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| {{#Wiki_filter:V hlEMO ROUTE SUP Form ERDA-93 ()-7S)ERDAhf 0240 See me about IIIla.Note and return.For concurrence. | | {{#Wiki_filter:V hlEMO ROUTE SUP See me about IIIla. For concurrence. For action. |
| For afgnature. | | Form ERDA-93 ()-7S) ERDAhf 0240 Note and return. For afgnature. For In(ormat ton. |
| For action.For In(ormat ton.To (Name and unit)IE Chief, FCSEB IE: Hg (4)Licensing (4)'To (Name and unit)A/D for Xn fo.Proces Region I Region II PDR INITIALS DATE ing REaIARKS American Electric Power Service Cor oration Indiana and Hjchi an Power Com an D C Cook Plant Unit N 1 50-315 To (Name and unit)NSXC'IC R.Callen R.Vollen IIIITIALS FROM{Namo and unit)G.Fiorelli IE:IIX Attached is a copy of licensee's reply dated September 30, 1975, to IE Bulletin 75-04A.PHONE IKL DATE 10-06-75 DSE OTHER SIDE FOR ADDITION+REMARK GPO c I915 0-599 559 9 AMERICAN ELECTRlC POWER Service Corporation RODKRT o.HUNTCR VICC F4CSIOCHT HVCICAA CNOIHCCAINO 2 Broadu:ay, iVeio York, K Y.10004 (212)422.4800 Donald C.Cook Nuclear Plant Docket No.50-315 DPR No.58 September 30, 1975 U.S, Nuclear Regulatory Commission Office of Inspection and Enforcement Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attention:
| | To (Name and unit) INITIALS REaIARKS IE Chief, FCSEB American Electric Power Service Cor oration IE: Hg (4) |
| iver.J.G.Keppler, Regional Director Gentlemen:
| | Licensing (4) DATE Indiana and Hjchi an Power Com an D C Cook Plant Unit N1 50-315 |
| Item 6 of IE Bulletin 75-0I+A requires a schedule for accomplishment of any revision to our policies and procedures and any proposed changes to the facility, to assure that consideration for alternate methods for accom-plishing an orderly plant shutdown and cooldown are provided in case of loss of normal and preferred alternate shutdown and cooldown ystems at the Donald C.Cook Nuclear Plant.Our letter to you dated June 27, 1975 provided this schedule.In, addition, Item 6 requests monthly summary reports detailing our progress in this work.This letter is the third such monthly report.The two previous reports were dated July 30, and August 27, 1975.In fulfillment of our schedule, the guides for performing local control of critical components and for writing a procedure for cold shutdown following the postulated event, are now being prepared in final form and will be transmitted to the plant by October 1, 1975.An index of the equipment concerned in these guides is being prepared which, in itself, will make it possible for the plant staff to prepare the first steps of the procedure.
| | 'To (Name and unit) |
| 14 Hr.J.G.Keppler 0 September 30, 1975 A design change request is being generated in American Electric Power Service Corporation,and will be submitted to our Change Control Board in the near future.Tnis document will give the specific in'formation on the location, design and installation of local instrumentation panels whicn will monitor critical parameters.
| | A/D for Xn fo. Proces ing Region I Region II PDR To (Name and unit) IIIITIALS NSXC |
| The request will al o include specifics concerning changes to air lines on a number of air-operated valves to make local control possible.Following approval by the Change Control Board, the AEPSC Nuclear Safety and Design Review Committee and the'lant Nuclear Safety Review Committee, changes will be made at the site.The schedule for implementation of the physical changes will con ider material availability and whether they can be made with the Unit in operation or during a cold shutdown.The completion of these changes and'he preparation, approval and implementation of the above-mentioned plant operating procedure will constitute the remainder of our efforts to assure that the Donald C..Cook Nuclear Plant can be brought to an orderly plant shut-down.and cooldown following loss of control'from the control room.A training class was held at the Donald C.Cook Nuclear Plant the week of September 8.The purpose of the class was to instruct all of the employees in the correct way to extinguish an energized cable fire with water.The class~ras given by an AEPSC specialist in fire prevention and.control.A total of 217 people attended the eight classes, plus two night sessions were held for the Lake Township and Bridgman Fire Departments.
| | 'IC R. Callen R. Vollen FROM {Namo and unit) |
| A five foot long cable tray filled with several types of cables and a piece of expanded metal 30" x 30" was attached'o the cable tray and energized to 4500 volts to ground.The highest voltage in any of the power or control cables at the Donald C.Cook Nuclear Plant is 4160 volts.Each employee turned the water on the energ'zed equipment at a distance of 10 feet, using a spray nozzle.Demonstrations were given at each class as to how efficiently water extinguishes electric cable fires.Very truly yours, RSH:mla 3)j R.S.O~ter Vi ce President-Nuclear Engxneerzng
| | G. Fiorelli Attached is a copy of licensee's reply dated September 30, IE:IIX 1975, to IE Bulletin 75-04A. |
| | PHONE IKL DATE 10-06-75 DSE OTHER SIDE FOR ADDITION+ REMARK GPO c I915 0-599 559 9 |
|
| |
|
| Mr.J.G;Keppler'eptember 30, 1975 cc: G.Charnoff R.C.Callen P.M.Stekett'e R.lrlalsh R.J.Vollen R.N.Jurgensen-Bridgman J.E.Dolan}} | | AMERICAN ELECTRlC POWER Service Corporation 2 Broadu:ay, iVeio York, K Y. 10004 (212) 422.4800 RODKRT o. HUNTCR VICC F4CSIOCHT HVCICAA CNOIHCCAINO Donald C. Cook Nuclear Plant Docket No. 50-315 DPR No. 58 September 30, 1975 U. S, Nuclear Regulatory Commission Office of Inspection and Enforcement Region III Roosevelt Road 799 Glen Ellyn, Illinois 60137 Attention: iver. J. G. Keppler, Regional Director Gentlemen: |
| | Item 6 of IE Bulletin 75-0I+A requires a schedule for accomplishment of any revision to our policies and procedures and any proposed changes to the facility, to assure that consideration for alternate methods for accom-plishing an orderly plant shutdown and cooldown are provided in case of loss of normal and preferred alternate shutdown and cooldown ystems at the Donald C. Cook Nuclear Plant. |
| | Our letter to you dated June 27, 1975 provided this schedule. |
| | In, addition, Item 6 requests monthly summary reports detailing our progress in this work. This letter is the third such monthly report. The two previous reports were dated July 30, and August 27, 1975. |
| | In fulfillment of our schedule, the guides for performing local control of critical components and for writing a procedure for cold shutdown following the postulated event, are now being prepared in final form and will be transmitted to the plant by October 1, 1975. An index of the equipment concerned in these guides is being prepared which, in itself, will make it possible for the plant staff to prepare the first steps of the procedure. |
| | |
| | 14 Hr. J. G. Keppler 0 |
| | September 30, 1975 A design change request is being generated in American Electric Power Service Corporation,and will be submitted to our Change Control Board in the near future. |
| | Tnis document will give the specific in'formation on the location, design and installation of local instrumentation panels whicn will monitor critical parameters. The request will al o include specifics concerning changes to air lines on a number of air-operated valves to make local control possible. |
| | Following approval by the Change Control Board, the AEPSC Nuclear Safety and Design Review Committee and the'lant Nuclear Safety Review Committee, changes will be made at the site. The schedule for implementation of the physical changes will con ider material availability and whether they can be made with the Unit in operation or during a cold shutdown. The completion of these changes and'he preparation, approval and implementation of the above-mentioned plant operating procedure will constitute the remainder of our efforts to assure that the Donald C.. |
| | Cook Nuclear Plant can be brought to an orderly plant shut-down .and cooldown following loss of control'from the control room. |
| | A training class was held at the Donald C. Cook Nuclear Plant the week of September 8. The purpose of the class was to instruct all of the employees in the correct way to extinguish an energized cable fire with water. The class ~ras given by an AEPSC specialist in fire prevention and. control. |
| | A total of 217 people attended the eight classes, plus two night sessions were held for the Lake Township and Bridgman Fire Departments. A five foot long cable tray filled with several types of cables and a piece of expanded metal 30" x 30" was attached'o the cable tray and energized to 4500 volts to ground. The highest voltage in any of the power or control cables at the Donald C. Cook Nuclear Plant is 4160 volts. Each employee turned the water on the energ'zed equipment at a distance of 10 feet, using a spray nozzle. Demonstrations were given at each class as to how efficiently water extinguishes electric cable fires. |
| | Very truly yours, 3)j O~ |
| | RSH:mla R. S. ter Vice President Nuclear Engxneerzng |
| | |
| | Mr. J. G; Keppler'eptember 30, 1975 cc: G. Charnoff R. C. Callen P. M. Stekett'e R. lrlalsh R. J. Vollen R. N. Jurgensen Bridgman J. E. Dolan}} |
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Category:Letter
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ML15323A4342015-11-16016 November 2015 Response (Part 1) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-99, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11 and 3.8.1.152015-10-30030 October 2015 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11 and 3.8.1.15 AEP-NRC-2015-98, Supplemental Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program2015-10-30030 October 2015 Supplemental Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program ML15308A0932015-10-15015 October 2015 Pressurized Water Reactor Owners Group (Pwrog), 15066-NP, Revision 1, Responses to Follow-Up NRC RAI 2 on the D.C. Cook, Units 1 and 2, Reactor Internals Aging Management Program. AEP-NRC-2015-86, Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent With. Previously Licensed Conditions.2015-09-18018 September 2015 Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent With. Previously Licensed Conditions. AEP-NRC-2015-80, Response to Third Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-08-28028 August 2015 Response to Third Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-75, Response to Second Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-08-24024 August 2015 Response to Second Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-88, Response to Request for Additional Information Regarding Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements2015-08-24024 August 2015 Response to Request for Additional Information Regarding Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements AEP-NRC-2015-69, Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program2015-08-0606 August 2015 Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program ML15223A4362015-07-28028 July 2015 PWROG-15066-NP, Revision 0, Responses to Follow-Up NRC RAI 2 on the DC Cook Units 1 and 2 Reactor Internals Aging Management Program. AEP-NRC-2015-63, Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection2015-07-17017 July 2015 Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection AEP-NRC-2015-64, Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-07-17017 July 2015 Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term 2024-08-15
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V hlEMO ROUTE SUP See me about IIIla. For concurrence. For action.
Form ERDA-93 ()-7S) ERDAhf 0240 Note and return. For afgnature. For In(ormat ton.
To (Name and unit) INITIALS REaIARKS IE Chief, FCSEB American Electric Power Service Cor oration IE: Hg (4)
Licensing (4) DATE Indiana and Hjchi an Power Com an D C Cook Plant Unit N1 50-315
'To (Name and unit)
A/D for Xn fo. Proces ing Region I Region II PDR To (Name and unit) IIIITIALS NSXC
'IC R. Callen R. Vollen FROM {Namo and unit)
G. Fiorelli Attached is a copy of licensee's reply dated September 30, IE:IIX 1975, to IE Bulletin 75-04A.
PHONE IKL DATE 10-06-75 DSE OTHER SIDE FOR ADDITION+ REMARK GPO c I915 0-599 559 9
AMERICAN ELECTRlC POWER Service Corporation 2 Broadu:ay, iVeio York, K Y. 10004 (212) 422.4800 RODKRT o. HUNTCR VICC F4CSIOCHT HVCICAA CNOIHCCAINO Donald C. Cook Nuclear Plant Docket No. 50-315 DPR No. 58 September 30, 1975 U. S, Nuclear Regulatory Commission Office of Inspection and Enforcement Region III Roosevelt Road 799 Glen Ellyn, Illinois 60137 Attention: iver. J. G. Keppler, Regional Director Gentlemen:
Item 6 of IE Bulletin 75-0I+A requires a schedule for accomplishment of any revision to our policies and procedures and any proposed changes to the facility, to assure that consideration for alternate methods for accom-plishing an orderly plant shutdown and cooldown are provided in case of loss of normal and preferred alternate shutdown and cooldown ystems at the Donald C. Cook Nuclear Plant.
Our letter to you dated June 27, 1975 provided this schedule.
In, addition, Item 6 requests monthly summary reports detailing our progress in this work. This letter is the third such monthly report. The two previous reports were dated July 30, and August 27, 1975.
In fulfillment of our schedule, the guides for performing local control of critical components and for writing a procedure for cold shutdown following the postulated event, are now being prepared in final form and will be transmitted to the plant by October 1, 1975. An index of the equipment concerned in these guides is being prepared which, in itself, will make it possible for the plant staff to prepare the first steps of the procedure.
14 Hr. J. G. Keppler 0
September 30, 1975 A design change request is being generated in American Electric Power Service Corporation,and will be submitted to our Change Control Board in the near future.
Tnis document will give the specific in'formation on the location, design and installation of local instrumentation panels whicn will monitor critical parameters. The request will al o include specifics concerning changes to air lines on a number of air-operated valves to make local control possible.
Following approval by the Change Control Board, the AEPSC Nuclear Safety and Design Review Committee and the'lant Nuclear Safety Review Committee, changes will be made at the site. The schedule for implementation of the physical changes will con ider material availability and whether they can be made with the Unit in operation or during a cold shutdown. The completion of these changes and'he preparation, approval and implementation of the above-mentioned plant operating procedure will constitute the remainder of our efforts to assure that the Donald C..
Cook Nuclear Plant can be brought to an orderly plant shut-down .and cooldown following loss of control'from the control room.
A training class was held at the Donald C. Cook Nuclear Plant the week of September 8. The purpose of the class was to instruct all of the employees in the correct way to extinguish an energized cable fire with water. The class ~ras given by an AEPSC specialist in fire prevention and. control.
A total of 217 people attended the eight classes, plus two night sessions were held for the Lake Township and Bridgman Fire Departments. A five foot long cable tray filled with several types of cables and a piece of expanded metal 30" x 30" was attached'o the cable tray and energized to 4500 volts to ground. The highest voltage in any of the power or control cables at the Donald C. Cook Nuclear Plant is 4160 volts. Each employee turned the water on the energ'zed equipment at a distance of 10 feet, using a spray nozzle. Demonstrations were given at each class as to how efficiently water extinguishes electric cable fires.
Very truly yours, 3)j O~
RSH:mla R. S. ter Vice President Nuclear Engxneerzng
Mr. J. G; Keppler'eptember 30, 1975 cc: G. Charnoff R. C. Callen P. M. Stekett'e R. lrlalsh R. J. Vollen R. N. Jurgensen Bridgman J. E. Dolan