ML20210B727
| ML20210B727 | |
| Person / Time | |
|---|---|
| Site: | Salem  (DPR-70-A-223, DPR-75-A-204) |
| Issue date: | 07/21/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210B730 | List: |
| References | |
| NUDOCS 9907230215 | |
| Download: ML20210B727 (13) | |
Text
/ acto yo UNITED STATES O d' E
NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20555 0001
.....l PUBLIC SERVICE ELECTRIC & GAS COMPANY l
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 Amendmen' No. 223 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 February 2,1999, as supplemented on April 26,1999, 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; D.
The 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 Specifications as L
indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility i
Operating License No. DPR-70 is hereby amended to read as follows:
9907230215 990721 PDR ADOCK 05000272 p
PDR t..
7- -
+
. (2) Technica'l Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 223, 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.
FOR THE NUCLEAR REGULATORY COMMISSION James W. Clifford, Chief, Section 2 Project Directorate I
)
Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: July 21, 1999 i
I
l I
ATTACHMENT TO LICENSE AMENDMENT NO. ??1 FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-272 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Paaes insert Paaes 5-5 5-5 5-Sa 5-6 5-6 5-6a 5-6a i
f
\\
l DESIGN FEATURES 1
l a.
In accordaL;e with the code requirements specified in section 4.1 of the ESAR, 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 J
680*F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is j
12,446 1 426 cubic feet at a nominal Tavg of 573*F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
l 5.6 FUEL STORAGE i
CRITICALITY 5.6.1.1 The new fuel storage racks are designed and shall be maintained with:
a.
A maximum K.tr equivalent of 0.95 with the storage racks flooded with unborated water.
1 i
b.
A nominal 21.0 inch center-to-center distance between fuel assemblies.
c.
Unirradiated fuel assemblies with enrichments less than or equal to 4.25 weight percent (w/o) U-235 with no requirements for Integral Fuel Burnable Absorber (IFBA) pins.
d.
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 which contain a minimum number of Integral Fuel Barnable Absorber (IFBA) pins.
This minimum number of IFBA pins shall have an equivalent l
reactivity hold-down which is greater than or equal to the reactivity hold down associated with N IFBA pins, at a nominal 2.35 mg B-10/ linear inch loading (1.5X), determined by the equation below:
l N = 42.67 ( E - 4.25 )
SALEM - UNIT 1 5-5 Amendment No. 223 l
l
DESIG?{ FEATURES 5.6.1.2 The spent fuel storage racks are designed and shall be maintained wfth:
a.
A maximum a.rr 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 (non-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 enrichmont 'f 4.25 w/o U-235 have unrestricted storage.
I I
i f
1 l
SALEM - Ut l'11 5-Ea Amendment No. 223 l
I i
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, which contain a minimum number of Integral Fuel Burnable Absorber (IFBA) pins have unrestricted storage. This minimum number of IFBA pins snall have an equivalent reactivity hold-down which is greater than or equal to the reactivity hold down associated with N IFBA pins, at a nominal 2.35 mg B-10/ linear inch loading (1.5X), determined by the equation below:
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 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.
l 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 equivalunt to 3 outer cells in a 3x3 array.
i SALEM - UNIT 1 5-6 Amendment No. 223 l
i 1
f DESIGN FEATURES 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 - 3.723E2 + 0.3535E2 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 - 0.602E2 DRAINAGE 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.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 1
3.7.1 The components identified in Table 5.7-1 are des ined and shall be maintained within the cyclic or transient limits of Tabl(
5.7-1.
l l
SALEM - UNIT 1 5-6a Amendment No.223
e nEc ps h
4 UNITED STATES j
,j NUCLEAR REGULATOR / COMMISSION
~#
WASHINGTON, D.C. 2055M001
\\...../
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 204 License No. DPR-75 1.
The Nuclear Regulatory Commissica (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electr,c & Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated February 2,1999, as supplemented on April 26,.1999, 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 i
forth in 10 CFR Chapter l-B.
The facility will operate in conformity with the application, the provisions of the Act, I
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 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.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications 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:
f 1
l l
2-l (2) Technical Specifications and Environmental Protectir
)lan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 204, 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.
FOR THE NUCLEAR REGULATORY COMMISSION 1
James W. Clifford, Chief, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Rcgulation
Attachment:
Changes to the Technical Specifications Date of issuance:
July:21, 1999 l
l 1-l
ATTACHMENTTO LICENSE AMENDMENT NO. 204 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Paoes insert Paaes 5-5 5-5
'5-Sa 5-Sa 5-5b 5-5b
l
]
l l
DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE I
CRITICALITY
~
5.6.1.1 The new fuel storage racks are designed and shall be maintained
)
with:
a.
A maximum K.re equivalent of equal to 0.95 with the storage racks flooded with unborated water.
b.
A nominal 21.0 inch center-to-center distance between fuel assemblies.
c.
Unirradiated fuel assemblies with enrichments less than or equal to 4.25 weight percent (w/o) U-235 with no requirements for Integral Fuel Burnable Absoruer (IFBA) pins.
d.
Unirradiated fuel assemblies with enrichments (E) greater than i
4.25 w/o U-235 and less than or equal to 5.0 w/o U-235 which contain a minimum number of Integral Fuel Burnable Absorber (IFBA) pins.
This minimum number of IFBA oins shall have an equivalent reactivity hold-down which is greater than or equal to the reactivity hold down associated with N IFBA pins, at a nominal j
2.35 mg B-10/ linear inch loading (1.5X), determined by the equation below:
l N = 42.67 ( E - 4.25 )
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 distarne 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 (non-flux trap) racks.
d.
Fuel assemblies storea 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.
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, l
may only be stored in the peripheral cells facing the concrete wall.
i SALEM - UNIT 2 5-5 Amendment No.204 l
E DESIGN FEATURES 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, which contain a minimum number of Integral Fuel Burnable Absorber (IFBA) pins have unrestricted storage.
This minimum number of IFBA pins shall have an equivalent
. reactivity hold-down which is greater than or equal to the reactivity hold down associated with N IFBA pins, at a nominal 2.35 mg B-10/ linear inch loading-(1.5X), determined,by the equation below:
N = 42;67 ( E - 4.25 )
l
'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 below, have unrestricted stcrage.
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 - 0.7036E8
-In this configuration, none of the nine cells in any 3x3 array shall.be common to cells in any other similar 3x3 l~
array. Along the rack periphery, the concrete wall is l
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 I
determined by the equation below, have unrestricted storage.
I J
BU (MWD /kg U) = -32. 06 + 25. 21E - 3. 72 3E2 + 0.3535L' SALEM - UNIT 2 5-Sa Amendment No.204
DESIGN FEATURES I
4.
Irradiated fuel assemblies with a maximum enrichre.nt (E) of 5.0 h/o U-235 that 'have attained the minimum burnup
(. U) as determined by the B
equation below, may be storec in a peripheral cell facing the concrete wall'.
BU (MWD /kg U) = - 25.56 + 15.14E - 0.602E2 DRAINAGE 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.
'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-Sb Amendment No. 204 I.
.