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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:CATEGORY 1 1 REGULAT Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)DOCKET¹05000315 05000316 ACCESSION NBR:9809220081, DOC.DATE: 98/09/14 NOTARIZED: | | {{#Wiki_filter:CATEGORY 1 1 |
| YES FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 50;316 Ponald C.Cook Nuclear Power Plant, Unit 2, Indiana M AUTH.NAME AUTHOR AFFILIATION POWERS,R.P. | | REGULAT Y INFORMATION DISTRIBUTIO SYSTEM (RIDS) |
| 'Induna Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk) | | ACCESSION NBR:9809220081, DOC.DATE: 98/09/14 NOTARIZED: YES DOCKET ¹ FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50;316 Ponald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION POWERS,R.P. 'Induna Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application for amends to licenses DPR-58 8 DPR-74,revising TS page 3/4 5-6.D1STRZBUT10N CODE: A'OOZD CORTES RECEZVED:LTR | | Application for amends to licenses DPR-58 8 DPR-74,revising TS page 3/4 5-6. |
| )ENCL I SZEE: P 1 TITLE: OR Submittal: | | A D1STRZBUT10N CODE: A'OOZD CORTES RECEZVED:LTR ) ENCL I SZEE: P TITLE: OR Submittal: General Distribution 1 |
| General Distribution NOTES: A T, E RECIPIENT ID CODE/NAME PD3-3 LA STANG,J INTERNA ILE CENTER 01 NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD3-3 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 0 D'NOTE TO ALL"RIDS" REC1PIENTS: | | T, NOTES: E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 1 0 STANG,J 1 1 INTERNA ILE CENTER 01 1 1 NRR/DE/ECGB/A 1 1 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC NRC PDR 1 1 D |
| PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRZBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12 I C indiana Michigan~Power Company 500 Circle Drive Buchanan, Ml 491071373 September 14, 1998 AEP:NRC:1274 10 CFR 50.92 Docket Nos.: 50-315 50-316 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop 0-Pl-17 Washington, D.C.20555-0001 Gentlemen: | | NOTE TO ALL "RIDS" REC1PIENTS: |
| DONALD C.COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION AMENDMENT SAFETY INJECTION PUMP RUNOUT FLOW LIMITS This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss)for Cook Nuclear Plant units 1 and 2.This amendment will change the runout limits for a safety injection pump to 675 gpm unless the pump is specifically tested to a higher flow rate not exceeding 700 gpm.Background information relevant to the T/S change and our analyses concerning significant hazards considerations are contained in attachment 1 to this letter.Attachment 2 contains the current T/S pages, marked-up to reflect the proposed change.The proposed revised T/S pages are contained in attachment 3.This submittal proposes a change to T/S page 3/4 5-6 for both unit 1 and 2.The proposed change will not result in a significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite or a significant increase in individual or cumulative occupational radiation exposure.The proposed change has been reviewed and approved by the plant nuclear safety review committee and the nuclear safety and design review committee.
| | PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRZBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12 |
| We request that the approved amendment be effective thirty days from issuance.980'7220081 9809'X4 PDR ADOCK 05000815 P'OR U.S~Nuclear Regulatory Commission Page 2 AEP:NRC:1274 In accordance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and the Michigan Department of Public Health.R.P.Powers Vice President SWORN TO AND SUBSCRIBED BEFORE ME~l~san*i INDE Notary Publi My commission expires l 2Z 01/jmc Attachments c: J.A.Abramson, w/attachments J.L.Caldwell, w/attachments MDEQ-DW&RPD, w/attachments NRC Resident Inspector, w/attachments J.R.Sampson, w/attachments sL C
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| ~~ATTACHMENT 1 TO AEP:NRC:1274 SUPPORTING ANALYSES FOR AMENDMENT TO THE TECHNICAL SPECIFICATIONS SAFETY INJECTION PUMP RUNOUT FLOW LIMITS Attachment 1 to AEP:NRC:1274 Page 1 Back round Amendment numbers 84 (6/24/85)and 64 (6/18/84), respectively, to the unit 1 and unit 2.technical specifications (T/Ss)incorporated a change to the allowable safety injection (SI)pump runout limits in T/S 4.5.2.h.The change raised the permissible runout flow of a single SI pump from 650 gpm to 700 gpm.The pump runout flow changes were necessitated by physical changes to the SI pump miniflow recirculation lines.These physical changes increased miniflow capacity from 30 gpm to approximately 60 gpm and it was anticipated that the increased miniflow would make it difficult to achieve all of the SI pump design flow objectives without exceeding the 650 gpm runout limit existing at that time.The justification for the change from 650 to 700 gpm was based on vendor testing (Dresser Industries) of a single Cook Nuclear Plant replacement safety injection pump and a spare element.The testing established safe pump operation up to a maximum flow of 700 gpm.We confirmed that the available net positive suction head to the SI pumps, as installed at the plant, was greater than that required to safely achieve 700 gpm during the vendor testing.Therefore, we believed this testing was also applicable to the three (untested) installed pumps.In 1991, we received correspondence from Westinghouse indicating that the generic runout limits for Pacific 2" JTCH pumps was 675 gpm unless each specific pump was tested to a higher flow.At our request, Dresser reviewed the pump runout limits for Cook Nuclear Plant.Based on their review, Dresser concluded the following:
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| 1)for the specific replacement pump and spare element previously tested by them, the 700 gpm runout limit remained applicable (this applies to the unit 2 north pump);and 2)for other (untested)
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| SI pumps, Dresser's position was to abide by the general Westinghouse limit of 675 gpm (this applies to both unit 1 pumps and the unit 2 south pump).They indicated that manufacturing tolerances in sand cast impellers and material changes in the pump casing (of the tested replacement pump)could result in test variations that limit applicability of the testing between pumps.Dresser also indicated that the generic limit of 675 gpm could be increased for the three untested pumps, with appropriate in place or vendor testing.Review of SI pump flow balancing data indicated that proper balancing could be achieved without exceeding 675 gpm for the three pumps that had not been specifically tested for higher flows.Procedure 12 EHP 4030 STP~208SIg U1&U2 ECCS FLOW BALANCE SAFETY INJECTlON SYSTEM", was changed to administratively limit flow of the three untested pumps to 675 gpm.Based on procedural controls for limiting runout flow of the three untested pumps, we concluded in 1992 that the intent of T/S 4.5.2.h was being met and that a change to the T/Ss was not necessary.
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| However, additional recent review has concluded that a change to the T/S should have been initiated.
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| This submittal provides the necessary change and also clarifies the basis for setting the SI pump runout limits.The bases clarification describes why the injection lineup is more conservative than the sump recirculation lineup (when the RHR pumps are providing a suction pressure boost)for potential SI pump runout.This is due to splitting of the SI
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| Attachment 1 to AEP:NRC: 1274 Page 2 trains during circulation, resulting in a higher system resistance than with a-single SI pump injecting to all four reactor coolant loops.Descri tion of Amendment Re uest Technical specification 4.5.2.h (SI system single pump)is being changed to require the maximum permitted runout flow rate for a SI pump be restricted to 675 gpm unless the pump is individually qualified to a higher flow rate of up to 700 gpm.Currently, T/S 4.5.2.h recognizes a runout flow rate of 700 gpm for each of the SI pumps.The basis is being clarified to describe why the injection lineup during flow balancing is the minimum resistance configuration for runout considerations. | | I C indiana Michigan Power Company |
| Justification for Amendment The proposed amendment is necessary to correct a technical discrepancy in the runout flow limit for safety injection pumps that, have not been specifically tested to the limit currently allowed by T/S 4.5.2.h.Basis for No Significant Hazards Determination In accordance with 10 CFR 50.92, this proposed amendment does not involve a significant hazard consideration if it does not: 1)Involve a significant increase in the probability or consequences of an accident previously evaluated. | | ~ |
| The proposed reduction in the SI pump runout flow does not increase the probability of occurrence of anypreviously evaluated accident because the SI pumps are not considered to be accident initiators. | | 500 Circle Drive Buchanan, Ml 491071373 AEP:NRC:1274 September 14, 1998 10 CFR 50.92 Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop 0-Pl-17 Washington, D. C. 20555-0001 Gentlemen: |
| In addition, flow balancing performed at Cook Nuclear Plant has proven the ability to deliver the minimum T/S flow o f 300 gpm to each pair o f cold leg injection points without exceeding the 675 gpm (or 700 gpm)pump runout limits.Therefore, the emergency core cooling system performance objectives of 10 CFR 50.46 are not impacted and this change does not involve a significant increase in the consequences of an accident previously evaluated. | | DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION AMENDMENT SAFETY INJECTION PUMP RUNOUT FLOW LIMITS This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss) for Cook Nuclear Plant units 1 and 2. This amendment will change the runout limits for a safety injection pump to 675 gpm unless the pump is specifically tested to a higher flow rate not exceeding 700 gpm. |
| 2)Create the possibility of a new or different kind of accident from any accident previously evaluated. | | Background information relevant to the T/S change and our analyses concerning significant hazards considerations are contained in attachment 1 to this letter. Attachment 2 contains the current T/S pages, marked-up to reflect the proposed change. The proposed revised T/S pages are contained in attachment 3. |
| This proposed change imposes a generic limit on maximum allowable flow for untested SI pumps.No physical system changes or changes in operating modes are being made that could introduce new or different kinds of accidents from those previously evaluated. | | This submittal proposes a change to T/S page 3/4 5-6 for both unit 1 and 2. The proposed change will not result in a significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite or a significant increase in individual or cumulative occupational radiation exposure. |
| As discussed in (1)above, the SI pumps are not considered accident initiators, and this status is not affected by the change to the SI pump runout limits. | | The proposed change has been reviewed and approved by the plant nuclear safety review committee and the nuclear safety and design review committee. We request that the approved amendment be effective thirty days from issuance. |
| Attachment 1 to AEP:NRC:1274 Page 3 3)Involve a significant reduction in a margin of safety.This change reflects a reduced maximum single pump flow to be observed during flow balancing of the SI system.Flow balance testing at Cook Nuclear Plant has demonstrated the ability to meet SI flow requirements while maintaining an adequate margin to the revised lower runout limits being proposed by this submittal.
| | 980'7220081 9809'X4 PDR P |
| Because the minimum required SI flow delivered to the core has not been reduced by this change, the change does not involve a reduction in a margin of safety.Based on the preceding, the evaluation concluded that the proposed change to the SI pump runout limits does not involve a significant hazards consideration as defined in 10 CFR 50.92. | | ADOCK |
| ATTACHMENT 2 TO AEP:NRC:1274 CURRENT PAGES MARKED-UP TO SHOW PROPOSED CHANGES TO THE DONALD CD COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION SAFETY INJECTION PUMP RUNOUT FLOW LIMITS UNIT NO.1}} | | 'OR05000815 |
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| | U. S ~ Nuclear Regulatory Commission AEP:NRC:1274 Page 2 In accordance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and the Michigan Department of Public Health. |
| | R. P. Powers Vice President SWORN TO AND SUBSCRIBED BEFORE ME |
| | ~l ~san*i INDE Notary Publi My commission expires l 2Z 01 |
| | /jmc Attachments c: J. A. Abramson, w/attachments J. L. Caldwell, w/attachments MDEQ - DW & RPD, w/attachments NRC Resident Inspector, w/attachments J. R. Sampson, w/attachments |
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| | ATTACHMENT 1 TO AEP:NRC:1274 SUPPORTING ANALYSES FOR AMENDMENT TO THE TECHNICAL SPECIFICATIONS SAFETY INJECTION PUMP RUNOUT FLOW LIMITS to AEP:NRC:1274 Page 1 Back round Amendment numbers 84 (6/24/85) and 64 (6/18/84), respectively, to the unit 1 and unit 2.technical specifications (T/Ss) incorporated a change to the allowable safety injection (SI) pump runout limits in T/S 4.5.2.h. The change raised the permissible runout flow of a single SI pump from 650 gpm to 700 gpm. The pump runout flow changes were necessitated by physical changes to the SI pump miniflow recirculation lines. These physical changes increased miniflow capacity from 30 gpm to approximately 60 gpm and it it was difficult to anticipated that the increased miniflow would make achieve all of the SI pump design flow objectives without exceeding the 650 gpm runout limit existing at that time. The justification for the change from 650 to 700 gpm was based on vendor testing (Dresser Industries) of a single Cook Nuclear Plant replacement safety injection pump and a spare element. The testing established safe pump operation up to a maximum flow of 700 gpm. We confirmed that the available net positive suction head to the SI pumps, as installed at the plant, was greater than that required to safely achieve 700 gpm during the vendor testing. Therefore, we believed this testing was also applicable to the three (untested) installed pumps. |
| | In 1991, we received correspondence from Westinghouse indicating that the generic runout limits for Pacific 2" JTCH pumps was 675 gpm unless each specific pump was tested to a higher flow. At our request, Dresser reviewed the pump runout limits for Cook Nuclear Plant. Based on their review, Dresser concluded the following: 1) for the specific replacement pump and spare element previously tested by them, the 700 gpm runout limit remained applicable (this applies to the unit 2 north pump); and 2) for other (untested) SI pumps, Dresser's position was to abide by the general Westinghouse limit of 675 gpm (this applies to both unit 1 pumps and the unit 2 south pump). They indicated that manufacturing tolerances in sand cast impellers and material changes in the pump casing (of the tested replacement pump) could result in test variations that limit applicability of the testing between pumps. Dresser also indicated that the generic limit of 675 gpm could be increased for the three untested pumps, with appropriate in place or vendor testing. Review of SI pump flow balancing data indicated that proper balancing could be achieved without exceeding 675 gpm for the three pumps that had not been specifically tested for higher flows. Procedure 12 EHP 4030 STP 208SIg |
| | ~ U1 & U2 ECCS FLOW BALANCE SAFETY INJECTlON SYSTEM", was changed to administratively limit flow of the three untested pumps to 675 gpm. |
| | Based on procedural controls for limiting runout flow of the three untested pumps, we concluded in 1992 that the intent of T/S 4.5.2.h was being met and that a change to the T/Ss was not necessary. |
| | However, additional recent review has concluded that a change to the T/S should have been initiated. This submittal provides the necessary change and also clarifies the basis for setting the SI pump runout limits. The bases clarification describes why the injection lineup is more conservative than the sump recirculation lineup (when the RHR pumps are providing a suction pressure boost) for potential SI pump runout. This is due to splitting of the SI |
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| | to AEP:NRC: 1274 Page 2 trains during circulation, resulting in a higher system resistance than with a- single SI pump injecting to all four reactor coolant loops. |
| | Descri tion of Amendment Re uest Technical specification 4.5.2.h (SI system single pump) is being changed to require the maximum permitted runout flow rate for a SI pump be restricted to 675 gpm unless the pump is individually qualified to a higher flow rate of up to 700 gpm. Currently, T/S 4.5.2.h recognizes a runout flow rate of 700 gpm for each of the SI pumps. The basis is being clarified to describe why the injection lineup during flow balancing is the minimum resistance configuration for runout considerations. |
| | Justification for Amendment The proposed amendment is necessary to correct a technical discrepancy in the runout flow limit for safety injection pumps that, have not been specifically tested to the limit currently allowed by T/S 4.5.2.h. |
| | Basis for No Significant Hazards Determination In accordance with 10 CFR 50.92, this proposed does not involve a significant hazard consideration if itamendment does not: |
| | : 1) Involve a significant increase in the probability or consequences of an accident previously evaluated. |
| | The proposed reduction in the SI pump runout flow does not increase the probability of occurrence of any previously evaluated accident because the SI pumps are not considered to be accident initiators. In addition, flow balancing performed at Cook Nuclear Plant has proven the ability to deliver the minimum T/S flow o f 300 gpm to each pair o f cold leg injection points without exceeding the 675 gpm (or 700 gpm) pump runout limits. Therefore, the emergency core cooling system performance objectives of 10 CFR 50.46 are not impacted and this change does not involve a significant increase in the consequences of an accident previously evaluated. |
| | : 2) Create the possibility of a new or different kind of accident from any accident previously evaluated. |
| | This proposed change imposes a generic limit on maximum allowable flow for untested SI pumps. No physical system changes or changes in operating modes are being made that could introduce new or different kinds of accidents from those previously evaluated. As discussed in (1) above, the SI pumps are not considered accident initiators, and this status is not affected by the change to the SI pump runout limits. |
| | to AEP:NRC:1274 Page 3 |
| | : 3) Involve a significant reduction in a margin of safety. |
| | This change reflects a reduced maximum single pump flow to be observed during flow balancing of the SI system. Flow balance testing at Cook Nuclear Plant has demonstrated the ability to meet SI flow requirements while maintaining an adequate margin to the revised lower runout limits being proposed by this submittal. Because the minimum required SI flow delivered to the core has not been reduced by this change, the change does not involve a reduction in a margin of safety. |
| | Based on the preceding, the evaluation concluded that the proposed change to the SI pump runout limits does not involve a significant hazards consideration as defined in 10 CFR 50.92. |
| | |
| | ATTACHMENT 2 TO AEP:NRC:1274 CURRENT PAGES MARKED-UP TO SHOW PROPOSED CHANGES TO THE DONALD CD COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION SAFETY INJECTION PUMP RUNOUT FLOW LIMITS |
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| | UNIT NO. 1}} |
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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
CATEGORY 1 1
REGULAT Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)
ACCESSION NBR:9809220081, DOC.DATE: 98/09/14 NOTARIZED: YES DOCKET ¹ FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50;316 Ponald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION POWERS,R.P. 'Induna Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
Application for amends to licenses DPR-58 8 DPR-74,revising TS page 3/4 5-6.
A D1STRZBUT10N CODE: A'OOZD CORTES RECEZVED:LTR ) ENCL I SZEE: P TITLE: OR Submittal: General Distribution 1
T, NOTES: E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 1 0 STANG,J 1 1 INTERNA ILE CENTER 01 1 1 NRR/DE/ECGB/A 1 1 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC NRC PDR 1 1 D
NOTE TO ALL "RIDS" REC1PIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRZBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12
I C indiana Michigan Power Company
~
500 Circle Drive Buchanan, Ml 491071373 AEP:NRC:1274 September 14, 1998 10 CFR 50.92 Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop 0-Pl-17 Washington, D. C. 20555-0001 Gentlemen:
DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION AMENDMENT SAFETY INJECTION PUMP RUNOUT FLOW LIMITS This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss) for Cook Nuclear Plant units 1 and 2. This amendment will change the runout limits for a safety injection pump to 675 gpm unless the pump is specifically tested to a higher flow rate not exceeding 700 gpm.
Background information relevant to the T/S change and our analyses concerning significant hazards considerations are contained in attachment 1 to this letter. Attachment 2 contains the current T/S pages, marked-up to reflect the proposed change. The proposed revised T/S pages are contained in attachment 3.
This submittal proposes a change to T/S page 3/4 5-6 for both unit 1 and 2. The proposed change will not result in a significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite or a significant increase in individual or cumulative occupational radiation exposure.
The proposed change has been reviewed and approved by the plant nuclear safety review committee and the nuclear safety and design review committee. We request that the approved amendment be effective thirty days from issuance.
980'7220081 9809'X4 PDR P
ADOCK
'OR05000815
U. S ~ Nuclear Regulatory Commission AEP:NRC:1274 Page 2 In accordance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and the Michigan Department of Public Health.
R. P. Powers Vice President SWORN TO AND SUBSCRIBED BEFORE ME
~l ~san*i INDE Notary Publi My commission expires l 2Z 01
/jmc Attachments c: J. A. Abramson, w/attachments J. L. Caldwell, w/attachments MDEQ - DW & RPD, w/attachments NRC Resident Inspector, w/attachments J. R. Sampson, w/attachments
sL C
~ ~
ATTACHMENT 1 TO AEP:NRC:1274 SUPPORTING ANALYSES FOR AMENDMENT TO THE TECHNICAL SPECIFICATIONS SAFETY INJECTION PUMP RUNOUT FLOW LIMITS to AEP:NRC:1274 Page 1 Back round Amendment numbers 84 (6/24/85) and 64 (6/18/84), respectively, to the unit 1 and unit 2.technical specifications (T/Ss) incorporated a change to the allowable safety injection (SI) pump runout limits in T/S 4.5.2.h. The change raised the permissible runout flow of a single SI pump from 650 gpm to 700 gpm. The pump runout flow changes were necessitated by physical changes to the SI pump miniflow recirculation lines. These physical changes increased miniflow capacity from 30 gpm to approximately 60 gpm and it it was difficult to anticipated that the increased miniflow would make achieve all of the SI pump design flow objectives without exceeding the 650 gpm runout limit existing at that time. The justification for the change from 650 to 700 gpm was based on vendor testing (Dresser Industries) of a single Cook Nuclear Plant replacement safety injection pump and a spare element. The testing established safe pump operation up to a maximum flow of 700 gpm. We confirmed that the available net positive suction head to the SI pumps, as installed at the plant, was greater than that required to safely achieve 700 gpm during the vendor testing. Therefore, we believed this testing was also applicable to the three (untested) installed pumps.
In 1991, we received correspondence from Westinghouse indicating that the generic runout limits for Pacific 2" JTCH pumps was 675 gpm unless each specific pump was tested to a higher flow. At our request, Dresser reviewed the pump runout limits for Cook Nuclear Plant. Based on their review, Dresser concluded the following: 1) for the specific replacement pump and spare element previously tested by them, the 700 gpm runout limit remained applicable (this applies to the unit 2 north pump); and 2) for other (untested) SI pumps, Dresser's position was to abide by the general Westinghouse limit of 675 gpm (this applies to both unit 1 pumps and the unit 2 south pump). They indicated that manufacturing tolerances in sand cast impellers and material changes in the pump casing (of the tested replacement pump) could result in test variations that limit applicability of the testing between pumps. Dresser also indicated that the generic limit of 675 gpm could be increased for the three untested pumps, with appropriate in place or vendor testing. Review of SI pump flow balancing data indicated that proper balancing could be achieved without exceeding 675 gpm for the three pumps that had not been specifically tested for higher flows. Procedure 12 EHP 4030 STP 208SIg
~ U1 & U2 ECCS FLOW BALANCE SAFETY INJECTlON SYSTEM", was changed to administratively limit flow of the three untested pumps to 675 gpm.
Based on procedural controls for limiting runout flow of the three untested pumps, we concluded in 1992 that the intent of T/S 4.5.2.h was being met and that a change to the T/Ss was not necessary.
However, additional recent review has concluded that a change to the T/S should have been initiated. This submittal provides the necessary change and also clarifies the basis for setting the SI pump runout limits. The bases clarification describes why the injection lineup is more conservative than the sump recirculation lineup (when the RHR pumps are providing a suction pressure boost) for potential SI pump runout. This is due to splitting of the SI
to AEP:NRC: 1274 Page 2 trains during circulation, resulting in a higher system resistance than with a- single SI pump injecting to all four reactor coolant loops.
Descri tion of Amendment Re uest Technical specification 4.5.2.h (SI system single pump) is being changed to require the maximum permitted runout flow rate for a SI pump be restricted to 675 gpm unless the pump is individually qualified to a higher flow rate of up to 700 gpm. Currently, T/S 4.5.2.h recognizes a runout flow rate of 700 gpm for each of the SI pumps. The basis is being clarified to describe why the injection lineup during flow balancing is the minimum resistance configuration for runout considerations.
Justification for Amendment The proposed amendment is necessary to correct a technical discrepancy in the runout flow limit for safety injection pumps that, have not been specifically tested to the limit currently allowed by T/S 4.5.2.h.
Basis for No Significant Hazards Determination In accordance with 10 CFR 50.92, this proposed does not involve a significant hazard consideration if itamendment does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed reduction in the SI pump runout flow does not increase the probability of occurrence of any previously evaluated accident because the SI pumps are not considered to be accident initiators. In addition, flow balancing performed at Cook Nuclear Plant has proven the ability to deliver the minimum T/S flow o f 300 gpm to each pair o f cold leg injection points without exceeding the 675 gpm (or 700 gpm) pump runout limits. Therefore, the emergency core cooling system performance objectives of 10 CFR 50.46 are not impacted and this change does not involve a significant increase in the consequences of an accident previously evaluated.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
This proposed change imposes a generic limit on maximum allowable flow for untested SI pumps. No physical system changes or changes in operating modes are being made that could introduce new or different kinds of accidents from those previously evaluated. As discussed in (1) above, the SI pumps are not considered accident initiators, and this status is not affected by the change to the SI pump runout limits.
to AEP:NRC:1274 Page 3
- 3) Involve a significant reduction in a margin of safety.
This change reflects a reduced maximum single pump flow to be observed during flow balancing of the SI system. Flow balance testing at Cook Nuclear Plant has demonstrated the ability to meet SI flow requirements while maintaining an adequate margin to the revised lower runout limits being proposed by this submittal. Because the minimum required SI flow delivered to the core has not been reduced by this change, the change does not involve a reduction in a margin of safety.
Based on the preceding, the evaluation concluded that the proposed change to the SI pump runout limits does not involve a significant hazards consideration as defined in 10 CFR 50.92.
ATTACHMENT 2 TO AEP:NRC:1274 CURRENT PAGES MARKED-UP TO SHOW PROPOSED CHANGES TO THE DONALD CD COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATION SAFETY INJECTION PUMP RUNOUT FLOW LIMITS
UNIT NO. 1
