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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
.
ePrag% UNITED STATES E k2 E NUCLEAR REGULATORY COMMISSION lj2Jgl[j[
yn wAssisotoN. o.c. 20sss.ooo1 OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 155 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 December 7, 1992, as supplemented by letters dated March 19, April 28, and May 14, 1993, 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; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the i 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.
- 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: -
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
9308240233 930812 PDR ADOCK 050002G5 P PDR
- 3. Accordingly, the license is hereby amended by a change to paragraph 3.D of Facility Operating License No. DPR-40 to read as follows:
3.D. Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel pool as described in the application dated December 7, 1992, as supplemented by letters dated March 19, April 28, and May 14, 1993. The modification shall consist of removing the existing racks which have a storage capacity of 729 fuel assemblies and inserting new racks which will have a storage capacity of 1083 fuel assemblies. There shall be 11 free-standing rack modules in a discrete-zone, two-region storage system.
The Appendix A Technical Specifications shall be effective as follows:
o Changes to Specifications 2.8(11) and (12), 4.4.2, and 5.10.3 and Figure 2-10, Table 3-5, and the basis for Specification 2.8 shall be effective when the last new rack is installed.
- 4. The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Harry Roo , Acting Director Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation Attachments:
- 1. Page 4a of license *
- 2. Changes to the Technical Specifications Date of Issuance: August 12, 1993
- Page 4a is attached for convenience so that the composite license reflects this change.
1
^
- 4a -
l i
i D. Spent Fuel Pool Modification '
The licensee is authorized to modify the spent fuel pool as described in the application dated December 7, 1992, as supplemented ,
by letters dated March 19, April 28, and May 14, 1993. The ;
modification shall consist of removing the existing racks which have !
a storage capacity of 729 fuel assemblies and inserting new racks ,
which will have a storage capacity of 1083 fuel assemblies. There shall be 11 free-standing rack modules in a discrete-zone, two- I region storage system. ;
The Appendix A Technical Specifications shall be effective as follows:
o Changes to Specifications 2.8(11) and (12), 4.4.2, and 5.10.3 I and Figure 2-10, Table 3-5, and the basis for Specification 2.8 shall be effective when the last new rack is installed. <
- 4. This amended license is effective as of the date of issuance and shall !
expire at midnight on June 7, 2008. !
FOR THE NUCLEAR REGULATORY COMMISSION !
Original signed by:
A. Giambusso l
A. Giambusso, Deputy Director for Reactor Projects !
Directorate of Licensing !
Enclosures.
Appendices A and B - Technical Specifications i i
Date of Issuance: August 9, 1973 t
i I
i 1
Amendment No.155 f
i t
ATTACHMENT TO LICENSE AMENDMENT NO.155 l
FACILITY OPERATING LICENSE N0. DPR-40 DOCKET NO. 50-285 l Revise Appendix "A" Technical Specifications as indicated below. The revised !
pages are identified by amendment number and contain vertical lines indicating l the area of change. :
FEMOVE PAGES INSERT PAGES i 2-38 2-38 Figure 2-10 Figure 2-10 i 2-39 2-39 .
3-20d 3-20d !
4-4 4-4 i i
5-19 5-19 i
b I
9 d
2.0 LIMITING CONDITIONS FOR OPERATION ,
2.8 Refueling Onerations (Continued)
(6) Direct communication between personnel in the control room and at the refueling
~
machine shall be available whenever changes iu core geometry are taking place.
(7) When irradiated fuel is being handled in the auxihary building, the exhaust i ventilation from the spent fuel pool area will be diverted through the charcoal ;
filter. ;
i (8) Prior to initial core loading and prior to refueling operations, a complete check
. out, including a load test, shall be conducted on fuel handling cranes that will be ,
required during the refueling operation to handle spent fuel assemblies.
(9) A minimum of 23 feet of water above the top of the core shall be maintained !
whenever irradiated fuel is being handled.
(10) Storage in Region 1 and Region 2 of the spent fuel racks shall be restricted to fuel assemblies having initial enrichment less or equal to 4.0 weight percent of U-235. ;
(11) Storage in Region 2 of the spent fuel racks shall be restricted to those assemblies whose parameters fall within the " acceptable" area of Figure 2-10. Storage in the peripheral cells of Region 2 shall be restricted to those assemblies whose ;
parameters fall within the noted area of Figure 2-10.
(12) A minimum boron concentration of 100 ppm shall be maintained in the Spent Fuel Pool whenever storing unitradiated fuel in the Spent Fuel Pool.
If any of the above conditions are not met, all refueling operations shall cease !
immediately, work shall be initiated to satisfy the required conditions, and no operations that may change the reactivity of the core shall be made.
A spent fuel assembly may be transferred directly from the reactor core to the spent fuel ;
pool Region 2 provided the independent verification of assembly burnups has been '
completed and the assembly burnup meets the acceptance criteria identified in Technical Specification Figure 2-10.
Movement of irradiated fuel from the reactor core shall not be initiated before the reactor l core has been subcritical for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the reactor has been operated at !
power levels in excess of 2% rated power.
Bases The equipment and general procedures to be utilized during refueling operations are !
discussed in the USAR. Detailed instructions, the above specifications, and the design ;
of the fuel handling equipment incorporating built-in interlocks and safety features provide assurance that no incident could occur during the refueling operations that would 2-38 Amendment No. 5,24,25,43,75,133,152, 155 i
i FIGURE 2-10 1
37500 35000 : .
32500 :
30000 : /
27500 3 ACCEPTABLE /
3 BJRNUP DOMAIN / ,
r 25000 : / .
% *g/ s' '
i 22500 .5 ,'
i ^ '
h a
20000l 17500 _ y f 'j'f ,
s ua s
15000 : '$/ ' 8' e i $ /> ,y*
12500 - r
! / <
10000
[, ' ' > UNACCEPTnBLE 7500:!
t
, BUFNUP D0iAIN 5000 _
, ( Re cuires Region 1 Storege) 2500 :
- /',,
0: ./. .
1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 INITIAL ENRICHMENT, wt% U235 LIMITING BURNUP CRITERIA FOR ACCEPTABLE STORAGE IN REGION 2 NOTE: 1. Ang fuel essembly (24.2% U235 overege) mechanically coupled with a full length CEA meg be located engwhere in Region 2.
- 2. Peripheral cells are those adjacent to the Spent Fuel Pool well or the cesk legdown area.
Amendment No. M;433,155
2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refuelinn Ooerations (Continued) i result in a hazard to public health and safety.m 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 condition. The shutdown cooling pump is used to maintain a uniform boron concentration.
The shutdown margin as indicated will keep the core suberitical even if all CEA's were withdrawn from the core. During refueling operations, the reactor refueling casity is ,
filled with approximately 250,000 gallons of borated water. The boron concentration of this water (of at least the refueling boron concentration) is sufficient to maintain the ,
reactor suberitical by more than 5 %, including allowance for uncertainties, in the cold condition with all rods withdrawn.m Periodic checks of refueling water boron concent'ation ensures the proper shutdown margin. Communication requirements allow the conwol room operator to inform the refueling machine operator of any impending unsafe condition detected from the main control room 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 2 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 manually put into operation whenever irradiated fuel is being handled.m The basis for the 100 ppm boron concentration requirement with Boral poisoned storage racks is to maintain the km below 0.95 in the event a misplaced unirradiated fuel assembly is located next to a spent fuel assembly. A misplaced unirradiated fuel assembly at 4.2 w/o enrichment condition, in the absence of soluble poison, may result in exceeding the design effective multiplication factor. Soluble boron in the Spent Fuel Pool water, for which credit is permitted under these conditions, would assure that the effective multiplication factor is maintained substantially less than the design condition.
The boron concentration is periodically sampled in accordance with Specification 3.2.
References (1) USAR, Section 9.5 (2) USAR, Section 9.5.1.2 2-39 Amendment No. 24,75,103,117,133,141,155
TABLE 3-5 (Continued) '
USAR Section Test Fanuu,0 -
Reference 10c. (continued) 4. Automatic and/or manual initi- At least once per plant operating cycle.
ation of the system shall be demonstrated. j
- 11. Containment Cool- 1. Demonstrate damper action. I year, 2 years, 5 years, and every 5 9.10 ing and lodine years thereafter.
Removal Fusible Linked Dampers 2. Test a spare fusible link.
- 12. Diesel Generator Calibrate During each refueling outage. 8.4.3 Under-Voltage Relays
- 13. Motor Opted Verify the contactor pickup value at During each refueling outage.
Safety injection 5,85% of 460 V.
Loop \ alve Motor Starters ()(CV-311, 314,317,320,327, 329,331,333,312, 315, 318, 321) j 14. Pressurizer llesters Verify control circuits operation During each refueling outage.
j for post-accident heater use.
- 15. Spent Fuel Pool Test neutron poison samples for I, 2, 4, 7, and to years after j Region i Racks dimensional change, hardness change, installation, and every 5 years weight, neutron attenuation change thereafter.
and specific gravity change.
- 16. Reactor Coolant 1. Verify all manual isolation During each refueling outagejust Gas Vent System valves in each vent path are prior to plant start-up.
- 2. Cycle each automatic valve in During each refueling outage.
the vent path through at least one complete cycle of full travel from the control room.
Verification of valve cycling may be determined by olmtva-tion of position indicating lights.
- 3. Verify flow through the reactor During each refueling outage, coolant vent system vent paths.
3-20d Ammdment No. ,51.".'5,7?,=,155
4.0 DESIGN FEATURES 4.4 Fuel Storace 4.4.1 New Fuel Storace 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 Stent Fuel Storace Irradiated fuel bundles will be stored prior to off-site shipment in the stainless steel lined spent fuel pool. The spent fuel pool is normally filled with borated water with a concentration of at least the refueling boron concentration.
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 14CTF.
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 and 2 cells are surrounded by Boral. Acceptance l criteria for fuel storage in Regions 1 and 2 are delineated in Section 2.8 of these Technical Specifications.
4-4 Amendrr.ent No. 13,43,75,103, 133,141,155
5.0 ADMINISTRATIVE CONTROLS 5.10.2 The following records shall be retained for the duration of the Facility Operating License:
- a. Records of drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
- b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
- c. Records of facility radiation and contamination surveys,
- d. Records of radiation exposure for all individuals entering radiation control areas.
- c. Records of gaseous and liquid radioactive material released to the environs.
- f. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
- g. Records of training and qualification for current members of the plant staff.
- h. Records of in-service inspections performed pursuant to these Technical Specifications.
- i. Records of Quality Assurance activities required by the QA Manual.
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- k. Records of meetings of the Plant Review Committee and the Safety Audit and Review Committee.
- 1. Records of Environmental Qualification of Electric Equipment pursuant to 10 CFR 50.49.
- m. Records of the se>vice lives of all hydraulic and mechanical snubbers which are covered mder the provisions of Section 2.18 of the Technical Specifications, inch ding the date at which the service life commences and associated installa6on and maintenance records.
- n. Records of analyses required by the Radiological Environmental Monitoring Program.
- o. Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program.
5.10.3 A complete record of the analysis employed in the selection of any fuel assembly to be placed in Region 2 of the spent fuel racks will be retained as long as that assembly remains in Region 2 (reference Technical Specifications 2.8 and 4.4).
l 5.11 Radiation Protection Procram Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
5-19 Order 70/2"S0 Amendment No. 59,86,93,99,105,152,155