ML20029D859
| ML20029D859 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/04/1994 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20029D858 | List: |
| References | |
| NUDOCS 9405100314 | |
| Download: ML20029D859 (14) | |
Text
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UNITED STATES i
5t NUCLEAR REGULATORY COMMISSION j#
4 WASHINGTON, D.C. 20555-0001 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1
. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 151 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated April 28, 1993, as supplemented by letters dated August 12, 1993, November 17, 1993, February 2, 1994, and April 7, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 0.
Tim issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby l
amended to read as follows:
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9405100314 940504 i
PDR ADOCK 05000272:
P PDR I
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i, (2) Technicsl Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.151, are hereby incorporated in the l
l license.
The licensee shall operate the facility in accordance with l
the Technical Specifications, i
l 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y
f$
l Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 4, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 151 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 9-3 3/4 9-3 l
5-5 5-5 5-6 5-6 5-6a 4
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'e REFUELING OPERATIONS
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a DECAY T1HE l
LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be suberitical for at least 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.
l APPLICABILITY: During movement of irradiated fuel in the reactor pressure j
vessel.
l
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ACTION:
l With the reactor suberitical for less than 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, suspend all operations l
j involving movement of irradiated fuel in the reactor pressure vessel. The
]
provisions of Specification 3.0.3 are not applicable. -
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SURVEILLANCE REQUIREMENTS 4.9.3 The reactor shall be determined to have been suberitical for at least l
168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> by verification of the date and time of suberiticality prior to l
movement of irradiated fuel in the reactor pressure vessel.
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SALEM - UNIT 1 3/4 9-3 Amendment No.151
DESIGN FEATURES a.
In accordance with tha code requirements specified in Section 4.1 l
of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650'F, except for the pressurizer which is 680*F.
VOLUME i
5.4.2 The total water and steam volume of the reactor coolant system is l
12,811 100 cubic feet at a nominal Tavg of 576.7'F.
5.5 METEOROLOGICAL TOWER LOCAIlQH 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
)
5.6 FUEL STORACE CRITICALIIX 5.6.1.1 The new fuel storage racks are designed and shall be maintained with:
a.
A maximum Keff equivalent of 0.95 with the storage racks flooded with unborated water.
b.
A nominal 21.0 inch center-to-center distance between fuel assemblies.
c.
A maximum unirradiated fuel assembly enrichment of 4.5 w/o U-235.
5.6.1.2 The spent fuel storage racks are designed and shall be maintained with:
a.
A maximum Keff equivalent of 0.95 with the storage racks filled with unborated water.
b.
A nominal 10.5 inch center-to-center distance between fuel assemblies stored in Region 1 (flux trap type) racks.
c.
A nominal 9.05 inch center-to-center distance between fuel assemblies stored in Region 2 (nor.-flux trap) racks.
d.
Fuel assemblies stored in Region 1 racks shall meet one of the following storage constraints.
1.
Unirradiated fuel assemblies with a maximum enrichment of 4 25 w/o U 235 have unrestricted storage.
SALEM - UNIT 1 5-5 Amendment No. 151
]
DESIGN FEATURES 2.
Unirradiated fuel assemblies with enrichments greater than 4.25 w/o U 235 and less than or equal to 5.0 w/o U-235, that do not contain Integral Fuel Burnable Absorber (IFBA) pins, may only be stored in the peripheral cells facing the concrete wall.
3.
Unirradiated fuel assemblies with enrichments (E) greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o U-235, that contain IFBA rods with a nominal 2.35 mg B 10/ linear inch loading, and a number of IFBA rods equal to or greater than the number determined by the equari.on below, have unrestricted storage.
N - 42.67 (E-4.25) 4.
Irradiated fuel assemblies with enrichments (E) greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o, that have attained the minimum burnup (BU) as determined by the equation i
below, have unrestricted storage.
BU (MWD /kg U) - -26.212 + 6.1677E e.
Fuel assemblies stored in Region 2 racks shall meet one of the following storage constraints.
l 1.
Unteradiated fuel assemblies with a maximum enrichment of 5.0 w/c. U-235 may be stored in a checkerboard pattern with intermediate cells containing only water or non-fissile bearing material.
2.
Unirradiated fuel assemblies with a maximum enrichment (E) of 5.0 w/o U-235 may be stored in the central cell of any 3x3 array of cells provided the surrounding eight cells are empty or contain fuel assemblies that have attained the minimum burnup (BU) as determined by the equation below.
BU (MWD /kg U) - -15.48 + 17.80E - 0.7038E In this configuration, none of the nine cells in any 3x3 array shall be common to cells in any other similar 3x3 array.
Along the rack periphery, the concrete wall is equivalent to 3 outer cells in a 3x3 array.
3.
Irradiated fuel assemblies with a maximum enrichment (E) of 5.0 w/o U-235 that have attained the minimum burnup (BU) as determined by the equation below, have unrestricted storage.
BU (MWD /kg U) - 32.06 + 25.21E - 3.723E + 0.3535E 4.
Irradiated fuel assemblies with a maximum enrichment (E) of 5.0 w/o U-235 that have attained the minimum burnup (BU) as determined by the equation below, may be stored in a peripheral cell facing the concrete wall.
BU (MWD /kg U) - -25,36 + 15.14E - 0.602E SALEM - UNIT 1 5-6 Amendment No. 151
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DESIGN FEATURES DRAINAGE
.f 5.6.2 The spent fuel storage pool is designed and shall be maintained to i
prevent inadvertent draining of the pool below elevation 124'8".
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CAPACITY 1
5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1632 fuel assemblies.
l 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT j
5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
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l SALEM - UNIT 1 5-6a Amendment No. -151 4
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3 UNITED STATES i '
NUCLEAR REGULATORY COMMISSION
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WASHING TON, D.C, 20555 0001 l
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY 00CKET NO. 50-311 I
SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 131 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated April 28, 1993, as supplemented by letters dated August 12, 1993, November 17, 1993, February 2, 1994, and April 7, 1994 complies with the standards and requirements of the Atomic Energy Act of 1954, as 1
amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of thh amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
.. _. _. _ =. _ _ _... _
a,
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
131, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective.as of'its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y
YlY Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects-- I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 4, 1994
-,.. _ - _,, - - -. _ =. -.. _, - - -. - -. =. -.
1 ATTACHMENT TO LICENSE AMENDMENT N0.131 FACILITY OPERATING LICENSE N0. DPR-75 1
DOCKET N0. 50-311 I
Revise Appendix A as follows:
Remove Paaes Insert Paaes l
3/4 9-3 3/4 9-3 s-s s-s 5-Sa i
s-5b l
\\
i."
i l
REFUELING OPERATIONS l
~
3/4.9.3 DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subcritical for at least 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.
APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTION:
With the reactor suberitical for less than 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, suspend all operations l
involving movement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.
I t
SURVEILLANCE REQUIREMENTS 1
j 4.9.3 The reactor shall be determined to have been subcritical for at l
least 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> by verification of the date and time of suberiticality l
l prior to movement of irradiated fuel in the reactor pressure vessel..
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l SALEM - UNIT 2 3/4 9 3 Amendment No. 131
. _. - -.. -.- ~_..
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DESIGN FEATURES i
5.5 METEOROLOGICAL TOWER LOCATION j'
5.5.1 The meteorological. tower shall be located as shown on Figure 5.1-1.
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5.6 FUEL STORAGE i
CRITICALITY 5.6.1.1 The new fuel storage racks are designed and shall be maintained with:
4 a.
A maximum Keff equivalent of 0.95 with the storage racks flooded i
with unborated water.
)
b.
A nominal 21.0 inch center to-center distance between fuel assemblies, 4
i l
c.
A maximum unirradiated fuel assembly enrichment of 4.5 w/o U-235.
5.6.1.2 The spent fuel storage racks are designed and shall be maintained j
with:
a.
A maximum Keff equivalent of 0.95 with the storage racks filled with j
unborated water.
J b.
A nominal 10.5 inch center-to-center distance between fuel j
assemblies stored in Region 1 (flux trap type) racks, i
]
c.
A nominal 9.05 inch center-to-center distance between fuel l
j assemblies stored in Region 2 (non-flux trap) racks.
1 j
d.
Fuel assemblies stored in Region 1 racks shall meet one of the l
following storage constraints.
.i 1.
Unirradiated fuel assemblies with a maximum enrichment of 4.25
)
w/o U-235 have unrestricted storage.
2.
Unirradiated fuel assemblies with enrichments greater than 4.25 w/o U-235 and less than or equal to 5,0 w/o U-235, that do not contain Integral Fuel Burnable Absorber (IFBA) pins, may only be stored in the peripheral cells facing the concrete wall.
3.
Unirradiated fuel assemblies with enrichments (E) greater than j
4.25 w/o U-235 and less than or equal to 5.0 w/o U-235, that contain IFBA rods with a nominal 2.35 mg B-10/ linear inch 4
~
loading, and a nunber of IFBA rods equal to or greater than the i
number determined by the equation below, have unrestricted storage.
i l
N - 42.67 (E 4.25) i
)
SALEM - UNIT 2 5-5 Amendment No. 131 4
m-
DESIGN FEATURES I
4 Irradiated fuel assemblies with enrichments (E) greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o, that have attained the minimum burnup (BU) as determined by the equation j
below, have unrestricted storage.
BU (MWD /kg U) - -26.212 + 6.1677E e.
Fuel assemblies stored in Region 2 racks shall meet one of the following storage constraints.
1.
Unirradiated fuel assemblies with a maximum enrichment of 5.0 w/o U-235 may be stored in a checkerboard pattern with intermediate cells containing only water or non fissile bearing material.
2.
Unirradiated fuel assemblies with a maximum enrichment-(E) of 5.0 w/o U-235 may be stored in the central cell of any 3x3 array of cells provided the surrounding eight cells are empty or contain fuel assemblies that have attained the minimum burnup (BU) as determined by the equation below.
BU (MWD /kg U) - -15.48 + 17.80E - 0.7038E In this configuration, none of the nine cells in any 3x3 array shall be common to cells in any other similar 3x3 array. Along the rack periphery, the concrete wall is equivalent to 3 outer cells in a 3x3 array.
3.
Irradiated fuel assemblies with a maximum enrichment (E) of 5.0 w/o U 235 that have attained the minimum burnup (BU) as determined by the equation below, have unrestricted storage.
BU (MWD /kg U) - -32.06 + 25.21E - 3.723E + 0.3535E 4.
Irradiated fuel assemblies with a maximum enrichment (E) of 5.0 w/o U-235 that have attained the minimum burnup (BU) as determined by the equation below, may be stored in a peripheral cell facing the concrete wall.
BU (MWD /kg U) - 25.56 + 15.14E - 0.602E bRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 124'8".
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1632 fuel assemblies.
SALEM - UNIT 2 5-Sa Amendment No. 131
W DESIGN FEATURES 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7 1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7 1.
SALEM - UNIT 2 5-5b Amendment No. 131
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