ML17158A744
| ML17158A744 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/19/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Pennsylvania Power & Light Co, Allegheny Electric Cooperative |
| Shared Package | |
| ML17158A745 | List: |
| References | |
| NPF-14-A-147, NPF-22-A-117 NUDOCS 9507030050 | |
| Download: ML17158A744 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PEN SY VANIA PO ER EE LIGHT CO PANY L
EGH ECTRIC COOP T
INC
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-33 SUS UEHANNA ST AM ELECTRIC STATION UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 147 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having'ound that:
A.
The application for the amendment filed by the Pennsylvania Power 8I
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Light Company, dated October 28,
- 1994, as supplemented April 18,
- 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 sat3:jfi.'ed; 9507030050 9506i9'DR ADOCK 05000387 t
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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 the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technic 1
S ecifications and Environ ental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
147 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION o
F. Stolz, Director Pr ject Directorate I-ivision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 19, 1995
ENT TO LICENSE AME DMENT NO.
F C
ITY OPERATING LICENSE NO. NPF-14 DDKKDK DD.
DD-DD Replace the following pages of the Appendix A Technical Specifications with attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
~RH~
~RS RT 3/4 3-76 B 3/4 3-5 3/4 3-76 B 3/4 3-5
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LIMITINGCONDITION FOR OPERATION 3.3.7.8 DELETED SUSQUEHANNA - UNIT 1 3/4 3-76 Amendment No. 7', 147
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BASES The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs, February, 1972.
The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
The OPERABILITYof the accident monitoring instrumentation ensures that sufficient information.
is available on selected plant parameters to monitor and assess important variables following an ~
accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97,-:
"Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions:,"
During and Following an Accident," December 1975 and NUREG-0578, "TMI-2Lessons Learned Task Force Status Report and Short-Term Recommendations",
The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions should not be made without this flux level information available to the operator.
When the intermediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.
SUSQUEHANNA - UNIT 1 B 3/4 3-5 Amendment No.
~47
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASH INGT0 N 0 D C 205554001 P
S ANIA POWER 5 LIGHT COMPANY 5
A EGHE Y ELECTRIC COOP RAT V NC
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ECTR C STAT 0 UNIT 2 AMENDMENT TO FACILITY OP TING LICENSE Amendment No.
117 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power III ~0 Light Company, dated October 28,
- 1994, as supplemented April 18,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulation's set
'orth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the 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 IO CFR Part 51 of the Commission's regulations and all applicable requirements have been sati s'f,i'e'd.
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- 00 QK
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 the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2) Techn c
1 S ec c t The Technical Specifications contained in Appendix A, as revised through Amendment No. ]17 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPKL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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me ta te t o 1
FOR THE NUCLEAR REGULATORY CONHISSION J
F. Stolz, Direct r P
ject Directorate 2
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
J~e ] 9
] 995 3.
This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.
TAC M NT TO LICENS AMENDMENT NO. 117 F
G IT OP RATING LICENSE NO.
NPF-
~KT 0.
8 Replace the following pages of the Appendix A Technical Specifications with attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
~R~O
~N~R 3/4 3-76 B 3/4 3-5 3/4 3-76 B 3/4 3-5
LIMITINGCONDlTION FOR OPERATION 3.3.V.S DELETED SUSQUEHANNA - UNIT2 3/4 3-76 Amendment No. 49, 117
BASES The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," February, 1972.
The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
The OPERABILITYof the accident monitoring instrumentation ensures that sufficient information, is available on selected plant parameters to monitor and assess important variables following an g<
accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97,"-:
"Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions
.'uring and Following an Accident," December 1975 and NUREG-0578, "TMI-2Lessons Learned Task Force Status Report and Short-Term Recommendations":
The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions should not be made without this flux level information available to the operator.
When the intermediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.
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SUSQUEHANNA - UNIT 2 B 3/4 3-5 Amendment No. 117