|
|
Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:0692CJ EXISTING LICENSE CONDITION PAGES MARKED TO REFLECT PROPOSED CHANGES 94041301,03 P'4Pijpg PDR'DOCK 05000315 PDR Docket No.315 Page 4 of 6 Amendment" 2.C(4)No.31.The 1'nsee ma oceed'with an s required to complete the m fication zdentified in e 1 of the Fi rotection Sa ty valuatio eport for th onald C.Cook ear Plant d June 4 1979.These difications sh be comple in ac dance with dates co tai Administrative contxols for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. | | {{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:0692CJ EXISTING LICENSE CONDITION PAGES MARKED TO REFLECT PROPOSED CHANGES 94041301,03 P'4Pijpg PDR 'DOCK 05000315 PDR |
| (5)S ent Fuel Pool Stora e Amendment No.118,136,169 The licensee is authorixed to store D.C.Cook, Unit 1 and Unit 2 fuel assemblies, new or irradiated up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C.Cook Nuclear Plant subject to the following conditions: | | |
| Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95%Uranium-235. | | Docket No. 315 Page 4 of 6 Amendment " |
| (6)Deleted by Amendment 80.Amendment No.169~~, i (7)The provisions of Specification 3/4.9.7 are not applicable for loads being moved over the pool for the duration of the spent fuel pool reracking project.Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612"Controls of Heavy Loads at Nuclear Powex Plants." Administrative controls shall be in place to prevent any load not rigged in comply.ance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged. | | 2.C(4) The 1'nsee ma oceed'with an s required to complete the No. 31 . m fication zdentified in e 1 of the Fi rotection Sa ty valuatio eport for th onald C. Cook ear Plant d June 4 1979. These difications sh be comple in ac dance with dates co tai Administrative contxols for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. |
| *2 AD Ph sical Protection Amendment No.122 The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to pxovisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822)and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Donald C.Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988;"Donald C.Cook Nuclear Plant Txaining and Qualification Plan," with revisions submitted through December 18, 1986;and"Donald C.Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988.Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. | | (5) S ent Fuel Pool Stora e Amendment The licensee is authorixed to store D. C. Cook, Unit 1 and Unit 2 No. 118,136,169 fuel assemblies, new or irradiated up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C. Cook Nuclear Plant subject to the following conditions: |
| Docket No.316 Page 5 of ll (l)Deleted by Amendment 63.(m)Deleted by hmendmont 19, (n)Deleted by hmendment 2S.(o)Pir rot tio hmendment No.12 e cen e ma pro ed r th a's equir to c let the odi cati s i tif d in abl of e iro rote ion afe oval ti Repo fo the D ld.Coo Nuclear P t ed J e 4 1979 Th e odi cati s shall be ompl ed acco dane rit the da s co aine'n Table Af t S or S le nts exe.hdministzative controls fox fixe protection as'escribed in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. | | Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95% Uranium-235. |
| Amendment No.6g>2)(p)Deleted by hmendment ATTACHMENT 3 TO AEP:NRC:0692CJ PROPOSED REVISED LICENSE CONDITION PAGES Docket No.315 Page 4 of 6 Amendment 2.C(4)No.31 Administrative controls for fire protection as I described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. | | (6) Deleted by Amendment 80. |
| (5)S ent Fuel Pool Stora e Amendment No.118,136,169 The licensee is authorized to store D.C.Cook, Unit 1 Unit 2 fuel assemblies, new or irradiated up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C.Cook Nuclear Plant subject to the following conditions: | | Amendment (7) The provisions of Specification 3/4.9.7 are not applicable for i |
| Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95%Uranium-235. | | No. 169 loads being moved over the pool for the duration of the spent |
| (6)Deleted by Amendment 80.Amendment 169 (7)The provisions of Specification 3/4.9.7 are not No.applicable for loads being moved over the pool for the duration of the spent fuel pool reracking project.Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612"Controls of Heavy Loads at Nuclear Power Plants." Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged. | | ~ ~, |
| *2.D Ph sical Protection Amendment No.122 The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822)and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Donald C.Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988;"Donald C.Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 18, 1986;and"Donald C.Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988.Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. | | fuel pool reracking project. Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612 "Controls of Heavy Loads at Nuclear Powex Plants." Administrative controls shall be in place to prevent any load not rigged in comply.ance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged. |
| Docket No.316 Page 5 of 11 (1)Deleted by Amendment 63.(m)Deleted by Amendment 19.(n)Deleted by Amendment 28.Amendment No.12 (o)Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. | | *2 AD Ph sical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to pxovisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Donald Amendment C. Cook Nuclear Plant Security Plan," with revisions submitted No. 122 through July 21, 1988; "Donald C. Cook Nuclear Plant Txaining and Qualification Plan," with revisions submitted through December 18, 1986; and "Donald C. Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. |
| Amendment No.64, 121 (p)Deleted by Amendment ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)ACCESSION NBR:9404040076 DOC.DATE: 94/03/29 NOTARIZED: | | |
| YES DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Xndiana M 05000315 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E. | | Docket No. 316 Page 5 of ll (l) Deleted by Amendment 63. |
| Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | | (m) Deleted by hmendmont 19, (n) Deleted by hmendment 2S. |
| | (o) Pir rot tio hmendment e cen e ma pro ed r th a 's equir to No. 12 c let iro rote the odi cati s ion afe oval i titifRepod in foabl the of e D ld . Coo Nuclear P t ed J e 4 1979 Th e odi cati s shall be |
| | 'n Table ompl ed acco dane rit the da s co aine Af t S or S le nts exe . hdministzative controls fox fixe protection as |
| | 'escribed in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. |
| | Amendment (p) Deleted by hmendment No. 6g >2) |
| | |
| | ATTACHMENT 3 TO AEP:NRC:0692CJ PROPOSED REVISED LICENSE CONDITION PAGES |
| | |
| | Docket No. 315 Page 4 of 6 Amendment 2.C(4) Administrative controls for fire protection as I No. 31 described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. |
| | (5) S ent Fuel Pool Stora e Amendment The licensee is authorized to store D. C. Cook, Unit 1 No. 118,136,169 Unit 2 fuel assemblies, new or irradiated up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C. Cook Nuclear Plant subject to the following conditions: |
| | Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95% Uranium-235. |
| | (6) Deleted by Amendment 80. |
| | Amendment (7) The provisions of Specification 3/4.9.7 are not No. |
| | 169 applicable for loads being moved over the pool for the duration of the spent fuel pool reracking project. |
| | Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612 "Controls of Heavy Loads at Nuclear Power Plants." Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged. |
| | *2.D Ph sical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which Amendment contain Safeguards Information protected under 10 CFR No. 122 73.21, are entitled: "Donald C. Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988; "Donald C. Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 18, 1986; and "Donald C. Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. |
| | |
| | Docket No. 316 Page 5 of 11 (1) Deleted by Amendment 63. |
| | (m) Deleted by Amendment 19. |
| | (n) Deleted by Amendment 28. |
| | Amendment (o) Administrative controls for fire protection as No. 12 described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. |
| | Amendment (p) Deleted by Amendment No. 64, 121 |
| | |
| | ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS) |
| | ACCESSION NBR:9404040076 DOC.DATE: 94/03/29 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Xndiana M 05000315 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 Document Control Branch (Document Control Desk) |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Responds to NRC 931103 request for rev to util previously proposed amend request for TS to increase allowable D tolerances for mann steam safety valves.Marked up of existing specs&proposed revised spec pages encl.8 DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR fENCL J SIZE: TITLE: OR Submittal: | | Responds to NRC 931103 request for rev to util previously proposed amend request for TS to increase allowable D tolerances for mann steam safety valves. Marked up of existing specs & proposed revised spec pages encl. 8 DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR fENCL J SIZE: |
| General Distribution NOTES: RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL: NRR/DE/EELB NRR/DRCH/HI CB 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 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DORS/OTS B NRR/DRPW NRR/DSSA/SRXB OC/~CB EG FXLE 01 NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 1 1 D D R D NOTE TO ALL"RIDS" RECIPIENTS: | | TITLE: OR Submittal: General Distribution NOTES: |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14 D D}} | | RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D HICKMAN,J 2 2 INTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTS B 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC/~CB 1 0 OGC/HDS2 1 0 EG FXLE 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 R |
| | D D |
| | D NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14}} |
Similar Documents at Cook |
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17335A5581999-10-12012 October 1999 Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5611999-10-11011 October 1999 Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal ML17335A5431999-10-0101 October 1999 Proposed Tech Specs Re Containment Recirculation Sump Water Inventory ML17326A1591999-09-23023 September 1999 Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project ML17326A1461999-09-17017 September 1999 Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality ML17326A1181999-09-10010 September 1999 Proposed Tech Specs Pages,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 ML17326A0941999-08-17017 August 1999 Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section ML17325B6061999-05-21021 May 1999 Proposed Tech Specs Revising Limitations on Positive Reactivity Additions ML17325B5551999-04-19019 April 1999 Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3681998-12-0303 December 1998 Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys ML17335A3581998-12-0303 December 1998 Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A3621998-12-0303 December 1998 Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3651998-12-0303 December 1998 Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors ML17335A2651998-10-0808 October 1998 Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp. ML17335A2691998-10-0808 October 1998 Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5 ML17335A2781998-10-0808 October 1998 Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2341998-09-14014 September 1998 Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1931998-08-28028 August 1998 Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000 ML17334B7031998-03-0303 March 1998 Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases ML20212A7051997-10-21021 October 1997 Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement ML17333B0751997-10-0808 October 1997 Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR ML17333B0451997-09-19019 September 1997 Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9851997-08-11011 August 1997 Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17333A9891997-08-11011 August 1997 Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI ML17335A2121997-08-0101 August 1997 Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig. ML17333A8261997-03-26026 March 1997 Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06 ML17333A8301997-03-26026 March 1997 Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8331997-03-26026 March 1997 Proposed Tech Specs Involving 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 in Prior Amend ML20135C3781997-02-24024 February 1997 Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements ML17333A7161996-12-20020 December 1996 Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI ML17333A7151996-12-20020 December 1996 Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys ML17333A5161996-07-22022 July 1996 Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge ML17334B5951996-07-11011 July 1996 Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt ML17333A4771996-06-19019 June 1996 Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05 ML17333A4651996-06-11011 June 1996 Proposed Tech Specs Re Administrative Controls Related to QA ML17333A4221996-04-0808 April 1996 Revised Proposed Ts,Moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3571996-03-12012 March 1996 Proposed Tech Specs,Removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3,4 & 5 ML17333A3301996-02-29029 February 1996 Proposed Tech Specs Re Boric Acid Storage Sys Boron Concentration ML17333A3231996-02-26026 February 1996 Proposed TS 5.6.2 Re Increase in Max Nominal Fuel Assembly Enrichment Limit,Taking Credit for Use of Integral Fuel Burnable Absorber Matl ML17333A3221996-02-22022 February 1996 Proposed Tech Specs,Proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3171996-02-22022 February 1996 Proposed Tech Specs,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 ML17333A3121996-02-16016 February 1996 Proposed Tech Specs Section 3.6.1.6,removing Words Structure & Steel Liner to Be Consistent W/Unit 2 Containment Sys Wording ML17333A2671996-01-12012 January 1996 Proposed Tech Specs,Modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2411995-12-19019 December 1995 Proposed Tech Specs 3/4.6.1.2,3/4.6.1.3,3/4.6/1/6 & 3/4.6.1.7,replacing Option a Scheduling Requirements for Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) W/Requirement Per 10CFR50 App J Option B ML17332B0131995-11-10010 November 1995 Proposed Tech Specs Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9991995-10-20020 October 1995 Proposed Tech Specs Adding Exemption to TS 4.0.4 in SR for MSIV ML17332A9151995-08-0808 August 1995 Proposed Tech Specs Re Deletion of Component Cyclic or Transient Limit Table ML17332A8751995-08-0404 August 1995 Proposed Tech Specs for Repair of Hybrid Expansion Joint Sleeved SG Tubes ML17332A8291995-06-30030 June 1995 Proposed Tech Specs Re Fuel Reconstitution,Per GL 90-02 ML17332A8111995-06-20020 June 1995 Proposed Tech Specs Removing Fire Protection Systems from Licenses 1999-09-23
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999 Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5611999-10-11011 October 1999 Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal ML17335A5431999-10-0101 October 1999 Proposed Tech Specs Re Containment Recirculation Sump Water Inventory ML17326A1591999-09-23023 September 1999 Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project ML17326A1461999-09-17017 September 1999 Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality ML17326A1181999-09-10010 September 1999 Proposed Tech Specs Pages,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 ML17326A0941999-08-17017 August 1999 Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section ML17326A1471999-05-28028 May 1999 Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2. ML17325B6061999-05-21021 May 1999 Proposed Tech Specs Revising Limitations on Positive Reactivity Additions ML17325B5891999-05-0707 May 1999 Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program. ML17325B5901999-05-0707 May 1999 Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys. ML17325B5551999-04-19019 April 1999 Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs ML17325B4671999-03-0303 March 1999 Rev 5 to Cook Nuclear Plant Restart Plan. ML17335A3581998-12-0303 December 1998 Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A3681998-12-0303 December 1998 Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys ML17335A3651998-12-0303 December 1998 Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors ML17335A3621998-12-0303 December 1998 Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17325B4431998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr ML17335A4071998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. ML17335A2781998-10-0808 October 1998 Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2691998-10-0808 October 1998 Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5 ML17335A2651998-10-0808 October 1998 Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp. ML17335A2341998-09-14014 September 1998 Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A2301998-09-12012 September 1998 Rev 3 to Cook Nuclear Plant Restart Plan. ML17335A2721998-09-0404 September 1998 Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project. ML17335A2751998-09-0202 September 1998 Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly. ML17335A1931998-08-28028 August 1998 Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000 ML17335A2731998-08-21021 August 1998 Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package. ML17334A7301998-05-0606 May 1998 Rev 2 of Cook Nuclear Plant Restart Plan. ML17325B5271998-04-0707 April 1998 Rev 1 to Cook Nuclear Plant Restart Plan. ML17334B8041998-04-0303 April 1998 Rev 1 to Valve IST Program for DCP Third 10-Yr Interval. ML17325B5261998-03-0707 March 1998 Rev 0 to Cook Nuclear Plant Restart Plan. ML17334B7031998-03-0303 March 1998 Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases ML20212A7051997-10-21021 October 1997 Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement ML17333B0751997-10-0808 October 1997 Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR ML17333B0451997-09-19019 September 1997 Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9891997-08-11011 August 1997 Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI ML17333A9851997-08-11011 August 1997 Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2121997-08-0101 August 1997 Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig. ML17333A8301997-03-26026 March 1997 Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8331997-03-26026 March 1997 Proposed Tech Specs Involving 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 in Prior Amend ML17333A8261997-03-26026 March 1997 Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06 ML20135C3781997-02-24024 February 1997 Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements ML17333A7161996-12-20020 December 1996 Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI ML17333A7151996-12-20020 December 1996 Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys ML17333A5161996-07-22022 July 1996 Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge ML17334B5951996-07-11011 July 1996 Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt ML17333A4771996-06-19019 June 1996 Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05 ML17333A4841996-06-11011 June 1996 ISI & Testing. ML17333A4651996-06-11011 June 1996 Proposed Tech Specs Re Administrative Controls Related to QA 1999-09-23
[Table view] |
Text
ATTACHMENT 2 TO AEP:NRC:0692CJ EXISTING LICENSE CONDITION PAGES MARKED TO REFLECT PROPOSED CHANGES 94041301,03 P'4Pijpg PDR 'DOCK 05000315 PDR
Docket No. 315 Page 4 of 6 Amendment "
2.C(4) The 1'nsee ma oceed'with an s required to complete the No. 31 . m fication zdentified in e 1 of the Fi rotection Sa ty valuatio eport for th onald C. Cook ear Plant d June 4 1979. These difications sh be comple in ac dance with dates co tai Administrative contxols for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.
(5) S ent Fuel Pool Stora e Amendment The licensee is authorixed to store D. C. Cook, Unit 1 and Unit 2 No. 118,136,169 fuel assemblies, new or irradiated up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C. Cook Nuclear Plant subject to the following conditions:
Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95% Uranium-235.
(6) Deleted by Amendment 80.
Amendment (7) The provisions of Specification 3/4.9.7 are not applicable for i
No. 169 loads being moved over the pool for the duration of the spent
~ ~,
fuel pool reracking project. Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612 "Controls of Heavy Loads at Nuclear Powex Plants." Administrative controls shall be in place to prevent any load not rigged in comply.ance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged.
- 2 AD Ph sical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to pxovisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Donald Amendment C. Cook Nuclear Plant Security Plan," with revisions submitted No. 122 through July 21, 1988; "Donald C. Cook Nuclear Plant Txaining and Qualification Plan," with revisions submitted through December 18, 1986; and "Donald C. Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
Docket No. 316 Page 5 of ll (l) Deleted by Amendment 63.
(m) Deleted by hmendmont 19, (n) Deleted by hmendment 2S.
(o) Pir rot tio hmendment e cen e ma pro ed r th a 's equir to No. 12 c let iro rote the odi cati s ion afe oval i titifRepod in foabl the of e D ld . Coo Nuclear P t ed J e 4 1979 Th e odi cati s shall be
'n Table ompl ed acco dane rit the da s co aine Af t S or S le nts exe . hdministzative controls fox fixe protection as
'escribed in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.
Amendment (p) Deleted by hmendment No. 6g >2)
ATTACHMENT 3 TO AEP:NRC:0692CJ PROPOSED REVISED LICENSE CONDITION PAGES
Docket No. 315 Page 4 of 6 Amendment 2.C(4) Administrative controls for fire protection as I No. 31 described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.
(5) S ent Fuel Pool Stora e Amendment The licensee is authorized to store D. C. Cook, Unit 1 No. 118,136,169 Unit 2 fuel assemblies, new or irradiated up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C. Cook Nuclear Plant subject to the following conditions:
Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95% Uranium-235.
(6) Deleted by Amendment 80.
Amendment (7) The provisions of Specification 3/4.9.7 are not No.
169 applicable for loads being moved over the pool for the duration of the spent fuel pool reracking project.
Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612 "Controls of Heavy Loads at Nuclear Power Plants." Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged.
- 2.D Ph sical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which Amendment contain Safeguards Information protected under 10 CFR No. 122 73.21, are entitled: "Donald C. Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988; "Donald C. Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 18, 1986; and "Donald C. Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
Docket No. 316 Page 5 of 11 (1) Deleted by Amendment 63.
(m) Deleted by Amendment 19.
(n) Deleted by Amendment 28.
Amendment (o) Administrative controls for fire protection as No. 12 described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.
Amendment (p) Deleted by Amendment No. 64, 121
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)
ACCESSION NBR:9404040076 DOC.DATE: 94/03/29 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Xndiana M 05000315 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 Document Control Branch (Document Control Desk)
SUBJECT:
Responds to NRC 931103 request for rev to util previously proposed amend request for TS to increase allowable D tolerances for mann steam safety valves. Marked up of existing specs & proposed revised spec pages encl. 8 DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR fENCL J SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D HICKMAN,J 2 2 INTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTS B 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC/~CB 1 0 OGC/HDS2 1 0 EG FXLE 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 R
D D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14