ML20078D708
| ML20078D708 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/24/1995 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078D717 | List: |
| References | |
| NUDOCS 9501300193 | |
| Download: ML20078D708 (8) | |
Text
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t UNITED STATES NUCLEAR REGULATORY COMMISSION i
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WASHINGTON, D.C. 20666 4001
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT. UNIT 1 l
AMENDMENT TO FACILITY OPERATING LICENSE i
l Amendment No. 194 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the i
licensee) dated January 3, 1995, complies with the standards and l
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chaptar 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 l
conducted in compliance with the Comission's regulations; 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 j
of the Comission's regulations and all applicable requirements have been satisfied.
l 9501300193 950124 PDR ADOCK 05000327 p
PDR l
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' 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-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in A)pendices A and B, as revised through Amendment No.194, are here)y incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance, to be l
implemented upon receipt.
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FOR THE NUCLEAR REGULATORY COMMISSION l
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Frederick J. Hebh n, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 24, 1995
i ATTACHMENT 70 LICENSE AMENDMENT NO.194 FACILITYOPERATING,LICENSENO.DPR-77 DOCKET N0. 50-327 i
Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised page is identified by the captioned amendment number and contains marginal lines indicating the area of change.
REMOVE INSERT 3/4 9-7 3/4 9-7 l
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i EE. FUELING OPERATIONS 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA LIMITING CONDITION FOR OPERATION 3.9.7 Loads traveling over fuel assemblies in the spent fuel pit area shall be restricted as follow.;:
a.
Spent fuel storage pool:
Loads in excess of 2100 pounds
- shall be prohibited from travel over fuel assemblies in the spent fuel storage pool.
i b.
Cask loading area of the cask pit:
1.
Loads which meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 may be carried i
over fuel assemblies stored in the cask loading area of the cask pit if the impact shield is in place over the cask loading area.
2.
Loads which do not meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 shall be prohibited from travel over the cask loading area of the cask pit when fuel is stored in it.
APPLICABILITY: With fuel assemblies in the spent fuel storage pool or in the cask loading area of the cask pit.
ACTION:
With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.
SVRVEILLANCE RE0VIREMENTS 4.9.7.1 Crane interlocks and physical stops dich prevent crane hook travel over the storage pool shall be demonstrated UPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation.#
l 4.9.7.2 When fuel is stored in the cask pit area, verify administrative requirements concerning the impact shield are met prinr to moving loads in excess of 2100 pounds across the cask pit area.
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- The spent fuel pool transfer canal gate and the spent fuel pool divider gate may travel over fuel assemblies in the spent fuel pool.
- The crane interlocks and paysical stops may be defeated for activities associated with the spent fuel pit rerack project.
SEQUOYAH - UNIT 1 3/4 9-7 Amendment No. 91, 167, 194
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20565 4001 l
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TENNESSEE VALLEY AUTHORITY l
DOCKET N0. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
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l Amendment No.185 l
License No. DPR-79 I
l 1.
The Nuclecr Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated January 3,1995, 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 i
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; 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.
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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. OPR-79 is hereby amended to read as follows:
l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.185, are hereby incorporated in the license. The licensee shall operate the facility in accordance 4
with the Technical Specifications.
3.
~his license amendment is effective as of its date of issuance, to be implemented upon receipt.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Heb on, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance: January 24, 1995 i
1 l
I i
f ATTACHMENT TO LICENSE AMENDMENT NO. 185 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix 1 Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised page is identified by the captioned amendment number and contains marginal lines indicating the area of change.
REMOVE INSERT l
3/4 9-8 3/4 9-8 i
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REFUELING OPERATIONS j
3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA l
LIMITING CONDITION FOR OPERATION 3.9.7 Loads traveling over fuel assemblies in the spent fuel pit area shall be restricted as follows:
l a.
Spent fuel storage pool:
i j
Loads in excess of 2100 pounds
- shall be prohibited from travel over fuel assemblies in the spent fuel storage pool.
b.
Cask loading area of the cask pit:
1.
Loads which meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 may be carried i
i over fuel assemblies stored in the cask loading area of the cask pit if the impact shield is in place over the cask loading area.
2.
Loads which do not meet the weight, cross-sectional impact area, and allowable travel height criteria of Figure 3.9-1 shall be prohibited from travel over the cask loading area of the cask pit when fuel is stored in it.
APPLICABILITY: With fuel assemblies in the spent fuel storage pool or in the cask loading area of the cask pit.
ACTION:
With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.9.7.1 Crane interlocks and physical stops which prevent crane hook travel l
over the storage pool shall be demonstrated OPERABLE within 7 days prior to l
crane use and at least once per 7 days thereafter during crane operation.#
I 4.9.7.2 When fuel is stored in the cask pit area, verify administrative requirements concerning the impact shield are met prior to moving loads in excess of 2100 pounds across the cask pit area.
l
- The spent fuel pool tre.7sfer canal gate and the spent fuel pool divider gate may travel over fuel assemblies in the spent fuel pool.
- The crane interlocks and physical stops may be defeatea for activities associated with the spent fuel pit rerack project.
1 SEQUOYAH - UNIT 2 3/4 9-8 Amendment No. 81, 157, 185