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| | issue date = 04/16/1993 | | | issue date = 04/16/1993 |
| | title = Application for Amends to Licenses DPR-58 & DPR-74,revising TS Section 6 Re Radioactive Effluent Reporting & Nuclear Safety & Design Review Committee Membership to Comply W/Nrc Final Ruling in Fr,Vol 57,Number 169,dtd 920831 | | | title = Application for Amends to Licenses DPR-58 & DPR-74,revising TS Section 6 Re Radioactive Effluent Reporting & Nuclear Safety & Design Review Committee Membership to Comply W/Nrc Final Ruling in Fr,Vol 57,Number 169,dtd 920831 |
| | author name = FITZPATRICK E | | | author name = Fitzpatrick E |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = MURLEY T | | | addressee name = Murley T |
| | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000315, 05000316 | | | docket = 05000315, 05000316 |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 8 | | | page count = 8 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:ACCELERAT~ DOCUMEN'1 DlST '8UTlON SYSTEM REGULA INFORMATION DISTRIBUTIO . YSTEM (RIDS) |
| | FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315I ACQESSION NBR:9304220164 DOC.DATE: 93/04/16 NOTARIZED: NO DOCKET 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R MURLEY,T. Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application for amends to Licenses DPR-58&DPR-74,revising TS Section 6 re radioactive effluent reporting&Nuclear Safety 6 Design Review Committee membership to comply w/NRC final ruling in FR,Vol 57,Number 169,dtd 920831.S DISTRIBUTION CODE: AOOZD COPIES RECEIVED:ILTR J ENCL Q SIZE: S H2S TITLE: OR Submittal: | | Application for amends to Licenses DPR-58 & DPR-74,revising TS Section 6 re radioactive effluent reporting & Nuclear D Safety 6 Design Review Committee membership to comply w/NRC final ruling in FR,Vol 57,Number 169,dtd 920831. |
| General Distribution
| | S DISTRIBUTION CODE: AOOZD TITLE: OR COPIES RECEIVED:ILTR Submittal: General Distribution J ENCL Q SIZE: S H2S / |
| /D NOTES'ACCELERAT~
| | NOTES' RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 DEAN,W 2 2 INTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTSB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SCSB 1 0 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT ' |
| DOCUMEN'1 DlST'8UTlON SYSTEM REGULA INFORMATION DISTRIBUTIO
| | 1 O~FN3~ 1 0 OGC/HDS2 1 0 EG FILE 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL"RIDS" RECIPIENTS: |
| .YSTEM (RIDS)ACQESSION NBR:9304220164 DOC.DATE: 93/04/16 NOTARIZED:
| | I'LEASE HELP VS fO REDUCE WASTE! CONTACI'flIE l)OCUMEN'I'ON'I'ROL D!:;IV, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FR()M I:!S I'RIIIUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| NO DOCKET I FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 13 |
| Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R MURLEY,T.Document Control Branch (Document Control Desk)RECIPIENT ID CODE/NAME PD3-1 LA DEAN,W INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1'1 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DORS/OTSB NRR/DSSA/SCSB NRR/DSSA/SRXB O~FN3~EG FILE 01 NSIC COPIES LTTR ENCL 1 1 1 1 1 0 1 1 1 0 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
| |
| I'LEASE HELP VS fO REDUCE WASTE!CONTACI'fl IE l)OCUMEN'I'ON'I'ROL D!:;IV, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FR()M I:!S I'RIIIUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 13 Indiana Michigan Power Company P.O.Box 16631 Coiumbus, OH 43216 AEP:NRC:0659V Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 SECTION 6 TECHNICAL SPECIFICATIONS CHANGE REQUEST (RAD.EFF.REPORTING AND NSDRC MEMBERSHIP) | |
| U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 ATTN: T.E.Murley April 16, 1993
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| ==Dear Dr.Murley:== | | Indiana Michigan Power Company P.O. Box 16631 Coiumbus, OH 43216 AEP:NRC:0659V Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 SECTION 6 TECHNICAL SPECIFICATIONS CHANGE REQUEST (RAD. EFF. REPORTING AND NSDRC MEMBERSHIP) |
| This letter and its attachments constitute an application for amendment of the license conditions and technical specifications (T/Ss)for the Donald C.Cook Nuclear Plant Units 1 and 2.Specifically, the changes proposed in this letter are to accommodate the NRC final rulings, published in Federal Register, Volume 57, Number 169, August 31, 1992, entitled"Reducing the Regulatory Burden on Nuclear Licensees." In addition, changes were made to the NSDRC charter to reflect a recent corporate reorganization. | | U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 ATTN: T. E. Murley April 16, 1993 |
| We believe the proposed changes to the T/Ss meet the regulatory requirements for the Radioactive Effluent Release Report.The NRC final ruling that addresses the reduction of the regulatory burden on nuclear licensees allows the licensee to submit their radioactive effluent release report annually in lieu of semi-annually. | | |
| The reasons for the proposed changes are to comply with the NRC final ruling and to reflect a corporate reorganization; we have, therefore, not included further justification nor do we believe any significant hazard considerations are necessary. | | ==Dear Dr. Murley:== |
| We believe that the proposed changes will not result in (1)a significant change in the types of effluents or a significant increase in the amount of any effluents that may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.These changes do not have any significant environmental impact.The proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and by the Nuclear Safety.and Design Review Committee. | | |
| 220028 9304220164 930416 PDR ADOCK 05000315 P-,PDR- | | This letter and its attachments constitute an application for amendment of the license conditions and technical specifications (T/Ss) for the Donald C. Cook Nuclear Plant Units 1 and 2. |
| ~~I 1'4~(I"le'r Dr.T.E.Murley-2-AEP'NRC'0659V In compliance with the requirements of 10CFR50.91(b)(1), copies of this'etter and its attachments have been transmitted to Mr.J.R.Padgett of the Michigan Public Service Commission and to the Michigan Department of Public Health.Attachment 1 contains the extent of the proposed, revised T/Ss pages.Attachment 2 contains the current T/Ss pages marked-up to reflect the proposed changes.Attachment 3 contains the revised T/Ss pages.Sincerely, Vice President edg Attachment CC: A.A.Blind J.R.Padgett G.Charnoff NFEM Section Chief A.B.Davis-Region III NRC Resident Inspector-Bridgman ATTACHMENT 1 TO AEP:NRC:0659V THE EXTENT OF PROPOSED TECHNICAL SPECIFICATIONS CHANGES Attachment 1 to AEP:NRC:0659V Section to be Chan ed A.Unit 1 (Section 6-Administrative Controls)1.2.3.4.5.6.7.8.Paragraph 6.5.2.2-Paragraph"6.5.2.3-Paragraph 6.5'.9 Paragraph 6.5'.10 Paragraph 6.9.1.8-Paragraph 6.9.1.9-Paragraph 6.9.1.9-Paragraph 6.9.1.9-page 6-7 page 6-7 page 6-10-page 6-10 page 6-15 page 6-15 page 6-16 page 6-17 B.Unit 2 (Section 6-Administrative Controls)1.2.3.4.5.6.7.8.Paragraph Paragraph Paragraph Paragraph Paragraph Paragraph Paragraph Paragraph 6.5.2.6.5.2.6.5.2.6.5.2.6.9.1.6.9.1.6.9.1.6.9.1.2-page 6-7 3-page 6-7 9-page 6-10 10-page 6-10 8-page 6-15 9-page 6-15 9-page 6-16 9-page 6-17 Extent of Chan e The changes to these pages will allow the radioactive effluent release report to be submitted to the NRC once a year in lieu of twice a year.This requested change is due to the NRC final ruling published in the Federal Register, Volume 57, Number 169, August 31, 1992, entitled'Reducing the Regulatory Burden on Nuclear Licensees'~ | | Specifically, the changes proposed in this letter are to accommodate the NRC final rulings, published in Federal Register, Volume 57, Number 169, August 31, 1992, entitled "Reducing the Regulatory Burden on Nuclear Licensees." In addition, changes were made to the NSDRC charter to reflect a recent corporate reorganization. |
| " Presently, it is required that this report be submitted within 60 days after January 1 and July 1 of each year.Since the two reports are being combined, it is being requested to have the annual report ,submitted 90 days after January 1 of each year.This report will now require additional time to prepare.Additionally, changes have been made to reElect changes in our corporate organization.
| | We believe the proposed changes to the T/Ss meet the regulatory requirements for the Radioactive Effluent Release Report. The NRC final ruling that addresses the reduction of the regulatory burden on nuclear licensees allows the licensee to submit their radioactive effluent release report annually in lieu of semi-annually. |
| Discussion The reason for the proposed changes is to comply with the NRC final ruling published in the Federal Register, Volume 57, Number 169, August 31, 1992, entitled"Reducing the Regulatory Burden on Nuclear Licensees." Also changes were made to reflect the change in our Attachment 1 to AEP:NRC:0659V Page 2 corporate organization caused by the retirement of the Senior Executive Vice President, Engineering | | The reasons for the proposed changes are to comply with the NRC final ruling and to reflect a corporate reorganization; we have, therefore, not included further justification nor do we believe any significant hazard considerations are necessary. We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amount of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. These changes do not have any significant environmental impact. |
| &Construction and the delegation of his duties and responsibilities. | | The proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and by the Nuclear Safety .and Design Review Committee. |
| We have therefore not included further justification nor do we believe any significant hazard considerations are necessary. | | 220028 9304220164 930416 PDR ADOCK 05000315 P - ,PDR- |
| We believe that the proposed changes will not result in (1)a significant change in the types of effluents or a significant increase in the amount of any effluents that may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure. | | |
| 4~}} | | 4 ~ |
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| | I 1' (I "le'r |
| | |
| | Dr. T. E. Murley AEP'NRC'0659V In compliance with the requirements of 10CFR50.91(b)(1), copies of this'etter and its attachments have been transmitted to Mr. J. R. Padgett of the Michigan Public Service Commission and to the Michigan Department of Public Health. contains the extent of the proposed, revised T/Ss pages. contains the current T/Ss pages marked-up to reflect the proposed changes. Attachment 3 contains the revised T/Ss pages. |
| | Sincerely, Vice President edg Attachment CC: A. A. Blind J. R. Padgett G. Charnoff NFEM Section Chief A. B. Davis - Region III NRC Resident Inspector - Bridgman |
| | |
| | ATTACHMENT 1 TO AEP:NRC:0659V THE EXTENT OF PROPOSED TECHNICAL SPECIFICATIONS CHANGES |
| | |
| | Attachment 1 to AEP:NRC:0659V Section to be Chan ed A. Unit 1 (Section 6 - Administrative Controls) |
| | : 1. Paragraph 6.5.2.2- page 6-7 |
| | : 2. Paragraph"6.5.2.3- page 6-7 |
| | : 3. Paragraph 6.5 '.9 page 6-10 |
| | : 4. Paragraph 6.5 '.10 - page 6-10 |
| | : 5. Paragraph 6.9.1.8- page 6-15 |
| | : 6. Paragraph 6.9.1.9- page 6-15 |
| | : 7. Paragraph 6.9.1.9- page 6-16 |
| | : 8. Paragraph 6.9.1.9- page 6-17 B. Unit 2 (Section 6 - Administrative Controls) |
| | : 1. Paragraph 6.5.2. 2 - page 6-7 |
| | : 2. Paragraph 6.5.2. 3 - page 6-7 |
| | : 3. Paragraph 6.5.2. 9 - page 6-10 |
| | : 4. Paragraph 6.5.2. 10 - page 6-10 |
| | : 5. Paragraph 6.9.1. 8 - page 6-15 |
| | : 6. Paragraph 6.9.1. 9 - page 6-15 |
| | : 7. Paragraph 6.9.1. 9 - page 6-16 |
| | : 8. Paragraph 6.9.1. 9 - page 6-17 Extent of Chan e The changes to these pages will allow the radioactive Licensees' effluent release report to be submitted to the NRC once a year in lieu of twice a year. |
| | This requested change is due to the NRC final ruling published in the Federal Register, Volume 57, Number 169, August 31, 1992, entitled the Regulatory Burden on Nuclear " 'Reducing Presently, it is required that this report be submitted within 60 days after January 1 and July 1 of each year. Since the two reports are being combined, it is being requested to have the annual report |
| | ,submitted 90 days after January 1 of each year. This report will now require additional time to prepare. |
| | Additionally, changes have been made to reElect changes in our corporate organization. |
| | Discussion The reason for the proposed changes is to comply with the NRC final ruling published in the Federal Register, Volume 57, Number 169, August 31, 1992, entitled "Reducing the Regulatory Burden on Nuclear Licensees." Also changes were made to reflect the change in our to AEP:NRC:0659V Page 2 corporate organization caused by the retirement of the Senior Executive Vice President, Engineering & Construction and the delegation of his duties and responsibilities. |
| | We have therefore not included further justification nor do we believe any significant hazard considerations are necessary. We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amount of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. |
| | |
| | 4 ~}} |
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Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases
ML17335A5591999-10-11011 October 1999
Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes
ML17335A5411999-10-0101 October 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl
ML17326A1571999-09-23023 September 1999
Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures
ML17326A1421999-09-17017 September 1999
Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld
ML17326A1161999-09-10010 September 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling
ML17326A0921999-08-17017 August 1999
Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections
ML17325B6041999-05-21021 May 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements
ML17325B5511999-04-19019 April 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs
ML17335A3661998-12-0303 December 1998
Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys
ML17335A3631998-12-0303 December 1998
Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors
ML17335A3591998-12-0303 December 1998
Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17335A3561998-12-0303 December 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A2631998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp
ML17335A2761998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2671998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled
ML17335A2311998-09-14014 September 1998
Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A1901998-08-28028 August 1998
Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs
ML17334A7471998-06-10010 June 1998
Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change
ML17334B7011998-03-0303 March 1998
Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases
ML17334B6561997-10-0808 October 1997
Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl
ML17333B0431997-09-19019 September 1997
Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9831997-08-11011 August 1997
Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2101997-08-0101 August 1997
Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS
ML17333A8281997-03-26026 March 1997
Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8311997-03-26026 March 1997
Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted
ML17333A7121996-12-20020 December 1996
Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency
ML17334B5941996-07-11011 July 1996
Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl
ML17334B5901996-06-19019 June 1996
Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking.
ML17334B5891996-06-11011 June 1996
Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05
ML17333A4201996-04-0808 April 1996
Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1
ML17333A3551996-03-12012 March 1996
Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5
ML17334B5751996-02-29029 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl
ML17334B5741996-02-26026 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks
ML17333A3201996-02-22022 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor
ML17333A3151996-02-22022 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test
ML17333A2641996-01-12012 January 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves
ML17333A2391995-12-19019 December 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B
ML17332B0111995-11-10010 November 1995
Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations
ML17332A9971995-10-20020 October 1995
Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV
ML17332A9111995-08-0606 August 1995
Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified
ML17334B5561995-08-0404 August 1995
Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld
ML17332A8271995-06-30030 June 1995
Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1
ML17334B5501995-06-20020 June 1995
License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07
ML17332A7991995-06-15015 June 1995
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H
ML17334B5481995-05-26026 May 1995
Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria
ML17334B5461995-05-26026 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08
ML17332A7661995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty
ML17332A7741995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1
ML17332A7771995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly
1999-09-23
[Table view] |
Text
ACCELERAT~ DOCUMEN'1 DlST '8UTlON SYSTEM REGULA INFORMATION DISTRIBUTIO . YSTEM (RIDS)
FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315I ACQESSION NBR:9304220164 DOC.DATE: 93/04/16 NOTARIZED: NO DOCKET 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R MURLEY,T. Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to Licenses DPR-58 & DPR-74,revising TS Section 6 re radioactive effluent reporting & Nuclear D Safety 6 Design Review Committee membership to comply w/NRC final ruling in FR,Vol 57,Number 169,dtd 920831.
S DISTRIBUTION CODE: AOOZD TITLE: OR COPIES RECEIVED:ILTR Submittal: General Distribution J ENCL Q SIZE: S H2S /
NOTES' RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 DEAN,W 2 2 INTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTSB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SCSB 1 0 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT '
1 O~FN3~ 1 0 OGC/HDS2 1 0 EG FILE 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
I'LEASE HELP VS fO REDUCE WASTE! CONTACI'flIE l)OCUMEN'I'ON'I'ROL D!:;IV, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FR()M I:!S I'RIIIUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 13
Indiana Michigan Power Company P.O. Box 16631 Coiumbus, OH 43216 AEP:NRC:0659V Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 SECTION 6 TECHNICAL SPECIFICATIONS CHANGE REQUEST (RAD. EFF. REPORTING AND NSDRC MEMBERSHIP)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 ATTN: T. E. Murley April 16, 1993
Dear Dr. Murley:
This letter and its attachments constitute an application for amendment of the license conditions and technical specifications (T/Ss) for the Donald C. Cook Nuclear Plant Units 1 and 2.
Specifically, the changes proposed in this letter are to accommodate the NRC final rulings, published in Federal Register, Volume 57, Number 169, August 31, 1992, entitled "Reducing the Regulatory Burden on Nuclear Licensees." In addition, changes were made to the NSDRC charter to reflect a recent corporate reorganization.
We believe the proposed changes to the T/Ss meet the regulatory requirements for the Radioactive Effluent Release Report. The NRC final ruling that addresses the reduction of the regulatory burden on nuclear licensees allows the licensee to submit their radioactive effluent release report annually in lieu of semi-annually.
The reasons for the proposed changes are to comply with the NRC final ruling and to reflect a corporate reorganization; we have, therefore, not included further justification nor do we believe any significant hazard considerations are necessary. We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amount of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. These changes do not have any significant environmental impact.
The proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and by the Nuclear Safety .and Design Review Committee.
220028 9304220164 930416 PDR ADOCK 05000315 P - ,PDR-
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Dr. T. E. Murley AEP'NRC'0659V In compliance with the requirements of 10CFR50.91(b)(1), copies of this'etter and its attachments have been transmitted to Mr. J. R. Padgett of the Michigan Public Service Commission and to the Michigan Department of Public Health. contains the extent of the proposed, revised T/Ss pages. contains the current T/Ss pages marked-up to reflect the proposed changes. Attachment 3 contains the revised T/Ss pages.
Sincerely, Vice President edg Attachment CC: A. A. Blind J. R. Padgett G. Charnoff NFEM Section Chief A. B. Davis - Region III NRC Resident Inspector - Bridgman
ATTACHMENT 1 TO AEP:NRC:0659V THE EXTENT OF PROPOSED TECHNICAL SPECIFICATIONS CHANGES
Attachment 1 to AEP:NRC:0659V Section to be Chan ed A. Unit 1 (Section 6 - Administrative Controls)
- 1. Paragraph 6.5.2.2- page 6-7
- 2. Paragraph"6.5.2.3- page 6-7
- 3. Paragraph 6.5 '.9 page 6-10
- 4. Paragraph 6.5 '.10 - page 6-10
- 5. Paragraph 6.9.1.8- page 6-15
- 6. Paragraph 6.9.1.9- page 6-15
- 7. Paragraph 6.9.1.9- page 6-16
- 8. Paragraph 6.9.1.9- page 6-17 B. Unit 2 (Section 6 - Administrative Controls)
- 1. Paragraph 6.5.2. 2 - page 6-7
- 2. Paragraph 6.5.2. 3 - page 6-7
- 3. Paragraph 6.5.2. 9 - page 6-10
- 4. Paragraph 6.5.2. 10 - page 6-10
- 5. Paragraph 6.9.1. 8 - page 6-15
- 6. Paragraph 6.9.1. 9 - page 6-15
- 7. Paragraph 6.9.1. 9 - page 6-16
- 8. Paragraph 6.9.1. 9 - page 6-17 Extent of Chan e The changes to these pages will allow the radioactive Licensees' effluent release report to be submitted to the NRC once a year in lieu of twice a year.
This requested change is due to the NRC final ruling published in the Federal Register, Volume 57, Number 169, August 31, 1992, entitled the Regulatory Burden on Nuclear " 'Reducing Presently, it is required that this report be submitted within 60 days after January 1 and July 1 of each year. Since the two reports are being combined, it is being requested to have the annual report
,submitted 90 days after January 1 of each year. This report will now require additional time to prepare.
Additionally, changes have been made to reElect changes in our corporate organization.
Discussion The reason for the proposed changes is to comply with the NRC final ruling published in the Federal Register, Volume 57, Number 169, August 31, 1992, entitled "Reducing the Regulatory Burden on Nuclear Licensees." Also changes were made to reflect the change in our to AEP:NRC:0659V Page 2 corporate organization caused by the retirement of the Senior Executive Vice President, Engineering & Construction and the delegation of his duties and responsibilities.
We have therefore not included further justification nor do we believe any significant hazard considerations are necessary. We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amount of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
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