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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 |
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| {{#Wiki_filter:A'C CKLFRATED SISTRIBUTlON DEMO.i STRATION SYSTEM REGULAT(ZNFORMATZON DZSTRZBUTZONZSTEM (RZDS)ACCESSION NBR;8902080288 DOC.DATE: 89/02/03 NOTARIZED: | | {{#Wiki_filter:A'C CKLFRATED SISTRIBUTlON DEMO.i STRATION SYSTEM REGULAT( ZNFORMATZON DZSTRZBUTZONZSTEM (RZDS) |
| NO DOCKET I FACIL:50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana&05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P. | | ACCESSION NBR;8902080288 DOC.DATE: 89/02/03 NOTARIZED: NO DOCKET I FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURDEY,T.E. Office of Nuclear Reactor Regulation, Director (Post 870411 |
| Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURDEY,T.E. | |
| Office of Nuclear Reactor Regulation, Director (Post 870411 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application to amend DPR-74,to modify T/S Table 3.2-1 (DNB Parameters). | | Application to amend DPR-74,to modify T/S Table 3.2-1 (DNB Parameters). |
| DISTRIBUTION'CODE: | | DISTRIBUTION'CODE: A001D COPIES RECEIVED:LTR I ENCL J SIZE: (P+ ~ |
| A001D COPIES RECEIVED:LTR I ENCL J SIZE: (P+~TITLE: OR Submittal: | | TITLE: OR Submittal: General Distribution NOTES: |
| General Distribution NOTES: RECIPIENT ID CODE/NAME PD3-1 LA STANGFJ COPIES LTTR ENCL 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD COPIES LTTR ENCL 2 2 INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DEST/SICB NUDOCS-BSTRACT E 01 EXTERNAL: LPDR NSIC 1 0 1 1 1 1 1 1 1 1 1 1-1 1 1 1 NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/DOEA/TSB 11 OGC/HDS1 RES/DSIR/EIB NRC PDR 1 1 1 1 1 1 1 1 1 0 1 1 1 1 R I NOrE'ro ALL RIDS~XXPIENXS. | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 2 2 STANGFJ 1 1 INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SICB 1 1 NRR/DOEA/TSB 11 1 1 NUDOCS- BSTRACT 1 1 OGC/HDS1 1 0 E 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR -1 1 NRC PDR 1 1 NSIC 1 1 R |
| PLEASE HELP US TO REDUCE HASTE.'GWZACr | | I NOrE 'ro ALL RIDS ~XXPIENXS. |
| '%HE DOCXMÃZ'CONrROL DESK, BOCK Pl-37 (EXT.20079)KO ELGHZHtGR YOUR MME FBOH DISTRIHlTIQN LISTS POR DOCUMENXS VXJ DGNFT 5EEDt TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 16 I | | PLEASE HELP US TO REDUCE HASTE.'GWZACr '%HE DOCXMÃZ'CONrROL DESK, BOCK Pl-37 (EXT. 20079) KO ELGHZHtGR YOUR MME FBOH DISTRIHlTIQN LISTS POR DOCUMENXS VXJ DGNFT 5EEDt TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 16 |
| Indiana Wlichigan Power Company P.O.Box 16631.Columbus, OH 43216 8 AEP:NRC:1070A 10 CFR 50.90 Donald C.Cook Nuclear Plant Unit 2 Docket No.50-316 License No.DPR-74 TECHNICAL SPECIFICATION CHANGE: MINIMUM REACTOR COOLANT FLOW REQUIREMENT U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Murley February 3, 1989
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| ==Dear Dr.Murley:==
| | I Indiana Wlichigan Power Company P.O. Box 16631 |
| This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss)for the Donald C.Cook Nuclear Plant Unit 2.Specifically, we propose to modify T/S Table 3.2-1 (DNB Parameters) such that the reactor coolant system flow rate is expressed on a volumetric rather than a mass basis.The proposed change is intended to ensure the requirements of the safety analyses are appropriately reflected in the T/Ss.The change is similar to a change proposed for Unit 1 of the Cook Nuclear Plant in letter No.AEP:NRC:1067, dated October 14, 1988.Attachment 1 to this letter summarizes the basis for the proposed change and includes our significant hazards evaluation.
| | . Columbus, OH 43216 8 |
| Attachment 2 contains the proposed revised T/S page.Attachment 3 contains a letter from ANF (the Cook Nuclear Plant Unit 2 fuel vendor)documenting their concurrence with the change.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 amounts of any effluent that may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting.8+02080288 8V0203 PDR ADOCK 05000~1+F'NU ot/l(
| | AEP:NRC:1070A 10 CFR 50.90 Donald C. Cook Nuclear Plant Unit 2 Docket No. 50-316 License No. DPR-74 TECHNICAL SPECIFICATION CHANGE: MINIMUM REACTOR COOLANT FLOW REQUIREMENT U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley February 3, 1989 |
| Dr.T.E.Murley-2-AEP:NRC:1070A In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr.R.C.Callen of the Michigan Public Service Commission and Mr.George Bruchmann of the Michigan Department of Public Health.This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
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| Sincerely, M..Al xich Vice President ldp Attachments cc: D.H.Williams, Jr.W.G.Smith, Jr.-Bridgman G~Bruchmann R.C.Callen G.Charnoff A.B.Davis-Region III NRC Resident Inspector-Bridgman ATTACHMENT 1 TO AEP:NRC:1070A DESCRIPTION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR THE DONALD C.COOK NUCLEAR PLANT UNIT 2 Attachment 1 to AEP:NRC:1070A Page 1 We are proposing to change the minimum required reactor coolant system flog rate specified in Table 3.2-1 (DNB Parameters) from 138.6 x 10 lbs/hr to the corresponding flow rate of 364,960 gpm.This change is administrative in nature, intended to ensure consistency between the safety analysis assumptions and the T/S.The change from mass flow to volumetric flow in T/S Table 3.2-1 results from our review of the relationship between the analysis assumption and the surveillance test that ensures the safety analysis assumption is satisfied.
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| The safety analyses performed by Advanced Nuclear Fuels (ANF), the Unit 2 fuel vendor, make an assumption regarding the primary volumetric flow at the core entrance.The surveillance test, which is a calorimetric test, obtains the mass flow required to remove the heat generated in the core at the measured temperature difference between the hot and cold legs.The volumetric flow is approximately independent of coolant temperature.
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| However, the mass flow depends directly on coolant density, which does vary with temperature., In order to ensure a correct comparison between the safety analysis assumed flow and the measured flow, we propose to specify the volumetric flow in the T/Ss.The surveillance procedure will then convert the measured mass flow to volumetric flow using temperatures from the test data.The proposed minimum flow value of 364,960 gpm)s the volumetric flow corresponding to a mass flow of 138.6 x 10 lbs/hr and an inlet temperature of 542.3 F.The 364,960 gpm value is exactly 0 four times the single loop design flow value of 91,240 gpm specified in T/S Table 2.2-1.The inlet temperature of 542.3 F is consistent with the Unit 2 full power T value of 574.1 F.ANF's concurrence with the change is provi8e5 in Attachment 3 to this letter.A similar change was proposed for Unit 1 of the Cook Nuclear Plant in our letter AEP:NRC:1067, dated October 14, 1988.That letter provided the analyses and T/S changes which support our reduced temperature and pressure program for Unit 1.10 CFR 50.92 Evaluation Per 10 CFR 50.92, a proposed amendment will not involve significant hazards consideration if the proposed amendment does not: (1)involve a significant increase in the probability or consequences of a previously evaluated accident, (2)create the possibility of a new or different kind of accident from any previously evaluated, or (3)involve a significant reduction in a margin of safety.
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| Attachment 1 to AEP:NRC:1070A Page 2 Criterion 1 The change is administrative in nature, consisting only of changing a mass flow rate to a volumetric flow rate at the appropriate temperature. | | ==Dear Dr. Murley:== |
| The change does not lessen any previous requirements. | | |
| Thus, the change is not expected to increase the probability or consequences of a previously evaluated accident, nor should it reduce the margin of safety.Criterion 2 The change is administrative in nature, intended to ensure consistency between the T/Ss and the safety analysis assumptions. | | This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant Unit 2. Specifically, we propose to modify T/S Table 3.2-1 (DNB Parameters) such that the reactor coolant system flow rate is expressed on a volumetric rather than a mass basis. |
| | The proposed change is intended to ensure the requirements of the safety analyses are appropriately reflected in the T/Ss. The change is similar to a change proposed for Unit 1 of the Cook Nuclear Plant in letter No. AEP:NRC:1067, dated October 14, 1988. |
| | Attachment 1 to this letter summarizes the basis for the proposed change and includes our significant hazards evaluation. |
| | Attachment 2 contains the proposed revised T/S page. |
| | Attachment 3 contains a letter from ANF (the Cook Nuclear Plant Unit 2 fuel vendor) documenting their concurrence with the change. |
| | 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 amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. |
| | These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting. |
| | ot/ |
| | F'NU 8+02080288 8V0203 PDR ADOCK 05000~1+ l( |
| | |
| | Dr. T. E. Murley AEP:NRC:1070A In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and Mr. George Bruchmann of the Michigan Department of Public Health. |
| | This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned. |
| | Sincerely, M. . Al xich Vice President ldp Attachments cc: D. H. Williams, Jr. |
| | W. G. Smith, Jr. - Bridgman G ~ Bruchmann R. C. Callen G. Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman |
| | |
| | ATTACHMENT 1 TO AEP:NRC:1070A DESCRIPTION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR THE DONALD C. COOK NUCLEAR PLANT UNIT 2 to AEP:NRC:1070A Page 1 We are proposing to change the minimum required reactor coolant system flog rate specified in Table 3.2-1 (DNB Parameters) from 138.6 x 10 lbs/hr to the corresponding flow rate of 364,960 gpm. |
| | This change is administrative in nature, intended to ensure consistency between the safety analysis assumptions and the T/S. |
| | The change from mass flow to volumetric flow in T/S Table 3.2-1 results from our review of the relationship between the analysis assumption and the surveillance test that ensures the safety analysis assumption is satisfied. The safety analyses performed by Advanced Nuclear Fuels (ANF), the Unit 2 fuel vendor, make an assumption regarding the primary volumetric flow at the core entrance. The surveillance test, which is a calorimetric test, obtains the mass flow required to remove the heat generated in the core at the measured temperature difference between the hot and cold legs. The volumetric flow is approximately independent of coolant temperature. However, the mass flow depends directly on coolant density, which does vary with temperature., |
| | In order to ensure a correct comparison between the safety analysis assumed flow and the measured flow, we propose to specify the volumetric flow in the T/Ss. The surveillance procedure will then convert the measured mass flow to volumetric flow using temperatures from the test data. |
| | The proposed minimum flow value of 364,960 gpm )s the volumetric flow corresponding to a mass flow of 138.6 x 10 lbs/hr and an inlet temperature of 542.3 0 F. The 364,960 gpm value is exactly four times the single loop design flow value of 91,240 gpm specified in T/S Table 2.2-1. The inlet temperature of 542.3 F is consistent with the Unit 2 full power T value of 574.1 F. |
| | ANF's concurrence with the change is provi8e5 in Attachment 3 to this letter. |
| | A similar change was proposed for Unit 1 of the Cook Nuclear Plant in our letter AEP:NRC:1067, dated October 14, 1988. That letter provided the analyses and T/S changes which support our reduced temperature and pressure program for Unit 1. |
| | 10 CFR 50.92 Evaluation Per 10 CFR 50.92, a proposed amendment will not involve significant not: |
| | hazards consideration if the proposed amendment does (1) involve a significant increase in the probability or consequences of a previously evaluated accident, (2) create the possibility of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in a margin of safety. |
| | |
| | Attachment 1 to AEP:NRC:1070A Page 2 Criterion 1 The change is administrative in nature, consisting only of changing a mass flow rate to a volumetric flow rate at the appropriate temperature. The change does not lessen any previous requirements. Thus, the change is not expected to increase the probability or consequences of a previously evaluated accident, nor should it reduce the margin of safety. |
| | Criterion 2 The change is administrative in nature, intended to ensure consistency between the T/Ss and the safety analysis assumptions. |
| Therefore, the change is not expected to create the possibility of a new or different kind of accident from any previously evaluated. | | Therefore, the change is not expected to create the possibility of a new or different kind of accident from any previously evaluated. |
| Criterion 3 See Criterion 1 above.We note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870)of amendments considered not likely to involve significant hazards consideration. | | Criterion 3 See Criterion 1 above. |
| The first of these examples refers to changes that are purely administrative in nature: for example, changes to achieve consistency throughout the T/Ss, correction of an error, or a change in nomenclature. | | We note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870) of amendments considered not likely to involve significant hazards consideration. The first of these examples refers to changes that are purely administrative in nature: for example, changes to achieve consistency throughout the T/Ss, correction of an error, or a change in nomenclature. |
| The proposed changes are intended only to ensure that currently existing analyses are reflected in the T/Ss.We believe that the changes are administrative in nature since they do not reflect new analyses or permit any'elaxation in requirements but rather'larify the relationship between analyses and T/Ss.We therefore believe that the Federal Register example cited is applicable and that the changes involve no significant hazards consideration. | | The proposed changes are intended only to ensure that currently existing analyses are reflected in the T/Ss. We believe that the changes are administrative in nature since they do not reflect new analyses or permit any'elaxation in requirements but rather |
| Additionally, we have made an editorial change to Table 3.2-1.Mathematical symbols have been written out in words.Since these changes are purely editorial in nature, they will not increase the probability or consequences of a previously evaluated accident, will not create the possibility of a new or different kind of accident from any previously evaluated, and do not involve significant hazards consideration. | | 'larify the relationship between analyses and T/Ss. We therefore believe that the Federal Register example cited is applicable and that the changes involve no significant hazards consideration. |
| | Additionally, we have made an editorial change to Table 3.2-1. |
| | Mathematical symbols have been written out in words. Since these changes are purely editorial in nature, they will not increase the probability or consequences of a previously evaluated accident, will not create the possibility of a new or different kind of accident from any previously evaluated, and do not involve significant hazards consideration. |
| | |
| ATTACHMENT 2 TO AEP:NRC:1070A PROPOSED TECHNICAL SPECIFICATION PAGE}} | | ATTACHMENT 2 TO AEP:NRC:1070A PROPOSED TECHNICAL SPECIFICATION PAGE}} |
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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] 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
A'C CKLFRATED SISTRIBUTlON DEMO.i STRATION SYSTEM REGULAT( ZNFORMATZON DZSTRZBUTZONZSTEM (RZDS)
ACCESSION NBR;8902080288 DOC.DATE: 89/02/03 NOTARIZED: NO DOCKET I FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURDEY,T.E. Office of Nuclear Reactor Regulation, Director (Post 870411
SUBJECT:
Application to amend DPR-74,to modify T/S Table 3.2-1 (DNB Parameters).
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I Indiana Wlichigan Power Company P.O. Box 16631
. Columbus, OH 43216 8
AEP:NRC:1070A 10 CFR 50.90 Donald C. Cook Nuclear Plant Unit 2 Docket No. 50-316 License No. DPR-74 TECHNICAL SPECIFICATION CHANGE: MINIMUM REACTOR COOLANT FLOW REQUIREMENT U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley February 3, 1989
Dear Dr. Murley:
This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant Unit 2. Specifically, we propose to modify T/S Table 3.2-1 (DNB Parameters) such that the reactor coolant system flow rate is expressed on a volumetric rather than a mass basis.
The proposed change is intended to ensure the requirements of the safety analyses are appropriately reflected in the T/Ss. The change is similar to a change proposed for Unit 1 of the Cook Nuclear Plant in letter No. AEP:NRC:1067, dated October 14, 1988.
Attachment 1 to this letter summarizes the basis for the proposed change and includes our significant hazards evaluation.
Attachment 2 contains the proposed revised T/S page.
Attachment 3 contains a letter from ANF (the Cook Nuclear Plant Unit 2 fuel vendor) documenting their concurrence with the change.
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 amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting.
ot/
F'NU 8+02080288 8V0203 PDR ADOCK 05000~1+ l(
Dr. T. E. Murley AEP:NRC:1070A In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and Mr. George Bruchmann of the Michigan Department of Public Health.
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M. . Al xich Vice President ldp Attachments cc: D. H. Williams, Jr.
W. G. Smith, Jr. - Bridgman G ~ Bruchmann R. C. Callen G. Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman
ATTACHMENT 1 TO AEP:NRC:1070A DESCRIPTION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR THE DONALD C. COOK NUCLEAR PLANT UNIT 2 to AEP:NRC:1070A Page 1 We are proposing to change the minimum required reactor coolant system flog rate specified in Table 3.2-1 (DNB Parameters) from 138.6 x 10 lbs/hr to the corresponding flow rate of 364,960 gpm.
This change is administrative in nature, intended to ensure consistency between the safety analysis assumptions and the T/S.
The change from mass flow to volumetric flow in T/S Table 3.2-1 results from our review of the relationship between the analysis assumption and the surveillance test that ensures the safety analysis assumption is satisfied. The safety analyses performed by Advanced Nuclear Fuels (ANF), the Unit 2 fuel vendor, make an assumption regarding the primary volumetric flow at the core entrance. The surveillance test, which is a calorimetric test, obtains the mass flow required to remove the heat generated in the core at the measured temperature difference between the hot and cold legs. The volumetric flow is approximately independent of coolant temperature. However, the mass flow depends directly on coolant density, which does vary with temperature.,
In order to ensure a correct comparison between the safety analysis assumed flow and the measured flow, we propose to specify the volumetric flow in the T/Ss. The surveillance procedure will then convert the measured mass flow to volumetric flow using temperatures from the test data.
The proposed minimum flow value of 364,960 gpm )s the volumetric flow corresponding to a mass flow of 138.6 x 10 lbs/hr and an inlet temperature of 542.3 0 F. The 364,960 gpm value is exactly four times the single loop design flow value of 91,240 gpm specified in T/S Table 2.2-1. The inlet temperature of 542.3 F is consistent with the Unit 2 full power T value of 574.1 F.
ANF's concurrence with the change is provi8e5 in Attachment 3 to this letter.
A similar change was proposed for Unit 1 of the Cook Nuclear Plant in our letter AEP:NRC:1067, dated October 14, 1988. That letter provided the analyses and T/S changes which support our reduced temperature and pressure program for Unit 1.
10 CFR 50.92 Evaluation Per 10 CFR 50.92, a proposed amendment will not involve significant not:
hazards consideration if the proposed amendment does (1) involve a significant increase in the probability or consequences of a previously evaluated accident, (2) create the possibility of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in a margin of safety.
Attachment 1 to AEP:NRC:1070A Page 2 Criterion 1 The change is administrative in nature, consisting only of changing a mass flow rate to a volumetric flow rate at the appropriate temperature. The change does not lessen any previous requirements. Thus, the change is not expected to increase the probability or consequences of a previously evaluated accident, nor should it reduce the margin of safety.
Criterion 2 The change is administrative in nature, intended to ensure consistency between the T/Ss and the safety analysis assumptions.
Therefore, the change is not expected to create the possibility of a new or different kind of accident from any previously evaluated.
Criterion 3 See Criterion 1 above.
We note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870) of amendments considered not likely to involve significant hazards consideration. The first of these examples refers to changes that are purely administrative in nature: for example, changes to achieve consistency throughout the T/Ss, correction of an error, or a change in nomenclature.
The proposed changes are intended only to ensure that currently existing analyses are reflected in the T/Ss. We believe that the changes are administrative in nature since they do not reflect new analyses or permit any'elaxation in requirements but rather
'larify the relationship between analyses and T/Ss. We therefore believe that the Federal Register example cited is applicable and that the changes involve no significant hazards consideration.
Additionally, we have made an editorial change to Table 3.2-1.
Mathematical symbols have been written out in words. Since these changes are purely editorial in nature, they will not increase the probability or consequences of a previously evaluated accident, will not create the possibility of a new or different kind of accident from any previously evaluated, and do not involve significant hazards consideration.
ATTACHMENT 2 TO AEP:NRC:1070A PROPOSED TECHNICAL SPECIFICATION PAGE