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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092K5471995-09-20020 September 1995 Revised Tech Spec Pages 4-31,4-32 & 4-33,incorporating Change in TS Section 4.4.1.5 ML20091L2911995-08-23023 August 1995 Proposed Tech Specs Page 6-11a,incorporating Ref to 10CFR20.1302 ML20087F4921995-08-11011 August 1995 Proposed TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements ML20085N1601995-06-22022 June 1995 Proposed Tech Specs Revising Replacement Pages in Package & Remove Outdated Pages,In Response to NRC Request for Addl Info ML20084L4351995-06-0101 June 1995 Proposed TS 5.3.1.1,describing Use of Advanced Clad Assemblies ML20084N3501995-06-0101 June 1995 Proposed Tech Specs,Deleting RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084B3361995-05-24024 May 1995 Proposed Tech Specs Re Change in Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7841995-05-17017 May 1995 Proposed Tech Specs,Consisting of Change Requests 252, Removing Chemical Addition Sys Requirements from TS to COLR ML20079A7811994-12-23023 December 1994 Proposed Tech Specs Page 3-32a ML20069A6781994-05-20020 May 1994 Proposed Tech Specs,Supporting Cycle 10 Control Rod Trip Insertion Time Testing ML20065M6831994-04-19019 April 1994 Proposed Tech Specs,Reflecting Deletion of Audit Program Frequency Requirements ML20065K0451994-04-11011 April 1994 Proposed Tech Specs Reflecting Relocation of Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR & Providing Direct Ref to Existing Tendon Surveillance Program ML20073C7731994-03-22022 March 1994 Proposed Tech Specs Re Control Rod Trip Insertion Time Testing 1999-09-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] |
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METRCFCLITAN DISC COMPA'IY JERSEY CE:iTPJLL FO'JER & LIGHT CCIGA'iY A:TD PEN!!SYLL IIA ELEC"*P.IC COMPANY THREE MILE ISLAND IIUCLEAR STATION UNIT 1 Cperating License No. DFR-50 Docket No. 50-269 Technical Specification Change Beauest No. 63 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating Licer. a No. DFR-50 for Three Mile Island :Iuclear Station Unit 1. As a part of this request, preposed replacement pages for Appendix A are also included.
METROFCLITA'I DISCN CCMPANY By /
Vice President h
Sworn and subscribed to me this i day of 1973.
G /
Ow o WW y a . .
Notary Public /
r..r nv ount ;
Rei: : ,*:.- P2 Yf COCS 33TA E C.51 N0v 13.1373 1583 318 1911ogog,,
U'iITD STATES OF AMERICA
- iUCLEAR REGULATORY CClo!ISSION I:I '"HE MATTER OF DCCKET II0. 50-289 LICE:ISE lio. DPR-50 ME"'ECPOLITMi EDISCN CCMPMtY This is to certify that a copy of Technical Specification Change Request lo. 68 to Appendix A of the Operating License for Three Mile Island
- iuclear Station Unit 1, has, on the date given belev, been filed with the U. S. :Tuclear Regulatory Cc==issicn and been served en the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States = ail, addressed as follows:
Mr. Weldon B. Arehart Mr. Harry B. Reese, Jr.
Board of Supervisors of Board of County Cc=missicners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Fennsylvania 17057 Harrisburg, Pennsylvania 17120 METECPCLITA'I DIS 0 i COMPMIY Ey ,- 7
/ ~ VIce President Dated: 5,-,,, , y o ,o-a 1583 319
>v .
Three Mile Island nuclear Station, Unit 1 Operating License No. DpR-50 Docket No. 50-289 Technical S ecification Chance Recuest #68 The licensee requests that the attached changed pages replace pages 3 h6, L-56, 6-18, and 6-19.
Reasons for Chance Recuest This proposed change is an URO revision of our Technical Specification Change Request No. 21. The new limits are = ore restrictive than vere previously used.
Safety Analysis Justifying Chance Pecuest There is no new equipment or procedure such that the probability of occurrence or the consequences of an accident or =alfunction of equip =ent i=portant to safety previously evaluated in the safety analysis report is not increased.
There is no change to any equipment or procedures such that the possibility of an accident or =alfunction of a different type than any evaluated previously in the safety analysis report is not created. The margin of safety defined in the basis for any technical specification has not been reduced.
1583 320
39 ?.ADI0 ACTIVE MATERIALS This section has been included in the Environ = ental Technical Specifications.
3.10 MISCELLwEOUS RADI0 ACTIVE MATERIALS SOUP.CES Anulicability Appliec to byproduct, source, and special nuclear radioactive =aterial sources.
Objective To assure that leakage from byproduct, source, and special nuclear radioactive material sources does not exceed allovable limits.
Specification 3 10.1 The source leakage test perforced pursuant to Specification h.13 shall be capable of detecting the presence of 0.005 pCi of radioactive
=aterial on the test sa=ple. :f the test reveals the presence of 0.005 pCi or more of re=ovable centamination, it shall immediately be withdrawn frem use, decenta=inated, and repaired, or be disposed of in accordance with Cc==issica regulations. Sealed sources are exempt from such leak tests when the source contains 100 pCi or less of beta and/or ga=ma emitting =aterial or 5 pCi or less of alpha l emitting material.
3.10.2 A complete inventory of licensed radioactive =aterials in possescien shall be maintained current at all times.
Bases The limitations on removable contamination for sources requiring leak testing, including alpha emitters, are based on 10CFR 70.39(c) limits for plutonium.
This limitation vill ensure that leakage from byproduct, source, and special nuclear material sources vill not exceed allevable intake values.
Pages 3-hT to 3-5h deleted
} )b 3-h6
.o h.13 RADICACTrlZ MA'ERIALS SCURCES SURVEILIE!CE Apolicability Applies to leakage testing of byproduct, source, and special nuclear radioactive material sources.
Objective To assure that leakage from byproduct, source, and special nuclear radioactive
=aterial sources does not exceed allevable li=its.
Specification Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Consission or any agreement State, as follows :
- 1. Each sealed source, except startup sources previously subject to core l flux, containing radioactive caterial, other than Rydrogen 3, with a half-life greater than 30 days and in any form, other than gas, shall be tested for leakage and/or contamination at intervals not to exceed six months.
- 2. The periodic leak test required does not apply to sealed sources that are stored and not being used. The sources accepted frc= 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 or indicating that a test has been made within six months prior tc the transfer, sealed scurces shall not be put into use until tested.
3 Each sealed startup source shall be tested within 31 days prior to being subjected to core flux and following repair or naintenance to the source.
,_, 1583 322
~6 9 REPORTI!G REOUIRE E ITS (cent'd) 6.9 3 Unique Reporting Requirements A. A section in the Annual Exposure Report shall include infor=ation on aircraft movements at the Harrisburg International Airport. This additional infor ation shall include the total nu=ber of aircraft =ovements. (takeoffs and landings) at the Harrisburg International Airport for the previous twelve-conth period. Also included shall be the total number of movements of aircraft larger than 200,000 pounds, based on a current percentage estimate provided by the airport manager.
B. Special reports shall be submitted to the Director of the Regulatory Operatiens Regional Office within the ti=e period specified for each report. These reports shall be submitted covering the activities identified belev:
Tests Submittal Cates (1) Containment Stru:tural Integrity Test (a) Tendon Surveillance Progra: Within 3 months after performance of surveillance program.
(_b ) Ring Girder Inspection Within 3 months Progrs: after performance of each inspection.
(2) Containment Integrated Leak Within 6 months Rate Test after ec=pletien of test.
(3) Inservice Inspection Program within 6 months after five years of operation.
(h) Radioactive Sealed Source Leakage Within 90 days after Test Revealing the Presence of ecmpletion of test.
> 0.005 microcuries of Re=cvable Contamination.
FOOTNCTES
- 1. These reporting require =ents apply only to Appendix A technical speci-fications.
- 2. A single submittal may be made for a multiple unit station. The sub-mittal should ecmbine those sections that are common te all units at the station.
1583 323 6-18
- 3. The term " forced reduction in pcver" is normally defined in the electric power industry as the occurrence of a component failure or other condition which requires that the load on the unit be reduced for corrective action immediately or up to and including the very next weekend. Note that routine preventive maintenance, surveillance and calibration activities requiring power reductions are not covered by this section.
- h. The term " forced outage" is nor ally defined in the electric power industry as the occurrence of a ecmponent failure or other condition which requires that the unit be removed from service for corrective action i==ediately or up to and including the very next weekend.
5 This tabulation supplements the requirements of 520.h07 of 10 CFR Part 20.
1583 324 6-18A
6.10 RECORD RETENTICN 6.10.1 The following records shall be retained for at least five years:
- a. Records of normal station operation including power levels and periods of operation at each power levels.
- b. Records of principal maintenance activities, including inspection, reports, substitution, or replacement of principal ite=s of equipment pertaining to nuclear safety.
- c. Records of reportable occurrences and safety limits exceeded.
- d. Records of periodic checks, tests, and calibration.
- e. Records of reactor physics tests and other special tests pertaining to nuclear safety.
- f. Changes to nuclear safety related operating procedures.
- g. Records of solid radicactive shi; ents.
- h. Test results, in units of microcuries, for leak tests perfor=ed on licensed sealed sources.
- i. Results of annual physical inventcry verifying accountability of licensed sources on record.
J. Control Room Log Book.
- k. Shift Fore =an's Log.
6.10.2 The following records shall be retained for the duration of Operating License DPR-50:
- a. Record and drawing changes reflecting facility design modifications made to syste=s and equip =ent described in the Final Safety Analysis Report,
- b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
- c. Routine station radiation surveys and =enitoring records.
- d. Records of radiation exposure history and radiation exposure status of personnel, including all contractors and station visitors who enter radioactive material area.
- e. Records of radioactive liquid and gaseous vastes released to the environment, and records of environnental =cnitoring surveys,
- f. Records of transient or operational cycles for those nuclear safety related facility ecmponents designed for a limited number of transient or cycles as defined in the Final Safety Analysis Report.
1583 325 6-19