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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
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, . O ur yg, . '*, UNITED STATES 3
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2068H001
%, ...../
OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE l
! l Amendment No.176 License No. DPR-40
- 1. The Nuclear Regulatory Comission (the Commission) has found that-A. The application for amendment by the Omaha Public Power District (the licensee) dated May 17, 1996, 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; i
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-1 D. The issuance of this license 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.
9610070149 960927 PDR ADOCK 05000285 P PDR
t l
l
- 2. Accordingly, Facility Operating License No. DPR-40 is hereby amended to l approve the relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensee's application dated May 17, 1996, and reviewed in the staff's safety evaluation dated j l September 27, 1996. This license is also hereby amended by changes to '
the Technical Specifications as indicated in the attachment to this l license amendment, and paragraph 3.B of Facility Operating License No. l DPR-40 is hereby amended to read as follows.
I B. Technical Soecifications i The Technical Specifications contained in Appendix A, as revised through Amendment No.176, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. The license amendment is effective as of its date of issuance.
Implementation shall include the relocation of Technical Specification requirements to the appropriate licensee-controlled document as identified in the licensea's dated May 17, 1996, and reviewed in the staff's safety evaluation dated September 27, 1996.
FOR THE NUCLEAR REGULATORY COMMISSION l
'. s.A L. Raynard Wharton, Project Manager l Project Directorate IV-2 l Division of Reactor Projects - III/IV {
Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: September 27, 1996 i
l I
'i ATTACHMENT TO LICENSE AMENDMENT NO. 176 E8CILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 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 11 11 y v vii vii 2-72 2-72 2-73 --
2-74 --
3-21 3-21 3-76 3-76 3-77 --
3-78 . --
3 --
3-79a --
3-79b --
3-79c --
5-19 5-19 l
. . , , . . . . . . . . . . . . . ~ . . . . . . . _ . . - . . - - - ~ , ~
t TABLE OF CONTENTS (Continoetir- ------
Enea 2.12 Control Room Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-59 2.13 Nuclear Detector Cooling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 240 2.14 Engmeered Safety Features System Initiation Instru=mmaa4a= Settings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 241 2.15 Instru-amana= and Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-65 2.16 River !.evel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-71 2.17 Miscellaneous Radioactive Matenal Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-72 2.18 DELETED l 2.19 DELETED 2.70 Steam Generator Coolant Radioactivity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-96 2.21 Post-Accident Monitoring Instrumentation ............................2-97 2.22 Toxic Gas Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-99 3.0 SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-On 3.1 Instrummtation and Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.2 Equipment and Sampling Tests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-17 3.3 Reactor Coolant System and Other Components Subject to ASME XI Boiler and Pressure Vessel Code Inspection and Testing Surveillance . . . . . . . . . . . . . . . . . . . . . . 3 21 3.4 Reactor Coolant System lategrity Testing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-36 3.5 Contan==amt Test ....... ......... .................. ........ . 3-37 3.6 Safety Injection and Containment Cooling Systems Tests . . . . . . . . . . . . .. . . . . . 3-54 3.7 Emergency Power System Periodic Tests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-58 3.8 Main Steam teolation Valves ....................................3-61 3.9 Auxiliary Feedwater System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 342 3.10 Reactor Core Panameters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 43 3.11 D ELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 44 3.12 Radioactive Waste Disposal System ................................349 3.13 Radinactive Material Sources Surveillance ............................376 3.14 DELETED l 3.15 DELETED 3.16 Residual Heat Removal System Integrity Testing . . . . . . . . . . . . . . . . . . . . . . . . 3-84 3.17 Steam Generator Tubes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-86 4.0 DESIGN FEATURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 1 4.1 Site.....................................................4-1 4.2 e'n.e.ia- e Design Features . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
4- 1 4.2.1 Contaanment Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.2.2 Penetrations ...... ... .. .... ...... .. .... . ...... .... .. .. 4-1 4.2.3 Contan====t Structure Cooling Systems .. . . . . . . . .. ..............'.4-2 ii Amendment No. , ,. .,.,. .,,. .,. ,2. ., , u.. . e . o. .m.. ,.2.
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- n. ., n. ,. . m. 2. . ., .,,. . , .,1. .. , .,., . ,. a_ , 1 7 6 l
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TECHNICAL SPECIRCATIONS - TABLES TABLE OF CONTENTS l
TABLE DESCRIFFION PAGE ,
1 3-3 Minimum Frequascies for Checks, Calibrations, and Testing !
of Miscellaneous Instrumantation and Controls .........................3-13 )
........................... 3-14
......................... .. 3-15
...........................316
...... .. ... .. .......... ... 3-16e
. . . . . . . . . . . . . . . . . . . . . . . . . . 3 - 16b
.. ... ..... .... ......... .. . 3-16c 3-3a Minimum Frequency for Checks, Calibrations and Functional i Testing of Alternate Shutdown Panels (AI 185 and AI-21%) and Emergency Auxiliary Feedwater Panel (AI-179) Instrumentation and Control Circuits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3- 16d
......... .............. . .... ...... .. .... .. 3-16e 9
3-4 Minimum Frequencies for Sampling Tests ............................3-18
...................... .......... 3-19 3-5 Minimum Frequencies for Equipment Tests ...........................3-20
........... .................... 3-20s
................................3-20b
................................3-20e
..........................,...... 3-20d !
34 Reactor Coolant Pump Surveillance ..... ...... . ..... ...... ......... 3-27 3-13 Steam Generator Tube Inspection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 -90 5.2-1 Minimum Shih Crew Composition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 i
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t
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k v Amendment No. 4!6,!2',!'2.!",!52,176
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TECHNICAL SPECIFICATIONS - TABLES 1
. I i
TABLE OF CONTENTS (ALPHABETICAL ORDER) '
4 Continued l i
I TABLE DESCRIFilON PAGE l 1
i 3-5 Minimum Frequencies for Equipment Tests ...........................3-20 l
................................3-20. ;
.. .......... .. .. .. ....... ...... . 3-20b l
................................3-20e
................................3-20d 3-4 Minimum Frequencies for Sampling Tests ............................3-!R
............ ..................... 3-19 5.2-1 Minimum ShiR Crew Composition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 2-10 Post-Accident Monitoring Instrumentation Operstmg Limits . . . . . . . . . . . . . . . . . 7 -9 8
. . . . . . . . . . . . . . . . . . . . . 2-9 8a
. . . . . . . . . . . . . . . . . . . . . 2-9 8b 2-9 RCS Pressure Isolation Valves ...................................2-24 3-6 Reactor Coolant Pump Surveillance ...... .....,. ........... .. .... ... 3-27 l1 RPS LS SS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 10
................................................. 1-10.
3-13 Steam Generator Tube Inspection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-90 4
2-11 Toxic Gas Monitoring Operating Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-100 1 t
I vii Amendment No. '!5,MS, 52,176
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2.0 IJMITING CONDITIONS FOR OPERATION 1
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[ 2.17 MISCI:H ANEOUS RADIOACTIVE MATERIAL SOURCES l Applicability 1
Applies to byproduct, source, and special nuclear radioactive material sources.
Objective To assure that leakage from byproduct, source, and special nuclear radioactive l
material sources does not exceed allowable limits. '
Specifintions l Radioactive sources shall be leak tested for contamination. The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. If the test reveals the presence of 0.005 microcurie or more of removable contamination, it shall immediately be withdrawn from use, decontaminated, and repaired, or be disposed of in accordance with Commission regulations. Those quantities of byproduct material that exceed the quantities listed in 10 CFR Part 30, Section 30.71, Schedule B are to be leak tested in accordance with the schedule shown in Surveillance Requirements. All other sources (including alpha emitters) containing greater than 0.1 microcurie are also to be leak tested in accordance with the Surveillance Requirements. l Basil Ingestion or inhalation of source material may give rise to total body or organ irradiation. This specification assures that leakage from radioactive material sources does not exceed allowable limits. In the unlikely event that those quantities of radioactive byproduct materials of interest to this specification which are exempt from leakage testing are ingested or inhaled, they represent less then one maximum permissible body burden for total body irradiation. The limits for all other sources (including alpha emitters) are based upon 10 CFR Part 70, Section 70. 39(c) limits for plutonium. l l
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2-72 Amendment No. M,176 (Next page is 2-96) Dr.:4: rd. rj 4,1975 [
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3.0 SURVERLANCE REQUIREMENTS I i - 3.3 maaa'ar raal=a* Sva*= =ad Orhar Canmananta Subi&t to ASME XI Bailer & hire i Va==.1 rad. ra=aaatma and Ta< tine Surveillance !
i
Applies to in-service surveillance of primary system components and other components i subject to inspection and testing according to ASME XI Boiler & Pressure Vessel Code.
3 l -
- Obiective i
j To ensure the integrity of the reactor coolant system and other components subject to 2
inspection and testing according to ASME XI Boiler & Pressure Vessel Code.
! Specifications 1
- (1) Surveillance of the ASME Code Class 1, 2 and 3 systems, except the steam generator tubes inspection, should be covered by ASME XI Boiler & Pressure l Vessel Code.
l j a. In-service inspection of ASME Code Class 1, Class 2, and Class 3 j l components, including applicable supports, and in-service testing of l j i ASME Code Class 1, Class 2, and Class 3 pumps and valves shall be performed in accordance with Secti6n XI of the ASME Boiler and
- l Pressure Vessel Code, as required by 10 CFR Part 50, Section 50.55a(g),
j except where specific written relief has been granted by the Commission j pursuant to 10 CFR Part 50, Section 50.55a (g)(6)(i).
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- b. Surveillance of the reactor coolant pump flywheels shall be performed as i indicated in Table 3-6.
j c. A surveillance program to monitor radiation-induced changes in the mechanical and impact properties of the reactor vessel materials shall be j maintained in accordance with 10 CFR Part 50 Appendix H.S t
8 (2) Surveillance of Reactor Coolant System Pressure Isolation Valves l;
- a. Peri <.xiic leakage testing
- on each valve listed in Table 2-9 shall be
- ma
- omplished prior to entering the power operation mode every time the
- f. plant is placed in the cold shutdown i
- To satisfy ALARA requirements, leakage may be measured indirectly (as from the i performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of j demonstrating valve compliance with the leakage criteria.
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3-21 Amendment No. ",75,1^4,102,157,176 1
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( 3.0 SURVEILLANCE REQUIREMENTS l '
3.13 RADIOACTIVE MATERIAL SOURCES SURVFIT T ANCE .. . . - . - . . - . . . . - - - - - - - . . - - - - . .
Anolicability Applies to leakage testing of byproduct, source, and special nuclear radiaactive material sources, i l
\ l l
Obiective I
To assure that leakage from byproduct, source, and special nuclear radioactive material '
sources does not exceed allowable limits.
Specification i l Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the NRC or an agreement State, as follows:
- 1. Each sealed source, except startup sources subject to core flux, containing radioactive material, other than Hydrogen 3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or 1 contamination at intervals of six months. '
- 2. The periodic leak test required does not apply to sealed sources that are stored and not being used. The sources excepted from this test shall be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to the date of use or transfer. In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer, sealed sources shall not be put into use until tested.
- 3. Startup sources shall be leak tested prior to. and following any repair or maintenance and before being subjected to core flux.
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t 3-76 Amendment No. !!,122,157,176 (Next page is 3-84) I
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,, +o 5.0 ADMINISTRATIVE CONTROIE 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 i
burnup histories.
- c. Records of facility radiation and contamination surveys.
, d. Records of radiation exposure for all individuals entering radiation control
- areas.
- e. Records of gaseous and liquid radioactive material released to the environs.
- f. Records of transient or operational cycles for these 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 Specifigations.
- 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 service lives of all hydraulic and mechanical snubbers, including the date at which the service life commences and associated installation 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 Speci(ications 2.8 and 4.4).
5.11 Rndidon Protection Program 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-70/24/80 Amendment No. 59, % ,93,"),105,152,155,176