ML20078K106
| ML20078K106 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/08/1994 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20078K112 | List: |
| References | |
| DPR-70-A-160, DPR-75-A-141 NUDOCS 9411220325 | |
| Download: ML20078K106 (12) | |
Text
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA EL:CTRIC COMPANY 1
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.160 License No. DPR !
1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found f
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 June 13, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), aH the Commission's rules and regulations set forth in 10 CFR Chapter.;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i
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 -
i satisfied.
2.
Accordingly, the license is amended by changes to the Te:hnical 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 i
amended to read as follows:
9411220325 941108 PDR ADOCK 05000272 P
PDR 4
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.160, 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
.J hn F. Stolz,41 rector
' roject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 8, 1994
ATTACHMENT TO LICENSE AMENDMENT NO.160 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Pages Insert Paaes 3/4 0-2 3/4 0-2 B 3/4 0-4a B 3/4 0-5 8 3/4 0-5 i
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APPLICABILITY l
LIMITING CONDITION FOR OPER^ATION 3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purposs-of satisfying the requirements of its applicable limiting Condition for Cperation, provided: (1) its corresponding normal or emergency power source it OPERABLE; and (2) all of its redundant system (s),
subsystem (s), train (s), coaponent (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply, by placing it, as applicable, in:
1.
At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This specification is not applicable in MODES 5 or 6.
3.0.6 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY c f other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
a SALEM - UNIT 1 3 '4 0-2 Amendment No. 137, 160 l
1 APPLICABILITY BASES
....................r.........................................................
in the other division trust be OPERABLE, or likewise satisfy Specification 3.0.5 (i.e.,
be capable of performing their design functions and have an emergency power source OPERABLE).
In other words, both emergency power sources must b. OPERABLE and all redundant systems, subsystems, trains, components ant
' ices in both divisions must also be OPERABLE.
If these i
conditions are u.c satisfied, action is required in accordance with this specification.
In MODES 5 or 6 Specification 3.0.5 is not applicable, and thus the individual ACTION stater ents for each applicable Limiting Condition for Operation in these MODES must be adhered to.
Specification 3.0.6 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LCO 3.0.2 (e.g.,
to not comply with the applicable Required Action (s)) to allow the performance of testing required to restore and demonstrate:
a.
The OPERABILITY of the equipment being returned to service; or b.
The OPERABILITY of other equipment.
The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary te perform the testing required to restore and i
demonstrate the operability of the equipment. This Specification does not provide time to perform any other preventive or corrective maintenance.
An example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the testing required to restore and demonstrace OPERABILITY.
An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of testing required to restore OPERABILITY of another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of testing required to restore and demonstrate the OPERABILITY of another channel in the same trip system.
i t
5 i
SALEM - UNIT 1 B 3/4 0-4a Amendment No.160 r
w
-n
APPLICABILITY _
BASES Specifications 4.0.1 throuch 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR
- 50. 36 (c) (3) :
" Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility ope ation will be within safety limits, and that the limiting conditions of operation will be met."
Specification 4.0 1 establishes the requirement that surveillances must be performed during the OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.
The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in i
a MODE or other specified condition for which the associated Limiting conditions for Operation are applicable.
Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.
The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.
4.0.2 Specification 4.0.2 establishes the limit for which the specified time interval for Surveillance Requirements may be extended.
It permits an allowable extension of the normal surveillance interval to facil:. tate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.,
transient conditions or other ongoing surveillance or maintenance activities.
It also e
provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18 month surveillance interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
The limitation of Specification 4.0.2 is based on engineering judgment and the recognition that the most probable result of any b
SALEM - UNIT 1 B 3/4 0-5 Amendment No.13I,160
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4 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 206 % 4 001 l
+...+,&
l 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.141 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 June 13, 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, 1
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: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) thi.t 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-75 is hereby amended to read as follows:
l 9 1 l
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.141, 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 i
be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
[1 Jo R F. Stolz, Direct Pr ject Directorate
-2 l
ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachment-Changes to the Technical Specifications Date of Issuance: November 8, 1994 1
l P
ATTACHMENT TO LICENSE AMENDMENT N0.141 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paoes 3/4 0-2 3/t 0-2 B 3/4 0-Aa B 3/4 0-5 8 3/4 0-5 1
i E
k I
6 I
l APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable l
limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s),
subsystem (s), train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply, by placing it, as applicable, in:
1.
At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This specification is not applicable in MODES 5 or 6.
3.0.6 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
F i
SALEM - UNIT 2 3/4 0-2 Amendment No.II@,141 l
APPLICABILITY BASES i
in the other division must be OPERABLE, or likewise satisfy Specification
[
3.0.5 (i.e.,
be capable of performing their design functions and have an emergency power source OPERABLE).
In other words, both emergency power sources must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE.
If these conditions are not satisfied, action is required in accordance with this specification.
In MODES 5 or 6 Specification 3.0.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.
l t
Soecification 3.0,6 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LCO 3.0.2 (e.g.,
to not comply with the applicable Required Action (s)) to allow the performance of testing
~
required to restore and demonstrate:
a.
The OPERABILITY of the equipment being returned to service; or b.
The OPERABILITY of other equipment.
The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the testing required to restore and demonstrate the operability of the equipment.
This Specification does not provide time to perform any other preventive or corrective maintenance.
An example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the testing required to restore and demonstrate OPERABILITY.
An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of testing required to restore OPERABILITY of another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of testing required to restore and demonstrate the OPERABILITY of another channel in the same trip system.
SALEM - UNIT 2 B 3/4 0-4a Amendment No.101
+
4 s--,
w
h APPLICABILITY BASES
r===========================================================================
I Specifications 4.0.1 throuch 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR
- 50. 36 (c) (3) :
" Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditione of operation will be met."
Soecification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable.
Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do net apply unless otherwise specified.
The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.
4.0.2 Specification 4.0.2 establishes the limit for which the specified time interval for Surveillance Requirements may be extended.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.,
transient conditions or other ongoing surveillance or maintenance activities.
It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18 month surveillance interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. The limitation of Specification 4.0.2 is based on engineering judgment and the recognition that the most probable result of any a
r t
SALEM - UNIT 2 B 3/4 0-5 7.mendment No. Il@,141
,