No. 24.75,103
k 2.0 LIMITING CONDITIONS FOR OPERATIONS 2.14 Enaineered Safety Features S_vstem Initiation Instrumentation Settings (Continued)
(3) Containment High Radiation (Air Monitoring) (Continued) t i
The setpoints for the isolation function will be calculated in accordance with the ODCM.
Each channel is supplied from a separate instrument A.C. bus and each auxiliary relay requires power to operate. On failure of a single A.C. supply, the A and B matrices will assume a one-out-of-two logic.
(4) Low Steam Generator Pressure A signal is provided upon sensing a low pressure in a steam generator to close the main steam isolation valves in order to minimize the temperature reduction in the reactor coolant system with resultant loss of water level and possible addition of reactivity. The setting of 500 psia includes a +22 psi uncertaintyandwasthesettingusedinthesafetylinalysis.(3)
As part of the AFW actuation logic, a separate signal is provided to tenninate flow to a steam generator upon sensing a
. 10w pressure in that steam generator if the other steam generator pressure is greater than the pressure setting. This is done to minimize the temperature reduction in the reactor coolant system in the event of a main steamline break. The setting of 466.7 psia includes a +31.7 psi uncertainty; therefore, a setting of 435 psia was used in the safety analysis.
(5) SIRW Tank Low Level Level switches are provided on the SIRW tank to actuate the valves in the safety injection pump suction lines in such a manner so as to switch the water supply from the SIRW tank to the containment sump for a recirculation mode of operation after a period of approximately 24 minutes following a safety injection signal. The switchover point of 16 inches above tank bottom is set to prevent the pumps from running dry during the 10 seconds required to stroke the valves and to hold in I
reserve approximately borated water. The FSAR28,000 lossgallons of ataccident of coolant least 1800 ppm (4) analysis assumed the recirculation started when the minimum usable volume of 283,000 gallons had been pumped from the tank.
(6) Low Steam Generator Water Level As part of the AFW actuation logic, a signal is provided to initiate AFW flow to one or two steam generators upon sensing a low water level in the steam generator (s) if the 2-62 Amendment No. 5,32,# ,65,86.103
4.0 DESIGN FEATURES 4.4 Fuel Storage 4.4.1 New Fuel Storage The new unirradiated fuel bundles will normally be stored in the dry new fuel storage rack with an effective multiplication factor of less than 0.9. The open grating floor below the rack and the covers above the racks, along with generous provision for drainage, precludes flooding of the new fuel storage rack.
New fuel may also'be stored in shipping containers or in the spent fuel pool racks which have a maximum effective multiplication factor of 0.95 with Fort Calhoun Type C fuel and unborated water.
The new fuel storage racks are designed as a Class I structure.
4.4.2 Spent Fuel Storage Irradiated fuel bundles will be stored prior to off-site shipment in the stainless steel lined spent fuel pool. The spent fuel pool is nonnally filled with borated water with a concentration of at least 1800 ppm. l The spent fuel racks are designed as a Class I structure.
Normally the spent fuel pool cooling system will maintain the bulk water temperature of the pool below 120*F. Under other conditions of fuel discharge, the fuel pool water temperature is maintained below 140*F.
The spent fuel racks are designed and will be maintained such that the calculated effective multiplication factor is no greater than 0.95 (including all known uncertainties) assuming the pool is flooded with unborated water. The racks are divided into 2 regions. Region 1 racks are surrounded by Boraflex; Region 2 racks have no poison. Acceptance criteria for fuel storage in Regions 1 and 2 are delineated in Section 2.8 of these Technical Specifications.
4-4 Amendment No. J),AJ,75,103
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