ML20246E398
| ML20246E398 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/05/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246E402 | List: |
| References | |
| NUDOCS 8907120225 | |
| Download: ML20246E398 (10) | |
Text
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NUCLEAR REGULATORY COMMISSION i
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i TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee)datedApril 17, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security cr 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 Comission's regulations and all applicable requirements have been satisfied.
1 8907120225 890705 PDR ADOCK 05000327 P
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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 pardgraph 2.C.(2) of Facility Operating License No. OPR-77 is hereby l
amended to redd as follows:
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-(2) Technical Specifications
.The Technical Specifications contained in Appendices A and B, as revised.through Amendment No.119, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 60 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'i Cd A
Suzanne ack, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Oate of Issuance: July 5,1939
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ATTACHMENT TO LICENSE AMENDMENT NO. 119 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 l
Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain merginal lines indicating the. area of change. Overleaf pages* are provided to amintain document completeness.
REMOVE INSERT 6-5 6-5 6-6 6-6*
l l
i 1
. _ - - - _ ~ _ - - - - _ - _ - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
4 1
ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING ('ISE)
FUNCTION 1
6.2.3.1.The ISE shall function to examine plant operating characteristics, l
NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety,
)
COMPOSITION 4
6.2.3.2. The ISE shall be composed of at least 3 dedicated full-time engineers located onsite.
These engineers will be supplemented as necessary by full-time engineers shared among all TVA nuclear sites to achieve an equivalent staffing of.5 full-time engineers performing the ISE functions applicable to Sequoyah.
RESPONSIBILITIES 6.2.3.3 The ISE shall be responsible for maintaining surveillance of plant l
activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
4 AUTHORITY 6.2.3.4 The ISE shall make detailed recommendations for revised procedures, l
equipment modifications, or other means of improving plant safety to the Manager of Nuclear Managers Review Group.
l
~ 6. 2. 4 SHIFT TECHNICAL ADVISOR (STA)
- 6.2.4.1 The STA shall serve in an advisory capacity to the shift supervisor on matters pertaining to the engineering aspects of assuring safe operation of the unit.
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all ' licensees, except for the Site Radiological Control Super-intendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
- Not responsible for sign-off function.
SEQUOYAH - UNIT 1 6-5 Amendment No. 12, 58, 74, 119
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i ADA NISTRATIVE CONTROLS 6.4. TRAINING 6.4.1 A retraining and replacement training program for the facility sta< f shall.be maintained under the direction of the Operations Superintendent and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.0 The. Senior Vice President, Nuclear Powei u responsible for the safe operation of all TVA power plants.
6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION
- 6. 5.1.' 1 The PORC shall function to advise the Plant Manager on all matters l,
related to nuclear safety.
L
. COMPOSITION l
6.5.1.2 The PORC shall be composed of the:
Chairman:
Plant Manager Member:~
Operations Superintendent Member:
Operations Manager Member:
Site Radiological Control Superintendent Member:~
Maintenance Superintendent Member:
Technical Support Superintendent Member:
Quality Engineering Manager Member:
Division of Nuclear Engineering Representative SEQUOYAH - UNIT 1 6-6 Amendment No. 58, 74
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TENNESSEE VALLEY' AUTHORITY 00CKET NO. 50-328 i
SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 108 License No. DPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 17, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended.(the Act),
and the Comission's rules and regul6tions 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 Comission; I
C.
There is reascnable assurance (1) that the activities authorized by l
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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendmerit is in accordance with 10 CFR Part 51 i
l of the Comission's regulations and all applicable requirements have l
been satisfied.
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.. 2..
Accordingly, the license is amehded 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.108, are tereby incorporated in the license. The licensee shall operate the facility.in accordance wit.
the Technical Specifications.
3.
This license amendment is effective 60 days after its date~ of' issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
.7 ct-v v w 4._
ACk Suzanne.
ack, Assistant Director for Projects TVA Projects Division Office of Nucledr Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 5, 1989 l
l
ATTACHMENT TO LICENSE AMENDMENT NO.108 FACILITY OPERATlhG LICENSE NO. OPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to i
maintain document completeness.
I REMOVE INSERT 6-5 6-5 6-6 6-6*
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. _ _ _ _. _ _ _ _. _ - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ ^ ^ ~
- - - ' ^ - ^ ~
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' ADMINISTRATIVE CONTROLS
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6.2.3. INDEPENDENT SAFETY ENGINEERING (ISE)
L FUNCTION
\\
6.2.3.1 The ISE shall function to examine plant operating characteristics, l
NRC issuances, industry advisories Licensee Event Reports and other sources which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISE shall be composed of at least 3 dedicated full-time engineers located onsite.
These engineers will be supplemented as necessary by full-time engineers' shared among all TVA nuclear sites to achieve an equivalent staffing of 5 full-time engineers performing the ISE functions applicable to Sequoyah.
RESPONSIBILITIES 1
6.2.3.3 The ISE shall be responsible for maintaining surveillance of plant l
activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY l
6.2.3.4 The ISE shall make detailed recommendations for revised procedures, l
quipment modifications, or other means of improving plant safety to the Manager of Nuclear Managers Review Group.
[
6.2.4 SHIFT TECHNICAL ADVISOR (STA) 6.2.4.1 The STA shall serve in an advisory capacity to the shif t supervisor on matters pertaining to the engineering aspects of assuring safe operation of the unit.
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum
-qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Section A and C of Enclosure 1 of March 28, 1980 NRC letter to all licensees, except for the Site Radiological Control Superintendent who shall meet or exceed the qualifications'of Regulatory Guide 1.8, September 1975.
- Not responsible for sign-off function.
SEQUOYAH - UNIT 2 6-5 Amendment No. 50, 66, 108
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'4-ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and: replacement training program for the facility staff shall be maintained-under the direction of the Operations Superintendent
'and shall. meet or exceed the requirements and recommendations of Section 5.5 of i
ANSI N18.1-1971:and Appendix "A" of 110 CFR Part 55 and the supplemental require-mentsLspecified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.0 Senior Vice President, Nuclear Power is responsible for the safe opera-tion of all TVA power. plants.
-6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION.
6.5.1.1 The PORC shall function to advise the Plant Manager on all matters related.to nuclear safety.
COMPOSITION 6.5.1.2 The PORC shall be composed of the:
Chairman:
' Plant Manager.
Member:
Operations Superintendent Member:
Operations Manager Member:
Site Radiological Control Superintendent Member:
Maintenance Superintendent Member:
Technical' Support Superintendent
- Member:
Quality Engineering Manager Member:
Division of Nuclear Engineering Representative SEQUOYAH - UNIT 2 6-6 Amendment No. 50, 66
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