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UNITED STATES OF AMERICA iUCLEAR REGULATORY CCIGIISSION IN THE MATTER OF DOCKET NO. 50-289 LICE:!SE :iO. DPR-50 METROPOLITAN EDISCU COMPANY This is to certify that a copy of Technical Specification Change Request No. LT, to Appendix A of the Operating License for 2 ree Mile Island Nuclear Station Unit 1, has , on the date given below, been filed with the U. C. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:
UNITED STATES OF AMERICA iUCLEAR REGULATORY CCIGIISSION IN THE MATTER OF DOCKET NO. 50-289 LICE:!SE :iO. DPR-50 METROPOLITAN EDISCU COMPANY This is to certify that a copy of Technical Specification Change Request No. LT, to Appendix A of the Operating License for 2 ree Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U. C. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:
Mr. Weldon B. Arehart                             Mr. Harry B. Reese, Jr.
Mr. Weldon B. Arehart Mr. Harry B. Reese, Jr.
Board of Cupervisors of                           Board of County Commissioners Londonderry Township                             of Dauphin County R. D. #1, Geyers Church Road                     Dauphin County Court House Middletown, Pennsylvania       17057             Harrisburg, Pennsylvania       17120 METROPOLITAN EDISCU COMPANY
Board of Cupervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISCU COMPANY
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METROPOLITAN EDISO:i COMPAiY JERSEY CENTRAL PC E & LIGHT COMPANY A'!D PEU ISYLVA: IIA ELECTRIC COMPA:iY THREE MILE ISLAND :!UCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Scecification Change Request '!o . h7 This Technical Specification Change Request is submitted in support of Licencee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1.                     As a part of this request, proposed replacement pages for Appendix A are also included.
METROPOLITAN EDISO:i COMPAiY JERSEY CENTRAL PC E & LIGHT COMPANY A'!D PEU ISYLVA: IIA ELECTRIC COMPA:iY THREE MILE ISLAND :!UCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Scecification Change Request '!o. h7 This Technical Specification Change Request is submitted in support of Licencee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1.
IT"ROPOLITAN EDISOU CCMPAUY
As a part of this request, proposed replacement pages for Appendix A are also included.
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Vice P; esident Sworn and subscribed to me this 3rd day of February 1977.
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Three Mile Island Nuclear Station Unit 1 (TMI-1)
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Technical Scecification Change Recuest No. h7, The licensee requests that the attached revised page replace page 5-7 of the existing Technical Specifications, Appendix A.
Operating License No. DPR-50 Docket No. 50-289 Technical Scecification Change Recuest No. h7, The licensee requests that the attached revised page replace page 5-7 of the existing Technical Specifications, Appendix A.
Reasons for Procosed Chance Technical Specification 5.h.2.d lists the number of spent fuel asse=blies which may be stored in the TMI-1 Spent Fuel Pool "B". Because of uncertainties in the availability of future fuel reprocessing facilities, it has been decided to replace the original spent fuel storage racks in the "B" pool with storage racks that have a reduced center-to-center spacing of 13 5/8 inches. This change vill increase the storage capacity in the "B" pool from 17h assemblies to h96 assemblies. This increase allows for the storage of spent fuel accumu-I lated from successive yearly refuelings with a full core offload occurring during the 1986 refueling outage.
Reasons for Procosed Chance Technical Specification 5.h.2.d lists the number of spent fuel asse=blies which may be stored in the TMI-1 Spent Fuel Pool "B".
Because of uncertainties in the availability of future fuel reprocessing facilities, it has been decided to replace the original spent fuel storage racks in the "B" pool with storage racks that have a reduced center-to-center spacing of 13 5/8 inches. This change vill increase the storage capacity in the "B" pool from 17h assemblies to h96 assemblies. This increase allows for the storage of spent fuel accumu-I lated from successive yearly refuelings with a full core offload occurring during the 1986 refueling outage.
Safety Analysis Justifying Change A Safety Evaluation and an Envirennental Impact Evaluation justifying this change is enclosed.
Safety Analysis Justifying Change A Safety Evaluation and an Envirennental Impact Evaluation justifying this change is enclosed.
1478 558
1478 558


South End Spent Fuel Pool A       Spent Fuel Pool B   Dry New Fuel of Fuel     North End of Fuel     South End of Fuel   Storage Area Transfer     Handling Building     Handling Building   Fuel Handling Canal RB                                               Building Fuel Assys         64
South End Spent Fuel Pool A Spent Fuel Pool B Dry New Fuel of Fuel North End of Fuel South End of Fuel Storage Area Transfer Handling Building Handling Building Fuel Handling Canal RB Building Fuel Assys 64
* 256 **               496 ***             66 Cores             0.36           1.45                 2.8                 0.37 NOTES:
* 256 **
496 ***
66 Cores 0.36 1.45 2.8 0.37 NOTES:
* includes one space for accommodating a failed fuel detection container.
* includes one space for accommodating a failed fuel detection container.
                    ** includes three spaces for accommodating failed fuel containers.
** includes three spaces for accommodating failed fuel containers.
                    *** Spent Fuel Pool B contains spent fuel storage racks with a reduced center-to-center spacing of '3 5/8 inches to increase the storage capacity oi the pool.
*** Spent Fuel Pool B contains spent fuel storage racks with a reduced center-to-center spacing of '3 5/8 inches to increase the storage capacity oi the pool.
: e. All of the fuel assembly storage racks provided are designed to Seismic Class 1 criteria to the accelerations indicated below:
e.
Fuel Transfer Canal       Fuel Handling Building     Fuel Handling l in Reactor Building       Dry New Fuel Storage Area   Building Spent And Spent Fuel Pool A       Fuel Pool B Horiz.                 0.76 g                     0.38 g
All of the fuel assembly storage racks provided are designed to Seismic Class 1 criteria to the accelerations indicated below:
* Vertical               0.51 g                     0.25 g                   *
Fuel Transfer Canal Fuel Handling Building Fuel Handling l
in Reactor Building Dry New Fuel Storage Area Building Spent And Spent Fuel Pool A Fuel Pool B Horiz.
0.76 g 0.38 g Vertical 0.51 g 0.25 g
* The "B" pool fuel storage racks are designed using the floor response spectra of the Fuel Handling Building.
* The "B" pool fuel storage racks are designed using the floor response spectra of the Fuel Handling Building.
REFERENCES (1) FSAR, Section 9.7 1478 35Si
REFERENCES (1) FSAR, Section 9.7 1478 35Si
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Latest revision as of 14:43, 3 January 2025

Tech Spec Change Request 47 Supporting Licensee Request to Change App a to License DPR-50 Re Increase of Storage Capacity in TMI-1 Spent Fuel Pool B from 174 to 496 Spent Fuel Assemblies.Certificate of Svc Encl
ML19260A039
Person / Time
Site: Crane Constellation icon.png
Issue date: 02/03/1977
From: Arnold R
METROPOLITAN EDISON CO.
To:
Shared Package
ML19260A030 List:
References
NUDOCS 7910290671
Download: ML19260A039 (4)
v • d • e


Text

.

UNITED STATES OF AMERICA iUCLEAR REGULATORY CCIGIISSION IN THE MATTER OF DOCKET NO. 50-289 LICE:!SE :iO. DPR-50 METROPOLITAN EDISCU COMPANY This is to certify that a copy of Technical Specification Change Request No. LT, to Appendix A of the Operating License for 2 ree Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U. C. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:

Mr. Weldon B. Arehart Mr. Harry B. Reese, Jr.

Board of Cupervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISCU COMPANY

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7 ice President Februarv ^, 19'"'

,at e a.:

7910290

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1478 356

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METROPOLITAN EDISO:i COMPAiY JERSEY CENTRAL PC E & LIGHT COMPANY A'!D PEU ISYLVA: IIA ELECTRIC COMPA:iY THREE MILE ISLAND :!UCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Scecification Change Request '!o. h7 This Technical Specification Change Request is submitted in support of Licencee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1.

As a part of this request, proposed replacement pages for Appendix A are also included.

IT"ROPOLITAN EDISOU CCMPAUY p)

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Vice P; esident Sworn and subscribed to me this 3rd day of February 1977.

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Ge'! '. iLO!! b y 'i;$ Sc, J,*'JT 3d,1)[ 3 Mf 1478 357

Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Technical Scecification Change Recuest No. h7, The licensee requests that the attached revised page replace page 5-7 of the existing Technical Specifications, Appendix A.

Reasons for Procosed Chance Technical Specification 5.h.2.d lists the number of spent fuel asse=blies which may be stored in the TMI-1 Spent Fuel Pool "B".

Because of uncertainties in the availability of future fuel reprocessing facilities, it has been decided to replace the original spent fuel storage racks in the "B" pool with storage racks that have a reduced center-to-center spacing of 13 5/8 inches. This change vill increase the storage capacity in the "B" pool from 17h assemblies to h96 assemblies. This increase allows for the storage of spent fuel accumu-I lated from successive yearly refuelings with a full core offload occurring during the 1986 refueling outage.

Safety Analysis Justifying Change A Safety Evaluation and an Envirennental Impact Evaluation justifying this change is enclosed.

1478 558

South End Spent Fuel Pool A Spent Fuel Pool B Dry New Fuel of Fuel North End of Fuel South End of Fuel Storage Area Transfer Handling Building Handling Building Fuel Handling Canal RB Building Fuel Assys 64

  • 256 **

496 ***

66 Cores 0.36 1.45 2.8 0.37 NOTES:

  • includes one space for accommodating a failed fuel detection container.
    • includes three spaces for accommodating failed fuel containers.
      • Spent Fuel Pool B contains spent fuel storage racks with a reduced center-to-center spacing of '3 5/8 inches to increase the storage capacity oi the pool.

e.

All of the fuel assembly storage racks provided are designed to Seismic Class 1 criteria to the accelerations indicated below:

Fuel Transfer Canal Fuel Handling Building Fuel Handling l

in Reactor Building Dry New Fuel Storage Area Building Spent And Spent Fuel Pool A Fuel Pool B Horiz.

0.76 g 0.38 g Vertical 0.51 g 0.25 g

  • The "B" pool fuel storage racks are designed using the floor response spectra of the Fuel Handling Building.

REFERENCES (1) FSAR, Section 9.7 1478 35Si

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