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| | issue date = 07/08/1983 | | | issue date = 07/08/1983 |
| | title = Application for Amend to Licenses DPR-58 & DPR-74 Changing Tech Spec Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements | | | title = Application for Amend to Licenses DPR-58 & DPR-74 Changing Tech Spec Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements |
| | author name = ALEXICH M P | | | author name = Alexich M |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = DENTON H R | | | addressee name = Denton H |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000315, 05000316 | | | docket = 05000315, 05000316 |
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| {{#Wiki_filter:REGULA'Y INFORMATION OISTRISUTI(YSTEM (RIOS)I ACCESSION NBR:8307120400 DOC.DATE: 83/07/08 NOTARIZED: | | {{#Wiki_filter:REGULA'Y INFORMATION OISTRISUTI(YSTEM (RIOS) |
| YES DOCKET FACIL:50 315 Donald C.Cook Nuclear Power Plants Unj t ls"Indiana 8 05000315 50 316 Donald C.Cook Nuclear Power P 1 ant F Unit 2s Indi ana 8 05000316 AUTH NAME, AUTHOR AFFILIATION ALEXICH~M.P.Indiana 8 Michiaan Electt ic Co RECIP.NAME REC IP IENT AFFILIATION DENTONsH R Of f ice of Nuclear Reactor Reaul ation.Director S UBJECT: Aoolication for amend to Licenses DPR 58 8.DPR 74 changing Tech Soec Table 4,3 1 re reactor trio svs instrumentation surveillance reauirements. | | I ACCESSION NBR:8307120400 DOC.DATE: 83/07/08 NOTARIZED: YES DOCKET FACIL:50 315 Donald C. Cook Nuclear Power Plants Unj t ls "Indiana 8 05000315 50 316 Donald C. Cook Nuclear Power P ant F Unit 2s Indi ana 1 8 05000316 AUTH NAME, AUTHOR AFFILIATION ALEXICH~ M.P. Indiana 8 Michiaan Electt ic Co RECIP. NAME REC IP IENT AFFILIATION DENTONsH R Of f ice of Nuclear Reactor Reaul ation. Director S UBJECT: Aoolication for amend to Licenses DPR 58 8.DPR 74 changing Tech Soec Table 4,3 1 re reactor trio svs instrumentation surveillance reauirements. |
| DISTRIBUTION CODE: A001S COPI/S R/CEI)ED:LTR | | DISTRIBUTION CODE: A001S COPI/S R/CEI)ED:LTR ENCL ~ |
| 'ENCL~SIZE;'ITLE: OR Submittal:
| | SIZE; OR Submittal: General Distribution 'ITLE: |
| General Distribution NOTES: RECIPIENT ID CODE/NAME NRR ORB1 BC 01 INTERNAL: ELD/HDS3 NRR/DL D I R NRR/DSI/METB G 04 COPIES LTTR ENCL 7 7 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME NRR/DE/MTEB NRR/DI/ORAB NRR/DSI/RAB RGN3 COPIES LTTR ENCL 1 1 0 1 1 1 1 EXTERNAL: ACRS NRC PDR NTIS 09 02 6 6 1 1 1 1 LPDR NSIC 03,'2 05'1 TOTAL NUMBER OF COPIES REQUIRED>>.LTTR 26 ENCL 24 Ig tl l f-I" il il 1 tl l,~P, h k'I jl'x I'i~'i'<kf)t u II II r'pl i~4'>>II x C'<N it t II A>isis I l'j~1 ll, I I'\ | | NOTES: |
| INDIANA L MICHIGAN ELECTRIC COMPANY P.O.BOX 18 BOWLING GREEN STATION NEW YORK, N.Y.10004 July 8, 1983 AEP:NRC:0591A Donald C.'Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 AMENDMENT TO TECHNICAL SPECIFICATION CHANGE REQUEST Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB1 BC 01 7 7 INTERNAL: ELD/HDS3 1 0 NRR/DE/MTEB 1 1 NRR/DL D IR 1 1 NRR/DI /ORAB 0 NRR/DSI/METB 1 1 NRR/DSI/RAB 1 1 G 04 1 1 RGN3 1 1 EXTERNAL: ACRS 09 6 6 LPDR 03,' ' 2 NRC PDR 02 1 1 NSIC 05 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED>>.LTTR 26 ENCL 24 |
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| | INDIANA L MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 July 8, 1983 AEP:NRC:0591A Donald C.'Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 AMENDMENT TO TECHNICAL SPECIFICATION CHANGE REQUEST Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 |
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| ==Reference:== | | ==Reference:== |
| | Letter No. AEP:NRCc0591 dated January 22, 1982 |
| | |
| | ==Dear Mr. Denton:== |
| | |
| | This letter and its Attachments amend the above referenced January 22, 1982 letter as a result of discussions with members of your staff. The subject matter attached is identical to that associated with the January 22, 1982, letter; the only items we are proposing to change are: |
| | : 1) the content of the individual Technical Specifications associated with Change No. 1, and |
| | : 2) we are hereby withdrawing the Technical Specification change request contained in Change No. 3. |
| | Change No. 2 remains as proposed in the referenced January 22, 1982/ |
| | letter. Change No. 4 has already been incorporated in Technical Specification Amendment Nos. 59 and 42> for Units Nos. 1 and 2 respectively. |
| | Attachment No. 1 to this letter contains a description of the proposed changes and our justification. Attachment No. 2 to this letter contains the proposed changes to Unit Nos. 1 and 2 Technical Specifications. |
| | 8SOZZaoeoo: aaOZ0S . -' |
| | PDR ADQCK 050003i5"''," |
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| | PDR |
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| | Our evaluation of the content of this amended Technical Specification change request shows that no significant hazards considerations are involved, since the amended response does not involve a significant increase in the probability or consequences of an accident previously evaluated> does not create the possibility of a new accident, or one different from any previously evaluatedt and does not involve a significant reduction in the margin of safety. |
| | These proposed changes have been reviewed and approved by the Plant Nuclear Safety Review Committee (PNSRC) and will be reviewed by the AEPSC Nuclear Safety and Design Review Committee at its next meeting. |
| | Since this license amendment change proposal is made at the request of your staff to simplify and clarify our original request of January 22, 1982, we interpret that, in accordance with the provisions of 10 CFR Part 170, this change does not require any fee. |
| | This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned. |
| | Very truly yours, M. P. Alex ch MPA/os Vice President cc: John E. Dolan - Columbus R. S. Hunter R. W. Jurgensen W. G. Smith, Jr. - Bridgman R. C. Callen State Representative G. Charnoff NRC Resident, Inspector at Cook Plant - Bridgman |
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| | 'I Attachment No. 1 to AEP:NRC:0591A Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Justificatio'n of the Proposed Technical Specification Changes |
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| Letter No.AEP:NRCc0591 dated January 22, 1982
| | Discussed below are two groups of proposed Technical Specification (T/S) changes. For convenience, each change is discussed as a separate part. The first group of proposed changes is to Table 4.3-1 'of the Unit No. 1 T/S; the second is to Table 4.3-1 of the Unit |
| | .No. 2 T/S. As stated in the cover letter, these changes are being |
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| ==Dear Mr.Denton:==
| | proposed to mnend our previous T/S change proposal contained in Change No. 1 of Attachment No. 1 to the January 22, 1982 letter (AEP:NRC:0591). In addition, when the proposed changes are issued, the yT/S for Unit Nos. 1 and 2 will be the same with regard to these particular T/S. |
| This letter and its Attachments amend the above referenced January 22, 1982 letter as a result of discussions with members of your staff.The subject matter attached is identical to that associated with the January 22, 1982, letter;the only items we are proposing to change are: 1)the content of the individual Technical Specifications associated with Change No.1, and 2)we are hereby withdrawing the Technical Specification change request contained in Change No.3.Change No.2 remains as proposed in the referenced January 22, 1982/letter.Change No.4 has already been incorporated in Technical Specification Amendment Nos.59 and 42>for Units Nos.1 and 2 respectively.
| | GROUP 1: Obanges to Table 4.3-1 of Unit Ro. 1 Tecbnical Specifications: |
| Attachment No.1 to this letter contains a description of the proposed changes and our justification.
| | PART 1 The first proposed change is the modification of the surveillance requirements for the Source Range, Neutron Flux Channels (Item 6), so that the surveillances are required in NODES 2 and 3 only when the plant is below the P-6 permissive setpoint. As previously discussed with members of your staff, this change will make, our surveillance requirements closer to those presented in the Standard Technical Specifications f'r Westinghouse Pressurized Water Reactors; NUREG-0452, Revision No. 4. |
| Attachment No.2 to this letter contains the proposed changes to Unit Nos.1 and 2 Technical Specifications.
| | PART 2 The second proposed change is the addition of a 12-hour (Shiftly) CHANNEL CHECK requirement to the Source Range, Neutron Flux Channel (Item 6) |
| 8SOZZaoeoo:
| | This change will make the T/S closer to the Standard Technical Specifications for Westinghouse Pressurized Water Reactors; NUREG-0452, Revision No. 4. |
| aaOZ0S.-'PDR ADQCK 050003i5"''," ,,P.-''"'PDR
| | :PART 3 The third proposed change is the addition of a requirement to perform a CHANNEL CALIBRATION on the Intermediate Range and Source Range, Neutron Flux Channels (Items 5 and 6) at, least once per 549 days. |
| ~'A I Our evaluation of the content of this amended Technical Specification change request shows that no significant hazards considerations are involved, since the amended response does not involve a significant increase in the probability or consequences of an accident previously evaluated>
| | This change will make the Unit No. 1 T/S the same as the Unit No. 2 T/S and closer to the Standard Technical Specifications for Westinghouse Pressurized Water Reactors; NUREG-0452, Revision No. 4. |
| does not create the possibility of a new accident, or one different from any previously evaluatedt and does not involve a significant reduction in the margin of safety.These proposed changes have been reviewed and approved by the Plant Nuclear Safety Review Committee (PNSRC)and will be reviewed by the AEPSC Nuclear Safety and Design Review Committee at its next meeting.Since this license amendment change proposal is made at the request of your staff to simplify and clarify our original request of January 22, 1982, we interpret that, in accordance with the provisions of 10 CFR Part 170, this change does not require any fee.This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
| | 'PART 4 The fourth proposed change is the addition of a requirement to perform a CHANNEL FUNCTIONAL TEST on the Source Range, Neutron Flux Channels (Item 6) at least once per month. |
| Very truly yours, MPA/os M.P.Alex ch Vice President cc: John E.Dolan-Columbus R.S.Hunter R.W.Jurgensen W.G.Smith, Jr.-Bridgman R.C.Callen-State Representative G.Charnoff NRC Resident, Inspector at Cook Plant-Bridgman
| | This change will make the Unit No. 1 T/S the same as the Unit No. 2 T/S and closer to the |
| 'I Attachment No.1 to AEP:NRC:0591A Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Justificatio'n of the Proposed Technical Specification Changes
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| Discussed below are two groups of proposed Technical Specification (T/S)changes.For convenience, each change is discussed as a separate part.The first group of proposed changes is to Table 4.3-1'of the Unit No.1 T/S;the second is to Table 4.3-1 of the Unit.No.2 T/S.As stated in the cover letter, these changes are being-proposed to mnend our previous T/S change proposal contained in Change No.1 of Attachment No.1 to the January 22, 1982 letter (AEP:NRC:0591).
| | Standard Technical Specifications for Westinghouse Pressurized Water ReactorsJ NUREG-0452, Revision No. 4. |
| In addition, when the proposed changes are issued, the yT/S for Unit Nos.1 and 2 will be the same with regard to these particular T/S.GROUP 1: Obanges to Table 4.3-1 of Unit Ro.1 Tecbnical Specifications:
| | PART 3 The fifth proposed change is the modification of the surveillance requirements for the High Positive Rate and High Negative Rate, Power Range, Neutron Flux Channels (Items 3 and 4), so that'the neutron detectors may be excluded from CHANNEL CALIBRATION. |
| PART 1 The first proposed change is the modification of the surveillance requirements for the Source Range, Neutron Flux Channels (Item 6), so that the surveillances are required in NODES 2 and 3 only when the plant is below the P-6 permissive setpoint.As previously discussed with members of your staff, this change will make, our surveillance requirements closer to those presented in the Standard Technical Specifications f'r Westinghouse Pressurized Water Reactors;NUREG-0452, Revision No.4.PART 2 The second proposed change is the addition of a 12-hour (Shiftly)CHANNEL CHECK requirement to the Source Range, Neutron Flux Channel (Item 6)..This change will make the T/S closer to the Standard Technical Specifications for Westinghouse Pressurized Water Reactors;NUREG-0452, Revision No.4.:PART 3 The third proposed change is the addition of a requirement to perform a CHANNEL CALIBRATION on the Intermediate Range and Source Range, Neutron Flux Channels (Items 5 and 6)at, least once per 549 days.This change will make the Unit No.1 T/S the same as the Unit No.2 T/S and closer to the Standard Technical Specifications for Westinghouse Pressurized Water Reactors;NUREG-0452, Revision No.4.'PART 4 The fourth proposed change is the addition of a requirement to perform a CHANNEL FUNCTIONAL TEST on the Source Range, Neutron Flux Channels (Item 6)at least once per month.This change will make the Unit No.1 T/S the same as the Unit No.2 T/S and closer to the Standard Technical Specifications for Westinghouse Pressurized Water ReactorsJ NUREG-0452, Revision No.4.PART 3 The fifth proposed change is the modification of the surveillance requirements for the High Positive Rate and High Negative Rate, Power Range, Neutron Flux Channels (Items 3 and 4), so that'the neutron detectors may be excluded from CHANNEL CALIBRATION.
| | This change will make our surveillance requirements consistent with those presen'ted in the Standard Technical Specifications for Westinghouse Pressurized Water Reactors; NUREG-0452, Revisions No. 4. |
| This change will make our surveillance requirements consistent with those presen'ted in the Standard Technical Specifications for Westinghouse Pressurized Water Reactors;NUREG-0452, Revisions No.4.GROUP 2: Changes to Table 4,3-1 of the Unit No.2 Technical Specifications: | | GROUP 2: Changes to Table 4,3-1 of the Unit No. 2 Technical Specifications: |
| PART 1 The first proposed change is the modification of the surveillance requirements for the Source Range, Neutron Flux Channels so that the surveillances are required in MODES 2 and 3 only when the plant is below the P-6 permissive setpoint.The justification for this change is the same as that proposed for Unit No.1.PART 2 The second proposed change is the addition of a 12-hour (Shiftly)CHANNEL CHECK requirement to the Source Range, Neutron Flux Channel (Item 6).The justification for this change is the same as that proposed for Unit No.1,'PART 3 The third proposed change is the deletion of the requirement to perform surveillances of the Source Range, Neutron Flux Channel (Item 6)while in Mode 6.As per previous discussions with your staff, it has been agreed upon that the justification submitted in our January 22, 1982 letter is adequate.'PART 4 The fourth proposed change is the modification of the surveillance requirements for the High Positive Rate anQ High Negative Rate, Power Range, Neutron Flux Channels (Items 3 and 4), so that.the neutron detectors may be excluded from CHANNEL CALIBRATION. | | PART 1 The first proposed change is the modification of the surveillance requirements for the Source Range, Neutron Flux Channels so that the surveillances are required in MODES 2 and 3 only when the plant is below the P-6 permissive setpoint. The justification for this change is the same as that proposed for Unit No. |
| This change will make our surveillance requirements consistent with those presented in the Standard Technical Specifications for Westinghouse Pressurized Water Reactors, NUREG-0452, Revision No.4.}} | | 1. |
| | PART 2 The second proposed change is the addition of a 12-hour (Shiftly) CHANNEL CHECK requirement to the Source Range, Neutron Flux Channel (Item 6) . The justification for this change is the same as that proposed for Unit No. 1, |
| | 'PART 3 The third proposed change is the deletion of the requirement to perform surveillances of the Source Range, Neutron Flux Channel (Item |
| | : 6) while in Mode 6. As per previous discussions with your staff, it has been agreed upon that the justification submitted in our January 22, 1982 letter is adequate. |
| | 'PART 4 The fourth proposed change is the modification of the surveillance requirements for the High Positive Rate anQ High Negative Rate, Power Range, Neutron Flux Channels (Items 3 and 4), so that. the neutron detectors may be excluded from CHANNEL CALIBRATION. |
| | This change will make our surveillance requirements consistent with those presented in the Standard Technical Specifications for Westinghouse Pressurized Water Reactors, NUREG-0452, Revision No. 4.}} |
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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]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999
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
REGULA'Y INFORMATION OISTRISUTI(YSTEM (RIOS)
I ACCESSION NBR:8307120400 DOC.DATE: 83/07/08 NOTARIZED: YES DOCKET FACIL:50 315 Donald C. Cook Nuclear Power Plants Unj t ls "Indiana 8 05000315 50 316 Donald C. Cook Nuclear Power P ant F Unit 2s Indi ana 1 8 05000316 AUTH NAME, AUTHOR AFFILIATION ALEXICH~ M.P. Indiana 8 Michiaan Electt ic Co RECIP. NAME REC IP IENT AFFILIATION DENTONsH R Of f ice of Nuclear Reactor Reaul ation. Director S UBJECT: Aoolication for amend to Licenses DPR 58 8.DPR 74 changing Tech Soec Table 4,3 1 re reactor trio svs instrumentation surveillance reauirements.
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INDIANA L MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 July 8, 1983 AEP:NRC:0591A Donald C.'Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 AMENDMENT TO TECHNICAL SPECIFICATION CHANGE REQUEST Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Reference:
Letter No. AEP:NRCc0591 dated January 22, 1982
Dear Mr. Denton:
This letter and its Attachments amend the above referenced January 22, 1982 letter as a result of discussions with members of your staff. The subject matter attached is identical to that associated with the January 22, 1982, letter; the only items we are proposing to change are:
- 1) the content of the individual Technical Specifications associated with Change No. 1, and
- 2) we are hereby withdrawing the Technical Specification change request contained in Change No. 3.
Change No. 2 remains as proposed in the referenced January 22, 1982/
letter. Change No. 4 has already been incorporated in Technical Specification Amendment Nos. 59 and 42> for Units Nos. 1 and 2 respectively.
Attachment No. 1 to this letter contains a description of the proposed changes and our justification. Attachment No. 2 to this letter contains the proposed changes to Unit Nos. 1 and 2 Technical Specifications.
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Our evaluation of the content of this amended Technical Specification change request shows that no significant hazards considerations are involved, since the amended response does not involve a significant increase in the probability or consequences of an accident previously evaluated> does not create the possibility of a new accident, or one different from any previously evaluatedt and does not involve a significant reduction in the margin of safety.
These proposed changes have been reviewed and approved by the Plant Nuclear Safety Review Committee (PNSRC) and will be reviewed by the AEPSC Nuclear Safety and Design Review Committee at its next meeting.
Since this license amendment change proposal is made at the request of your staff to simplify and clarify our original request of January 22, 1982, we interpret that, in accordance with the provisions of 10 CFR Part 170, this change does not require any fee.
This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M. P. Alex ch MPA/os Vice President cc: John E. Dolan - Columbus R. S. Hunter R. W. Jurgensen W. G. Smith, Jr. - Bridgman R. C. Callen State Representative G. Charnoff NRC Resident, Inspector at Cook Plant - Bridgman
'I Attachment No. 1 to AEP:NRC:0591A Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Justificatio'n of the Proposed Technical Specification Changes
Discussed below are two groups of proposed Technical Specification (T/S) changes. For convenience, each change is discussed as a separate part. The first group of proposed changes is to Table 4.3-1 'of the Unit No. 1 T/S; the second is to Table 4.3-1 of the Unit
.No. 2 T/S. As stated in the cover letter, these changes are being
proposed to mnend our previous T/S change proposal contained in Change No. 1 of Attachment No. 1 to the January 22, 1982 letter (AEP:NRC:0591). In addition, when the proposed changes are issued, the yT/S for Unit Nos. 1 and 2 will be the same with regard to these particular T/S.
GROUP 1: Obanges to Table 4.3-1 of Unit Ro. 1 Tecbnical Specifications:
PART 1 The first proposed change is the modification of the surveillance requirements for the Source Range, Neutron Flux Channels (Item 6), so that the surveillances are required in NODES 2 and 3 only when the plant is below the P-6 permissive setpoint. As previously discussed with members of your staff, this change will make, our surveillance requirements closer to those presented in the Standard Technical Specifications f'r Westinghouse Pressurized Water Reactors; NUREG-0452, Revision No. 4.
PART 2 The second proposed change is the addition of a 12-hour (Shiftly) CHANNEL CHECK requirement to the Source Range, Neutron Flux Channel (Item 6)
This change will make the T/S closer to the Standard Technical Specifications for Westinghouse Pressurized Water Reactors; NUREG-0452, Revision No. 4.
- PART 3 The third proposed change is the addition of a requirement to perform a CHANNEL CALIBRATION on the Intermediate Range and Source Range, Neutron Flux Channels (Items 5 and 6) at, least once per 549 days.
This change will make the Unit No. 1 T/S the same as the Unit No. 2 T/S and closer to the Standard Technical Specifications for Westinghouse Pressurized Water Reactors; NUREG-0452, Revision No. 4.
'PART 4 The fourth proposed change is the addition of a requirement to perform a CHANNEL FUNCTIONAL TEST on the Source Range, Neutron Flux Channels (Item 6) at least once per month.
This change will make the Unit No. 1 T/S the same as the Unit No. 2 T/S and closer to the
Standard Technical Specifications for Westinghouse Pressurized Water ReactorsJ NUREG-0452, Revision No. 4.
PART 3 The fifth proposed change is the modification of the surveillance requirements for the High Positive Rate and High Negative Rate, Power Range, Neutron Flux Channels (Items 3 and 4), so that'the neutron detectors may be excluded from CHANNEL CALIBRATION.
This change will make our surveillance requirements consistent with those presen'ted in the Standard Technical Specifications for Westinghouse Pressurized Water Reactors; NUREG-0452, Revisions No. 4.
GROUP 2: Changes to Table 4,3-1 of the Unit No. 2 Technical Specifications:
PART 1 The first proposed change is the modification of the surveillance requirements for the Source Range, Neutron Flux Channels so that the surveillances are required in MODES 2 and 3 only when the plant is below the P-6 permissive setpoint. The justification for this change is the same as that proposed for Unit No.
1.
PART 2 The second proposed change is the addition of a 12-hour (Shiftly) CHANNEL CHECK requirement to the Source Range, Neutron Flux Channel (Item 6) . The justification for this change is the same as that proposed for Unit No. 1,
'PART 3 The third proposed change is the deletion of the requirement to perform surveillances of the Source Range, Neutron Flux Channel (Item
- 6) while in Mode 6. As per previous discussions with your staff, it has been agreed upon that the justification submitted in our January 22, 1982 letter is adequate.
'PART 4 The fourth proposed change is the modification of the surveillance requirements for the High Positive Rate anQ High Negative Rate, Power Range, Neutron Flux Channels (Items 3 and 4), so that. the neutron detectors may be excluded from CHANNEL CALIBRATION.
This change will make our surveillance requirements consistent with those presented in the Standard Technical Specifications for Westinghouse Pressurized Water Reactors, NUREG-0452, Revision No. 4.
