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| {{#Wiki_filter:REGULATORY ENFORMATION DISTRIBUTION SYSTEM (RIOS)ACCESSION NBR:8105290360 DOC~DATE: 81/05/26 NOTARIZED: | | {{#Wiki_filter:REGULATORY ENFORMATION DISTRIBUTION SYSTEM (RIOS) |
| NO DOCKET FACILi 50 315 Oonal d C Cook Nuclear Power Plant>Uni t 1 i Indi ana K~>OA>50 316 Donald C~Cook hucl.ear Power Plant>Unit 2P Indiana 8-500031.AUTH'AME AUTHOR AFFILIATION HUNTERPR~8'ndiana 8 Michigan Electric Co~REC IP~NAME RECIPIENT AFFILIATION SUBJFCT: Applicdtion for~amend to OL<changing App A of Tech Specs~DISTRIBUTION CODE: AOO'IS COPIES RECEIVED:LTR J.ENCL S SIZE::.5+T'ITLE.: General Distr ibution for af ter Issuance of Oper ating License RECIPIENT ID CODE/NAME'OTES:ICE:3 cooies all material~Send 3 copies-'of al 1 material to ICE~W/C4ucl-4 l~40~REC IP I ENT COPIES ID CODE/NAME LTTR ENCL ACTION!VARGA E 8~04 13.13 COPTES LTTR ENCL 05000315 05000316 INTERNAL: D/OIRgHUM FACOS IaE..06 OELO 11 RAO ASMT BR 1 1 2 2 1 0 1 1 OIR P DI V OF LIC NRC PDR'2 0 A-E4'S R 1 0 G FIQ 01 1 1 1 1 0 1 EXTERNAL'CRS NSIC 09.05 fe 16 1 1 LPOR 03 1 1 wl TOTAL NUMBER'F COPIES REQUIRED LTTR''NCL i | | ACCESSION NBR:8105290360 DOC ~ DATE: 81/05/26 NOTARIZED: NO DOCKET FACILi50 315 Oonal d C Cook Nuclear Power Plant> Uni t 1 i Indi ana K ~>OA> |
| INDIANA Ilt MICHIGAN ELECTRIC COMPANY P.O.BOX 18 BOWLIN G GR E EN STATION NEW YORK, N.Y.10004 May 26, 1981 AEP:NRC:0372 Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 TECHNICAL SPECIFICATIONS CHANGE REQUEST~]g/@a.a.l't'ai',pg tg 8 U~g~'ib Mr.Harold R.Denton, Director'ffice of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
| | 50 316 Donald C ~ Cook hucl.ear Power Plant> Unit 2P Indiana 8 -500031. |
| | AUTH'AME HUNTERPR ~ 8 REC |
| | 'ndiana IP ~ NAME AUTHOR AFFILIATION 8 Michigan RECIPIENT AFFILIATION Electric Co ~ |
| | SUBJFCT: Applicdtion for ~ |
| | amend to OL<changing App A of Tech Specs ~ |
| | DISTRIBUTION CODE: AOO'IS COPIES RECEIVED:LTR J. ENCL S SIZE::. 5+ |
| | T'ITLE.: General Distr ibution for af ter Issuance of Oper ating License cooies all material ~ 05000315 Send 3 copies-'of al material to ICE ~ |
| | 1 05000316 W/C4ucl- 4 l~ 40~ CODE/NAME'OTES:ICE:3 REC IP I ENT COPIES RECIPIENT COPTES ID CODE/NAME LTTR ENCL ID LTTR ENCL ACTION! VARGA E 8 ~ 04 13 . 13 IaE.. |
| | INTERNAL: D/OIRgHUM FACOS OELO 06 11 1 |
| | 2 1 |
| | 1 2 |
| | 0 OIR P DI V OF LIC NRC 0 A-PDR'2 E4'S R 1 0 1 |
| | 1 1 |
| | 1 0 |
| | RAO ASMT BR 1 1 G FIQ 01 1 EXTERNAL'CRS 09. fe 16 LPOR 03 1 1 NSIC 05 1 1 wl TOTAL NUMBER'F COPIES REQUIRED LTTR' 'NCL |
|
| |
|
| ==Dear Mr.Denton:==
| | i INDIANA Ilt MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GR E EN STATION NEW YORK, N. Y. 10004 May 26, 1981 AEP:NRC:0372 a. |
| This letter and its attachments request changes in several of the Appendix'A'echnical Specifications for the Donald C.Cook Nuclear Plant Unit Nos.1 and 2.Attachment 1 is the description of'he changes.Attachment 2 contains the revised Technical Specification pages.A number of these changes are editorial.
| | ~]g/@ |
| All changes have been indicated by a vertical line on the right hand side of the page.We request that the NRC file and process this Technical Specification change package as a single amendment.
| | Donald C. Cook Nuclear Plant Unit Nos. |
| These proposed Technical Specifications have been reviewed and approved by the Plant Nuclear Safety CoraIIittee.
| | Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 1 and 2 U~g |
| The result of these reviews is that these proposed revisions will not adversely affect the health and safety of the public.Change Nos.4, 5 and 6'ave been reviewed by the AEPSC Nuclear Safety and Design Review Committee (NSDRC).The NSDRC concurs with the Plant PNSRC findings.The remaining changes will be reviewed at the next meeting of the NSDRC scheduled for June 9, 1981.
| | ~ |
| Mr.Harold R.Denton AEP:NRC:0372 SeVen proposed Technical Specification revisions are contained in this submittal; four editorial in nature.Change Nos.4 and 7 are considered to be Class II amendments
| | a .l't'ai',pg tg 8 |
| ($1,200 fee each)and change No.6 is considered to be a Class II'I amendment'$
| | TECHNICAL SPECIFICATIONS CHANGE REQUEST |
| 4,000.00 fee).Class I duplicate fees also apply for change Nos.4, 6 and 7:.Accordingly, attached is a check in the amount of$7,600.00 for NRC processing of the aforementioned requests.Very truly yours, Vice President cc: John E.Dolan-Columbus R.C.Callen G.Charnoff R.M.Jurgensen D.V.Shaller-Bridgman Region III Resident Inspector 9 Cook Plant-Bridgman ATTACHMENT 1 TO AEP:NRC:0372 Technical S ecification Chan'e Descri'tions | | 'ib Mr. Harold R. Denton, Director of Nuclear Reactor Regulation'ffice U. S. Nuclear Regulatory Commission Washington, D. C. 20555 |
| ~Ch N.1 (EC(Unit No.1-Page 3/4 8-8-Section 3.8.2.3.Under the definitions of the two D.C.bus trains, the second one should be changed from AB to CD.Cch¹N.E (EC(Unit Ho.2-Pages 3/4 8-9 and 3/4 8-10;Section 4.8.2.3.2d In item (d), the table number for-battery emergency.
| | |
| loads must be changed to 4-.8-1A.This revision is due to the fact that currently there are two tables numbered"Table 4.8.1".~Ch N.1 (EC(Unit 1;Page 1-7;Table 1.2'.Unit 2;Page 1-8, Table 1.2 In Table 1.2 of both units, frequence notations of the surveillance scheduling will be specified as a specific number of days whenever the frequency is greater than 24 hours.The words"6 months" and"18 months" will be revised to read"184 days" and"549 days" respectively.
| | ==Dear Mr. Denton:== |
| This terminology conforms to ASME boiler and pressure vessel code, Section III.Chan e Ho.4 Unit 1;page 3/4 2-2;Section 3.2.1 Unit 2;Page 3/4 2-2;Section 3.2.1 As presently written, Specification 3.2.1 requires that a Licensee Event Report (LER)be submitted whenever the Axial Flux Difference (AFD)exceeds the target AFD by more than+5%regardless of the cumuiattve penalty deviation.
| | |
| In Section 3.2.1 of the bases it is clearly stated that the use of control rods can'be expected, in the majority of instances, to cause the actual AFD to differ from the target AFD by more than+55.~c c'h 1~~~~
| | This letter and its attachments request changes in several of the Appendix 'A'echnical Specifications for the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2. Attachment 1 is the description Attachment 2 contains the revised Technical Specification of'he changes. |
| It is our understanding that the intent of Specification 3.2.1 is to re-quire LER submittal only in those instances when the cumulative penalty deviation exceeds, the allowable values specified in the action statement of the specification.
| | pages. A number of these changes are editorial. All changes have been indicated by a vertical line on the right hand side of the page. We request that the NRC file and process this Technical Specification change package as a single amendment. |
| However, our present.Specification 3.2.1 does not reflect this understanding.
| | These proposed Technical Specifications have been reviewed and approved by the Plant Nuclear Safety CoraIIittee. The result of these reviews is that these proposed revisions will not adversely affect the health and safety of the public. Change Nos. 4, 5 and 6 |
| In order to clarify the requirements of the specification and to minimize submittal of unnecessary LERs, we are re-questing that a Section 3.2.l.d be added to the existing AFD specification.
| | 'ave been reviewed by the AEPSC Nuclear Safety and Design Review Committee (NSDRC). The NSDRC concurs with the Plant PNSRC findings. |
| The-revised Technical Specification pages reflect this proposed change.Unit 2;Page 3/4 l-ll;Section 4.1.2.3 The centrifugal charging pumps, when=tested on recirculation flow during modes 5 and 6,, must develop a discharge pressure 2390 psig.The 15 psi pressure difference between discharge pressures of the pump during Modes 5 and 6 and during Modes 1-4-is-due-to a.difference.in-the'Volume Control Tank (VCT)pressure in those modes.This was reflected in the Unit 1 Technical Specifications. | | The remaining changes will be reviewed at the next meeting of the NSDRC scheduled for June 9, 1981. |
| earlier and is now being revised accordingly, in the Unit 2 Technical Specification. | | |
| Chan e No.5 Unit 1;Page 3/4 6-35;Section 4.6.5.6 Unit 2;Page 3/4 6-44;Section 4.6.5.6 The intent of the Ceq fan motor current surveillance is to check for disengaged drive shafts, broken fan blades, frozen or bad bearings, and other malfunctions in the fan-motor system which would cause a significant deviation from the normal motor load.Our review o surveillance test data indicates that the average current observed during tests is less than 56 amperes and the range of deviations under normal yet variable operating conditions.is slightly greater than 10 amperes.Me are therefore requesting a change to Specification 4.6.5.6.b to read: "b.Verifying that with the return air fan dampers closed, the fan motor current is 56+10 A'1PS when the fan speed is 880+20 RPM.This envelope would bound all normal operating readings and ensure that the intent of the Specification, to detect an inoperable system, is met." | | Mr. Harold R. Denton AEP:NRC:0372 SeVen proposed Technical Specification revisions are contained in this submittal; four editorial in nature. Change Nos. 4 and 7 are considered to be Class II amendments ($ 1,200 fee each) and change No. 6 is considered to be a Class II'I amendment'$ 4,000.00 fee). Class I duplicate fees also apply for change Nos. 4, 6 and 7:. Accordingly, attached is a check in the amount of $ 7,600.00 for NRC processing of the aforementioned requests. |
| Chan e No.7 Unit 1;Page 3/4 1-15;Section 3.1.2.7.and 4.1.2.7 Unit 2;Page 3/4 1-15;Section D.1.2.7 and 4.1.2.7 The Technical Specifications require the refueling water storage tank borated water solution temperature be maintained at 70oF or above in Unit 1 and 80oF or above in Unit 2, when it is to be used as a borated water source in Modes 5 and 6.This temperature can be very difficult to maintain when adding cool water to the RWST by blending following draining of the tank for refueling purposes.Since the present solution temperature limits are derived from emergency core cooling requirements, this high temperature limit should only apply in Modes 1, 2, 3 and 4 which is covered by Technical Specifications 3.1.2.8 and 3.5.5.It is therefore requested that the minimum tem-perature limit for Modes 5 and 6 be returned to its original value of 35.oF}} | | Very truly yours, Vice President cc: John E. Dolan - Columbus R. C. Callen G. Charnoff R. M. Jurgensen D. V. Shaller - Bridgman Region III Resident Inspector 9 Cook Plant - Bridgman |
| | |
| | ATTACHMENT 1 TO AEP:NRC:0372 Technical S ecification Chan 'e Descri'tions |
| | ~Ch N . 1 (EC( |
| | Unit No. 1 - Page 3/4 8 Section 3.8.2.3. |
| | Under the definitions of the two D. C. bus trains, the second one should be changed from AB to CD. |
| | Cch¹N. E (EC( |
| | Unit Ho. 2 - Pages 3/4 8-9 and 3/4 8-10; Section 4.8.2.3.2d In item (d), the table number for-battery emergency. loads must be changed to 4-.8-1A. This revision is due to the fact that currently there are two tables numbered "Table 4.8.1". |
| | ~Ch N . 1 (EC( |
| | Unit 1; Page 1-7; Table 1.2'. |
| | Unit 2; Page 1-8, Table 1.2 In Table 1.2 of both units, frequence notations of the surveillance scheduling will be specified as a specific number of days whenever the frequency is greater than 24 hours. The words "6 months" and "18 months" will be revised to read "184 days" and "549 days" respectively. This terminology conforms to ASME boiler and pressure vessel code, Section III. |
| | Chan e Ho. 4 Unit 1; page 3/4 2-2; Section 3.2.1 Unit 2; Page 3/4 2-2; Section 3.2.1 As presently written, Specification 3.2.1 requires that a Licensee Event Report (LER) be submitted whenever the Axial Flux Difference (AFD) exceeds the target AFD by more than +5% regardless of the cumuiattve penalty deviation. In Section 3.2.1 of the bases it is clearly stated that the use of control rods can 'be expected, in the majority of instances, to cause the actual AFD to differ from the target AFD by more than +55. |
| | ~c c 'h |
| | |
| | 1 ~ ~ ~ ~ |
| | It is our understanding that the intent of Specification 3.2.1 is to re-quire LER submittal only in those instances when the cumulative penalty deviation exceeds, the allowable values specified in the action statement of the specification. However, our present. Specification 3.2.1 does not reflect this understanding. In order to clarify the requirements of the specification and to minimize submittal of unnecessary LERs, we are re-questing that a Section 3.2.l.d be added to the existing AFD specification. |
| | The- revised Technical Specification pages reflect this proposed change. |
| | Unit 2; Page 3/4 l-ll; Section 4.1.2.3 The centrifugal charging pumps, when= tested on recirculation flow during modes 5 and 6,, must develop a discharge pressure 2390 psig. The 15 psi pressure difference between discharge pressures of the pump during Modes 5 and 6 and during Modes 1-4 -is-due-to a .difference .in-the'Volume Control Tank (VCT) pressure in those modes. This was reflected in the Unit 1 Technical Specifications. earlier and is now being revised accordingly, in the Unit 2 Technical Specification. |
| | Chan e No. 5 Unit 1; Page 3/4 6-35; Section 4.6.5.6 Unit 2; Page 3/4 6-44; Section 4.6.5.6 The intent of the Ceq fan motor current surveillance is to check for disengaged drive shafts, broken fan blades, frozen or bad bearings, and other malfunctions in the fan-motor system which would cause a significant deviation from the normal motor load. Our review o surveillance test data indicates that the average current observed during tests is less than 56 amperes and the range of deviations under normal yet variable operating conditions .is slightly greater than 10 amperes. Me are therefore requesting a change to Specification 4.6.5.6.b to read: |
| | "b. Verifying that with the return air fan dampers closed, the fan motor current is 56+ 10 A'1PS when the fan speed is 880+ 20 RPM. This envelope would bound all normal operating readings and ensure that the intent of the Specification, to detect an inoperable system, is met." |
| | |
| | Chan e No. 7 Unit 1; Page 3/4 1-15; Section 3.1.2.7 .and 4.1.2.7 Unit 2; Page 3/4 1-15; Section D.1.2.7 and 4.1.2.7 The Technical Specifications require the refueling water storage tank borated water solution temperature be maintained at 70oF or above in Unit 1 and 80oF or above in Unit 2, when it is to be used as a borated water source in Modes 5 and 6. This temperature can be very difficult to maintain when adding cool water to the RWST by blending following draining of the tank for refueling purposes. |
| | Since the present solution temperature limits are derived from emergency core cooling requirements, this high temperature limit should only apply in Modes 1, 2, 3 and 4 which is covered by Technical Specifications |
| | : 3. 1. 2. 8 and 3. 5. 5. It is therefore requested that the minimum tem-perature limit for Modes 5 and 6 be returned to its original value of 35.oF}} |
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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
REGULATORY ENFORMATION DISTRIBUTION SYSTEM (RIOS)
ACCESSION NBR:8105290360 DOC ~ DATE: 81/05/26 NOTARIZED: NO DOCKET FACILi50 315 Oonal d C Cook Nuclear Power Plant> Uni t 1 i Indi ana K ~>OA>
50 316 Donald C ~ Cook hucl.ear Power Plant> Unit 2P Indiana 8 -500031.
AUTH'AME HUNTERPR ~ 8 REC
'ndiana IP ~ NAME AUTHOR AFFILIATION 8 Michigan RECIPIENT AFFILIATION Electric Co ~
SUBJFCT: Applicdtion for ~
amend to OL<changing App A of Tech Specs ~
DISTRIBUTION CODE: AOO'IS COPIES RECEIVED:LTR J. ENCL S SIZE::. 5+
T'ITLE.: General Distr ibution for af ter Issuance of Oper ating License cooies all material ~ 05000315 Send 3 copies-'of al material to ICE ~
1 05000316 W/C4ucl- 4 l~ 40~ CODE/NAME'OTES:ICE:3 REC IP I ENT COPIES RECIPIENT COPTES ID CODE/NAME LTTR ENCL ID LTTR ENCL ACTION! VARGA E 8 ~ 04 13 . 13 IaE..
INTERNAL: D/OIRgHUM FACOS OELO 06 11 1
2 1
1 2
0 OIR P DI V OF LIC NRC 0 A-PDR'2 E4'S R 1 0 1
1 1
1 0
RAO ASMT BR 1 1 G FIQ 01 1 EXTERNAL'CRS 09. fe 16 LPOR 03 1 1 NSIC 05 1 1 wl TOTAL NUMBER'F COPIES REQUIRED LTTR' 'NCL
i INDIANA Ilt MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GR E EN STATION NEW YORK, N. Y. 10004 May 26, 1981 AEP:NRC:0372 a.
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Donald C. Cook Nuclear Plant Unit Nos.
Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 1 and 2 U~g
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TECHNICAL SPECIFICATIONS CHANGE REQUEST
'ib Mr. Harold R. Denton, Director of Nuclear Reactor Regulation'ffice U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Denton:
This letter and its attachments request changes in several of the Appendix 'A'echnical Specifications for the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2. Attachment 1 is the description Attachment 2 contains the revised Technical Specification of'he changes.
pages. A number of these changes are editorial. All changes have been indicated by a vertical line on the right hand side of the page. We request that the NRC file and process this Technical Specification change package as a single amendment.
These proposed Technical Specifications have been reviewed and approved by the Plant Nuclear Safety CoraIIittee. The result of these reviews is that these proposed revisions will not adversely affect the health and safety of the public. Change Nos. 4, 5 and 6
'ave been reviewed by the AEPSC Nuclear Safety and Design Review Committee (NSDRC). The NSDRC concurs with the Plant PNSRC findings.
The remaining changes will be reviewed at the next meeting of the NSDRC scheduled for June 9, 1981.
Mr. Harold R. Denton AEP:NRC:0372 SeVen proposed Technical Specification revisions are contained in this submittal; four editorial in nature. Change Nos. 4 and 7 are considered to be Class II amendments ($ 1,200 fee each) and change No. 6 is considered to be a Class II'I amendment'$ 4,000.00 fee). Class I duplicate fees also apply for change Nos. 4, 6 and 7:. Accordingly, attached is a check in the amount of $ 7,600.00 for NRC processing of the aforementioned requests.
Very truly yours, Vice President cc: John E. Dolan - Columbus R. C. Callen G. Charnoff R. M. Jurgensen D. V. Shaller - Bridgman Region III Resident Inspector 9 Cook Plant - Bridgman
ATTACHMENT 1 TO AEP:NRC:0372 Technical S ecification Chan 'e Descri'tions
~Ch N . 1 (EC(
Unit No. 1 - Page 3/4 8 Section 3.8.2.3.
Under the definitions of the two D. C. bus trains, the second one should be changed from AB to CD.
Cch¹N. E (EC(
Unit Ho. 2 - Pages 3/4 8-9 and 3/4 8-10; Section 4.8.2.3.2d In item (d), the table number for-battery emergency. loads must be changed to 4-.8-1A. This revision is due to the fact that currently there are two tables numbered "Table 4.8.1".
~Ch N . 1 (EC(
Unit 1; Page 1-7; Table 1.2'.
Unit 2; Page 1-8, Table 1.2 In Table 1.2 of both units, frequence notations of the surveillance scheduling will be specified as a specific number of days whenever the frequency is greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The words "6 months" and "18 months" will be revised to read "184 days" and "549 days" respectively. This terminology conforms to ASME boiler and pressure vessel code,Section III.
Chan e Ho. 4 Unit 1; page 3/4 2-2; Section 3.2.1 Unit 2; Page 3/4 2-2; Section 3.2.1 As presently written, Specification 3.2.1 requires that a Licensee Event Report (LER) be submitted whenever the Axial Flux Difference (AFD) exceeds the target AFD by more than +5% regardless of the cumuiattve penalty deviation. In Section 3.2.1 of the bases it is clearly stated that the use of control rods can 'be expected, in the majority of instances, to cause the actual AFD to differ from the target AFD by more than +55.
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1 ~ ~ ~ ~
It is our understanding that the intent of Specification 3.2.1 is to re-quire LER submittal only in those instances when the cumulative penalty deviation exceeds, the allowable values specified in the action statement of the specification. However, our present. Specification 3.2.1 does not reflect this understanding. In order to clarify the requirements of the specification and to minimize submittal of unnecessary LERs, we are re-questing that a Section 3.2.l.d be added to the existing AFD specification.
The- revised Technical Specification pages reflect this proposed change.
Unit 2; Page 3/4 l-ll; Section 4.1.2.3 The centrifugal charging pumps, when= tested on recirculation flow during modes 5 and 6,, must develop a discharge pressure 2390 psig. The 15 psi pressure difference between discharge pressures of the pump during Modes 5 and 6 and during Modes 1-4 -is-due-to a .difference .in-the'Volume Control Tank (VCT) pressure in those modes. This was reflected in the Unit 1 Technical Specifications. earlier and is now being revised accordingly, in the Unit 2 Technical Specification.
Chan e No. 5 Unit 1; Page 3/4 6-35; Section 4.6.5.6 Unit 2; Page 3/4 6-44; Section 4.6.5.6 The intent of the Ceq fan motor current surveillance is to check for disengaged drive shafts, broken fan blades, frozen or bad bearings, and other malfunctions in the fan-motor system which would cause a significant deviation from the normal motor load. Our review o surveillance test data indicates that the average current observed during tests is less than 56 amperes and the range of deviations under normal yet variable operating conditions .is slightly greater than 10 amperes. Me are therefore requesting a change to Specification 4.6.5.6.b to read:
"b. Verifying that with the return air fan dampers closed, the fan motor current is 56+ 10 A'1PS when the fan speed is 880+ 20 RPM. This envelope would bound all normal operating readings and ensure that the intent of the Specification, to detect an inoperable system, is met."
Chan e No. 7 Unit 1; Page 3/4 1-15; Section 3.1.2.7 .and 4.1.2.7 Unit 2; Page 3/4 1-15; Section D.1.2.7 and 4.1.2.7 The Technical Specifications require the refueling water storage tank borated water solution temperature be maintained at 70oF or above in Unit 1 and 80oF or above in Unit 2, when it is to be used as a borated water source in Modes 5 and 6. This temperature can be very difficult to maintain when adding cool water to the RWST by blending following draining of the tank for refueling purposes.
Since the present solution temperature limits are derived from emergency core cooling requirements, this high temperature limit should only apply in Modes 1, 2, 3 and 4 which is covered by Technical Specifications
- 3. 1. 2. 8 and 3. 5. 5. It is therefore requested that the minimum tem-perature limit for Modes 5 and 6 be returned to its original value of 35.oF