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| | issue date = 03/29/1989 | | | issue date = 03/29/1989 |
| | title = Application for Amends to Licenses DPR-58 & DPR-74, Clarifying Response Time Testing Requirements for Power Range Neutron Flux Reactor Trip | | | title = Application for Amends to Licenses DPR-58 & DPR-74, Clarifying Response Time Testing Requirements for Power Range Neutron Flux Reactor Trip |
| | 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 = MURLEY T E | | | addressee name = Murley T |
| | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000315, 05000316 | | | docket = 05000315, 05000316 |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 9 | | | page count = 9 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:kC CE1K PATED D1 BUI3 OY BE M 0~S TlOY SYSTEM ee REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DOCKET 05000315 05000316 R I+R S D D | | {{#Wiki_filter:kC CE1K PATED D1 BUI3 OY BE M 0~ S TlOY SYSTEM ee REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:8904040229 DOC.DATE: 89/03/29 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME . AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. |
| | RECIP.NAME 'ECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Control Desk) R |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application. | | Application. for amends to Licenses'PR-58 & DPR-74,to I clarify response time testing requirements for PRNFRT. |
| for amends to Licenses'PR-58 | | DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR TITLE: OR Submittal: General Distribution ENCL SIZE: +R S |
| &DPR-74,to clarify response time testing requirements for PRNFRT.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal: | | NOTES: |
| General Distribution NOTES: COPIES LTTR ENCL 1 1 RECIPIENT ID CODE/NAME PD3-1 PD COPIES LTTR ENCL 1 1 5 5 RECIPIENT ID CODE/NAME PD3-1 LA STANG,J 1 1 1 1 1 1 1 1 1 0 1 1 INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/ICSB NRR/DEST/RSB 8E-ABSTRACT RElFI E'1 1 0 1 1 1.1 1 1 1 1 1 1 NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MTB 9H NRR/DOEA/TSB 11 OGC/HDS1 RES/DSIR/EIB ACCESSION NBR:8904040229 DOC.DATE: 89/03/29 NOTARIZED: | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANG,J 5 5 D INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 D NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 1 . |
| NO FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana&50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana&AUTH.NAME.AUTHOR AFFILIATION ALEXICH,M.P.
| | 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E REl FI E '1 |
| Indiana Michigan Power Co.RECIP.NAME
| | -ABSTRACT 1 |
| 'ECIPIENT AFFILIATION MURLEY,T.E.
| | 1 1 |
| Document Control Branch (Document Control Desk)EXTERNAL: LPDR NSIC 1 1 1 1 NRC PDR 1 1 NAZE K)ALL"RIDS" RECIPIENIS'LEASE HELP US K)REDUCE WASTE!COMI'ACZ'IHE DOCUMENT CONIBDL DESK, RDCM Pl-37 (EXT.20079)KO ELIMINATE YOUR NME FRY DISTRIBUTION LISTS FOR DOCUHENZS YOU DON'T NEED!S TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 20 indiana Michigan Power Company P.O.Box 16631 Coiumbus, OH 43216 ItlAIEMANA MCHE6'AN PWE5k AEP:NRC:1078 Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 CLARIFICATION OF RESPONSE TIME TESTING REQUIREMENTS FOR POWER RANGE NEUTRON FLUX REACTOR TRIP U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Murley 1 March 29, 1989
| | 1 1 |
| | 1 NRR/DOEA/TSB OGC/HDS1 RES/DSIR/EIB 11 1 1 |
| | 1 1 |
| | 1 0 |
| | 1 1 |
| | EXTERNAL: LPDR 1 1 NRC PDR NSIC 1 1 NAZE K) ALL "RIDS" RECIPIENIS'LEASE S |
| | HELP US K) REDUCE WASTE! COMI'ACZ 'IHE DOCUMENT CONIBDL DESK, RDCM Pl-37 (EXT. 20079) KO ELIMINATE YOUR NME FRY DISTRIBUTION LISTS FOR DOCUHENZS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 20 |
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| ==Dear Dr.Murley:==
| | indiana Michigan Power Company P.O. Box 16631 Coiumbus, OH 43216 ItlAIEMANA MCHE6'AN PWE5k AEP:NRC:1078 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 CLARIFICATION OF RESPONSE TIME TESTING REQUIREMENTS FOR POWER RANGE NEUTRON FLUX REACTOR TRIP U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley 1 |
| This letter constitutes an application for amendment to the Technical Specifications (T/Ss)for the Donald C.Cook Nuclear Plant.Units 1 and 2.Specifically we are proposing to clarify the response time testing requirements for the power range neutron flux reactor trip.A detailed description of the change, our reasons for requesting the change, and our analyses concerning significant hazards are contained in Attachment 1.Attachment 2 includes the proposed revised T/S pages.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.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.S904040229 S90329 PDR ADOCK 05000315 P PDC oor Dr.T.E.Murley-2-AEP'NRC:1078 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.
| | March 29, 1989 |
| Sincerely, M.P.Al ich Vice President ldp Attachments cc: D.H.Williams, Jr.W.G~Smith, Jr.-Bridgman R.C.Callen G.Charnoff A.B.Davis NRC Resident Inspector-Bridgman G.Bruchmann ATTACHMENT 1 TO AEP:NRC 1078 REASONS AND 10 CFR 50.92 ANALYSES FOR CHANGES TO THE DONALD C.COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS Attachment 1 to AEP:NRC:1078 Page 1 Descri tion of Chan e This letter proposes to clarify the requirements of Table 3.3-2,"Reactor Trip System Instrumentation Response Times," by indicating that the requirements of Functional Unit 2 apply to both the high and low power range neutron flux (PRNF)reactor trip setpoints.
| |
| Back round and Reasons for Chan e During a review of our reactor trip system instrumentation time response testing procedures, it was observed that the time response test procedure for the nuclear instrumentation system PRNF reactor trip only included the high setpoint trip.Since credit was taken for the low setpoint trip in the safety analysis for both Units 1 and 2, the low setpoint should have been time response tested.It is believed that the lack of specific detail in the T/Ss regarding the separate setpoints was a contributing factor to the lack of testing, and we are therefore submitting the proposed changes of this letter to ensure that sufficient detail is included in the T/Ss for the PRNF reactor trip.Justification for Chan e These changes are considered to be administrative in nature and intended to clarify the response time testing requirements for the PRNF reactor trip.No operability or surveillance requirements will be reduced as a result of this change.Anal sis of Si nificant Hazards 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.Criterion 1 This change is intended to clarify the existing T/S requirements for the PRNF reactor trip, No operability or surveillance requirements have been reduced.We therefore believe the change does not involve a significant increase in the probability or consequences of an accident previously analyzed or a significant reduction in a margin of safety.
| |
| Attachment 1 to AEP:NRC:1078 Page 2 Criterion 2 The change does not involve physical modifications to the plant or changes in plant operation.
| |
| The change therefore should not create the possibility of a new or different kind of accident from any previously analyzed or evaluated.
| |
| Criterion 3 See Criterion 1 above.Lastly, 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 which are purely administrative in nature: for example, changes to achieve consistency throughout the T/Ss, correction of errors, or changes in nomenclature.
| |
| The proposed change only clarifies the present T/S.We are not proposing to reduce any present requirements.
| |
| For these reasons, we believe that the example cited is applicable and that the proposed change should not involve significant hazards consideration.
| |
|
| |
|
| TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT 1.Manual Reactor Trip RESPONSE TIME NOT APPLICABLE 2.Power Range, Neutron Flux (High and Low Setpoint)Less than or equal to 0.5 seconds 3.Power Range, Neutron Flux, High Positive Rate NOT APPLICABLE 4.Power Range, Neutron Flux, High Negative Rate Less than or equal to 0.5 seconds*5.Intermediate Range, Neutron Flux NOT APPLICABLE 6.Source Range, Neutron Flux 7.Overtemperature delta T NOT APPLICABLE Less than or equal to 6.0 seconds 8.Overpower delta T 9.Pressurizer Pressure--Low NOT APPLICABLE Less than or equal to 1.0 seconds 10.Pressurizer Pressure--High Less than or equal to 1.0 seconds 11.Pressurizer Water Level--High NOT APPLICABLE | | ==Dear Dr. Murley:== |
| *Neutron detectors are exempt from response time testing.Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.COOK NUCLEAR PLANT-UNIT 2 3/4 3-9 AMENDMENT NO. | | |
| Q~~}} | | This letter constitutes an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant. Units 1 and 2. Specifically we are proposing to clarify the response time testing requirements for the power range neutron flux reactor trip. A detailed description of the change, our reasons for requesting the change, and our analyses concerning significant hazards are contained in Attachment 1. Attachment 2 includes the proposed revised T/S pages. |
| | 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. |
| | 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. |
| | S904040229 S90329 oor PDR ADOCK 05000315 P PDC |
| | |
| | Dr. T. E. Murley AEP'NRC:1078 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. P. Al ich Vice President ldp Attachments cc: D. H. Williams, Jr. |
| | W. G ~ Smith, Jr. - Bridgman R. C. Callen G. Charnoff A. B. Davis NRC Resident Inspector - Bridgman G. Bruchmann |
| | |
| | ATTACHMENT 1 TO AEP:NRC 1078 REASONS AND 10 CFR 50.92 ANALYSES FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS to AEP:NRC:1078 Page 1 Descri tion of Chan e This letter proposes to clarify the requirements of Table 3.3-2, "Reactor Trip System Instrumentation Response Times," by indicating that the requirements of Functional Unit 2 apply to both the high and low power range neutron flux (PRNF) reactor trip setpoints. |
| | Back round and Reasons for Chan e During a review of our reactor trip system instrumentation time response testing procedures, it was observed that the time response test procedure for the nuclear instrumentation system PRNF reactor trip only included the high setpoint trip. Since credit was taken for the low setpoint trip in the safety analysis for both Units 1 and 2, the low setpoint should have been time response tested. It is believed that the lack of specific detail in the T/Ss regarding the separate setpoints was a contributing factor to the lack of testing, and we are therefore submitting the proposed changes of this letter to ensure that sufficient detail is included in the T/Ss for the PRNF reactor trip. |
| | Justification for Chan e These changes are considered to be administrative in nature and intended to clarify the response time testing requirements for the PRNF reactor trip. No operability or surveillance requirements will be reduced as a result of this change. |
| | Anal sis of Si nificant Hazards 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. |
| | Criterion 1 This change is intended to clarify the existing T/S requirements for the PRNF reactor trip, No operability or surveillance requirements have been reduced. We therefore believe the change does not involve a significant increase in the probability or consequences of an accident previously analyzed or a significant reduction in a margin of safety. |
| | to AEP:NRC:1078 Page 2 Criterion 2 The change does not involve physical modifications to the plant or changes in plant operation. The change therefore should not create the possibility of a new or different kind of accident from any previously analyzed or evaluated. |
| | Criterion 3 See Criterion 1 above. |
| | Lastly, 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 which are purely administrative in nature: for example, changes to achieve consistency throughout the T/Ss, correction of errors, or changes in nomenclature. The proposed change only clarifies the present T/S. We are not proposing to reduce any present requirements. For these reasons, we believe that the example cited is applicable and that the proposed change should not involve significant hazards consideration. |
| | |
| | TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME |
| | : 1. Manual Reactor Trip NOT APPLICABLE |
| | : 2. Power Range, Neutron Flux Less than or equal to (High and Low Setpoint) 0.5 seconds |
| | : 3. Power Range, Neutron Flux, High Positive Rate NOT APPLICABLE |
| | : 4. Power Range, Neutron Flux, Less than or equal to High Negative Rate 0.5 seconds* |
| | : 5. Intermediate Range, Neutron Flux NOT APPLICABLE |
| | : 6. Source Range, Neutron Flux NOT APPLICABLE |
| | : 7. Overtemperature delta T Less than or equal to 6.0 seconds |
| | : 8. Overpower delta T NOT APPLICABLE |
| | : 9. Pressurizer Pressure--Low Less than or equal to 1.0 seconds 10.Pressurizer Pressure--High Less than or equal to 1.0 seconds 11.Pressurizer Water Level--High NOT APPLICABLE |
| | * Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel. |
| | COOK NUCLEAR PLANT - UNIT 2 3/4 3-9 AMENDMENT NO. |
| | |
| | Q |
| | ~ ~}} |
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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
kC CE1K PATED D1 BUI3 OY BE M 0~ S TlOY SYSTEM ee REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8904040229 DOC.DATE: 89/03/29 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME . AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co.
RECIP.NAME 'ECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Control Desk) R
SUBJECT:
Application. for amends to Licenses'PR-58 & DPR-74,to I clarify response time testing requirements for PRNFRT.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR TITLE: OR Submittal: General Distribution ENCL SIZE: +R S
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANG,J 5 5 D INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 D NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 1 .
1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E REl FI E '1
-ABSTRACT 1
1 1
1 1
1 NRR/DOEA/TSB OGC/HDS1 RES/DSIR/EIB 11 1 1
1 1
1 0
1 1
EXTERNAL: LPDR 1 1 NRC PDR NSIC 1 1 NAZE K) ALL "RIDS" RECIPIENIS'LEASE S
HELP US K) REDUCE WASTE! COMI'ACZ 'IHE DOCUMENT CONIBDL DESK, RDCM Pl-37 (EXT. 20079) KO ELIMINATE YOUR NME FRY DISTRIBUTION LISTS FOR DOCUHENZS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 20
indiana Michigan Power Company P.O. Box 16631 Coiumbus, OH 43216 ItlAIEMANA MCHE6'AN PWE5k AEP:NRC:1078 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 CLARIFICATION OF RESPONSE TIME TESTING REQUIREMENTS FOR POWER RANGE NEUTRON FLUX REACTOR TRIP U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley 1
March 29, 1989
Dear Dr. Murley:
This letter constitutes an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant. Units 1 and 2. Specifically we are proposing to clarify the response time testing requirements for the power range neutron flux reactor trip. A detailed description of the change, our reasons for requesting the change, and our analyses concerning significant hazards are contained in Attachment 1. Attachment 2 includes the proposed revised T/S pages.
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.
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.
S904040229 S90329 oor PDR ADOCK 05000315 P PDC
Dr. T. E. Murley AEP'NRC:1078 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. P. Al ich Vice President ldp Attachments cc: D. H. Williams, Jr.
W. G ~ Smith, Jr. - Bridgman R. C. Callen G. Charnoff A. B. Davis NRC Resident Inspector - Bridgman G. Bruchmann
ATTACHMENT 1 TO AEP:NRC 1078 REASONS AND 10 CFR 50.92 ANALYSES FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS to AEP:NRC:1078 Page 1 Descri tion of Chan e This letter proposes to clarify the requirements of Table 3.3-2, "Reactor Trip System Instrumentation Response Times," by indicating that the requirements of Functional Unit 2 apply to both the high and low power range neutron flux (PRNF) reactor trip setpoints.
Back round and Reasons for Chan e During a review of our reactor trip system instrumentation time response testing procedures, it was observed that the time response test procedure for the nuclear instrumentation system PRNF reactor trip only included the high setpoint trip. Since credit was taken for the low setpoint trip in the safety analysis for both Units 1 and 2, the low setpoint should have been time response tested. It is believed that the lack of specific detail in the T/Ss regarding the separate setpoints was a contributing factor to the lack of testing, and we are therefore submitting the proposed changes of this letter to ensure that sufficient detail is included in the T/Ss for the PRNF reactor trip.
Justification for Chan e These changes are considered to be administrative in nature and intended to clarify the response time testing requirements for the PRNF reactor trip. No operability or surveillance requirements will be reduced as a result of this change.
Anal sis of Si nificant Hazards 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.
Criterion 1 This change is intended to clarify the existing T/S requirements for the PRNF reactor trip, No operability or surveillance requirements have been reduced. We therefore believe the change does not involve a significant increase in the probability or consequences of an accident previously analyzed or a significant reduction in a margin of safety.
to AEP:NRC:1078 Page 2 Criterion 2 The change does not involve physical modifications to the plant or changes in plant operation. The change therefore should not create the possibility of a new or different kind of accident from any previously analyzed or evaluated.
Criterion 3 See Criterion 1 above.
Lastly, 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 which are purely administrative in nature: for example, changes to achieve consistency throughout the T/Ss, correction of errors, or changes in nomenclature. The proposed change only clarifies the present T/S. We are not proposing to reduce any present requirements. For these reasons, we believe that the example cited is applicable and that the proposed change should not involve significant hazards consideration.
TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME
- 1. Manual Reactor Trip NOT APPLICABLE
- 2. Power Range, Neutron Flux Less than or equal to (High and Low Setpoint) 0.5 seconds
- 3. Power Range, Neutron Flux, High Positive Rate NOT APPLICABLE
- 4. Power Range, Neutron Flux, Less than or equal to High Negative Rate 0.5 seconds*
- 5. Intermediate Range, Neutron Flux NOT APPLICABLE
- 6. Source Range, Neutron Flux NOT APPLICABLE
- 7. Overtemperature delta T Less than or equal to 6.0 seconds
- 8. Overpower delta T NOT APPLICABLE
- 9. Pressurizer Pressure--Low Less than or equal to 1.0 seconds 10.Pressurizer Pressure--High Less than or equal to 1.0 seconds 11.Pressurizer Water Level--High NOT APPLICABLE
- Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.
COOK NUCLEAR PLANT - UNIT 2 3/4 3-9 AMENDMENT NO.
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