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Leon D. White, Jr i DATE OF DOCUMENT 4/21/77 DATE AECEIVED 4/25/77 gS LETT E A Pg) AIGINAL QCOPY DESCAIPTION 0 NOTOAIZ CD MhlcLASSIFIED PAOP INPUT FOAM ENCI.OSV AE NUMOEA OF COPIES AECEIVED i szg~FW Ltr furnishing information regarding spent fuel pool modificationi; ~ ~ ~ ~ ~ ~ ~
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  /t////VJ     '//////////                                                                               o 5TAlC ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. '14649 LEON D. WHITE JR.       ~
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TELEPHONE VICE PRESIDENT ARCA CCOC VIS 546-2700 April 21,,1977                   3 (p(ggy M)55 ALLt35 Director of Nuclear Reactor Regulation Attention: A. Schwencer, Chief Branch No. 1                               QP U.S. Nuclear Regulatory Commission Nashington,                     DC 20555
ROCHESTER GAS AND ELECTRIC CORPORATION Los ~ OslasOy I
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89 EAST AVENUE, ROCHESTER, N.Y. '14649 LEON D. WHITE~ JR.
VICE PRESIDENT TELEPHONE ARCA CCOC VIS 546-2700 April 21,,1977 (p(ggy M)55 ALLt35 Director of Nuclear Reactor Regulation Attention:
A. Schwencer, Chief Branch No.
1 U.S. Nuclear Regulatory Commission Nashington, DC 20555


==Subject:==
==Subject:==
Spent Fuel Pool Modification R. E. Ginna Nuclear Power Plant, Unit No. 1 Do'cket No. 50-244
Spent Fuel Pool Modification R. E. Ginna Nuclear Power Plant, Unit No.
1 Do'cket No. 50-244 3
QP


==Dear Mr. Schwencer:==
==Dear Mr. Schwencer:==
 
On November 15, 1976, the Commission issued Amendment No.
On       November 15, 1976,         the Commission issued   Amendment No. 11 to our Provisional Operating License No. DPR-18 for the R.E.
11 to our Provisional Operating License No. DPR-18 for the R.E.
Ginna Nuclear Power. Plant. This Amendment authorized changes in the design of the Ginna spent fuel storage pool. Pertinent to the issuance of that Amendment and the Technical Specifications thereto, there was correspondence dated January 30, May 19, June 3, August. 5, and September 29, 1976. That. correspondence envisioned a total of 595 fuel storage locations arranged in a checker board array (see Figure 1 of our January 30 submittal) .
Ginna Nuclear Power. Plant.
This letter is to inform you that., by interchanging the fuel and water box locations as shown in Figure 1, the as-built spent fuel racks contain 596 fuel storage locations. However, physically                     impossible to place fuel in one 'of the storage it loca-is tions because of interference with permanently installed pipe supports for the spent fuel pool cooling system discharge pipe.
This Amendment authorized changes in the design of the Ginna spent fuel storage pool.
Pertinent to the issuance of that Amendment and the Technical Specifications thereto, there was correspondence dated January 30, May 19, June 3, August. 5, and September 29, 1976.
That. correspondence envisioned a total of 595 fuel storage locations arranged in a checker board array (see Figure 1 of our January 30 submittal).
This letter is to inform you that., by interchanging the fuel and water box locations as shown in Figure 1, the as-built spent fuel racks contain 596 fuel storage locations.
However, it is physically impossible to place fuel in one 'of the storage loca-tions because of interference with permanently installed pipe supports for the spent fuel pool cooling system discharge pipe.
Since this storage location is permanently disabled, there are only 595 usable fuel storage locations.
Since this storage location is permanently disabled, there are only 595 usable fuel storage locations.
Even though there are only 595 storage locations, we have been informed by our supplier that all calculations are valid for the 596 location array.                       In addition, we have 'reviewed each of our submittals in detail to assure ourselves that, all analyses are valid for the 596 location arrangement. The review has demon-strated, that the results of the evaluation are unchanged.
Even though there are only 595 storage locations, we have been informed by our supplier that all calculations are valid for the 596 location array.
In addition, we have 'reviewed each of our submittals in detail to assure ourselves that, all analyses are valid for the 596 location arrangement.
The review has demon-strated, that the results of the evaluation are unchanged.
Specifically, the following was reviewed:
Specifically, the following was reviewed:


ROCHESTER GAS AND ELECTR   ORP.                                              SHEET NO.
ROCHESTER GAS AND ELECTR ORP.
'o pATE April 21,     1977 Mr. A. Schwencer,       Chief The seismic     analysis   assumed   that each rack was fully loaded with fuel assemblies.         Rack type A contained 70 fuel assem-blies, rack type B contained 56 fuel assemblies, and rack type C contained 50 fuel assemblies.             Therefore, the analysis is unchanged by the 596 location arrangement.
pATE April 21, 1977
The spent     fuel cooling analysis was based on BTU/hr limits derived from equipment capabilities. The spent fuel pool heat load will be maintained below these BTU/hr limits.
'o Mr. A. Schwencer, Chief SHEET NO.
The seismic analysis assumed that each rack was fully loaded with fuel assemblies.
Rack type A contained 70 fuel assem-blies, rack type B contained 56 fuel assemblies, and rack type C contained 50 fuel assemblies.
Therefore, the analysis is unchanged by the 596 location arrangement.
The spent fuel cooling analysis was based on BTU/hr limits derived from equipment capabilities.
The spent fuel pool heat load will be maintained below these BTU/hr limits.
These limits and the analysis are unchanged by the 596 loca-tion arrangement.
These limits and the analysis are unchanged by the 596 loca-tion arrangement.
The individual fuel assembly cooling analysis assumed the hottest fuel assemblies were located near the east wall of the spent fuel pool. The location of the hottest assembly and   the analysis are unchanged by the           596 location arrange-ment.
The individual fuel assembly cooling analysis assumed the hottest fuel assemblies were located near the east wall of the spent fuel pool.
The   nuclear analysis assumed an infinite array of uniform spent   fuel racks; therefore, this analysis is unchanged by the 596 location arrangement.
The location of the hottest assembly and the analysis are unchanged by the 596 location arrange-ment.
The loss of spent fuel pool cooling analysis was based on the BTU/hr limits derived from equipment capabilities. These limits and the analysis are unchanged by the 596 location arrangement.
The nuclear analysis assumed an infinite array of uniform spent fuel racks; therefore, this analysis is unchanged by the 596 location arrangement.
The   fuel assembly drop analysis was based on a fully-loaded fuel rack. For the cases analyzed, the rack was assumed to be fully loaded with 70 fuel assemblies.               This analysis is unchanged by the 596 location arrangement.
The loss of spent fuel pool cooling analysis was based on the BTU/hr limits derived from equipment capabilities.
The structural, mechanical, and material designs are based on a fully loaded type A rack. Therefore, these designs are unchanged by the 596 location arrangement.
These limits and the analysis are unchanged by the 596 location arrangement.
The environmental impact of the modification is essentially unchanged by the 596 location arrangement.             There is no change in the amount   of materials   required   for the modification.
The fuel assembly drop analysis was based on a fully-loaded fuel rack.
The radiation dose calculations are unchanged.               The amount of solid waste generated by         the   spent. fuel pool   is essentially unchanged and     remains   less than   4.1 percent of the total yearly generated solid     radioactive   waste. The limit on minimum   spacing of freshly   discharged     fuel is also   unchanged since   it, is based on a unit area.
For the cases
: analyzed, the rack was assumed to be fully loaded with 70 fuel assemblies.
This analysis is unchanged by the 596 location arrangement.
The structural, mechanical, and material designs are based on a fully loaded type A rack.
Therefore, these designs are unchanged by the 596 location arrangement.
The environmental impact of the modification is essentially unchanged by the 596 location arrangement.
There is no change in the amount of materials required for the modification.
The radiation dose calculations are unchanged.
The amount of solid waste generated by the spent. fuel pool is essentially unchanged and remains less than 4.1 percent of the total yearly generated solid radioactive waste.
The limit on minimum spacing of freshly discharged fuel is also unchanged since it, is based on a unit area.


I 0
0 I


ROCHESTER GAS AND ELECTR ~ ORP.                                SHEET NO.
ROCHESTER GAS AND ELECTR ~
DATE April 21,   1977 To Mx. A. Schwencer, .Chief Our engineering procedures are presently heing reviewed to ensure   that this type of reporting inconsistency is prevented in the future.
ORP.
Very truly yours, Q~P     ~p Leon D. White, Jr.
DATE April 21, 1977 To Mx. A. Schwencer,
xc:   James   P. O'Reilly
.Chief SHEET NO.
Our engineering procedures are presently heing reviewed to ensure that this type of reporting inconsistency is prevented in the future.
Very truly yours, Q~P ~p Leon D. White, Jr.
xc:
James P. O'Reilly


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Latest revision as of 20:46, 5 January 2025

R. E. Ginna - 04/21/1977 Letter Spent Fuel Pool Modification
ML18142A823
Person / Time
Site: Ginna 
Issue date: 04/21/1977
From: White L
Rochester Gas & Electric Corp
To: Schwencer A
Office of Nuclear Reactor Regulation
References
Download: ML18142A823 (7)
v • d • e


Text

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Leon D. White, Jr i DATE OF DOCUMENT 4/21/77 DATE AECEIVED 4/25/77 gS LETT E A Pg) AIGINAL QCOPY DESCAIPTION 0 NOTOAIZ CD MhlcLASSIFIED PAOP INPUT FOAM ENCI.OSV AE NUMOEA OF COPIES AECEIVED i szg~FW Ltr furnishing information regarding spent fuel pool modificationi; ~ ~ ~ ~ ~ ~ ~

l90 NOT REM0~(s-.)

KCKNOWZ,E PLANT lIAHE:

R Ei Ginna Unit No.

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SAFETY ASSIGNED AD:

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