ML20118C048
| ML20118C048 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/28/1992 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20118C049 | List: |
| References | |
| NUDOCS 9210090155 | |
| Download: ML20118C048 (12) | |
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TENNESSEE VALLEY AUTHORITY QOCKET NO. 50-327 EE0V0YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.163 License No, OPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 28, 1992, and modified by letter dated July 14, 1992, 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; D.
The issuance of this amendment will not be itiimical 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 tave been satisfied.
9210090155 920920 gpR ADocK0500{y7 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment
- nd paragraph 2.C.(2) of facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Ischnical Soecifications The lechnical Specifications contained in Appendices A and B, as revised through Amendment ho.163, 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, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
, Asbva I
(
Frederick J. Hebdon, Director Projec* Directorate 11-4 t-Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
September 28, 1992 T
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ATTACHMENT TO LICENSE AMENDMENT NO.163 FACillTY OPEPATING LICENSE NO. DPR-77 QQLKET NO. 50-327 Revise the Appendix A Technical Specifications by removirg 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.
REMOVE LNJERI 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 3-4 6-23 3/4 6-23
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ADMINISTRATIVE CONia0LS 6.2.3 INDEPENDENTSAFETYENGINEERING(ISE}
FUNCTION 6.2.3.1 The ISE shall function to examine plant operating characteristics, NRC iscuances, industry advisories, Licensee Event Reports and other sources l
which may indicate areas for improving plant safety.
j COMPOSITION 6.2.3.2 The ISE shall be composed of at least 3 dedicated full-time engineers located onsite.
These engineers elli 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 activities to provide independent verification
- that these activitics are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The ISE shall make detailed recommendations for revised procedures, equipment modifications, or other means of improving plant safety to the Manager, Nuclear Experience Review / Independent Safety Engineering.
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 except for the-Site l
Radiological Control Manager who shall meet or exceed the qualifications of.
Regulatory Guide 1.8, September 1975.
- Not responsible for sign-off function.
I SEQUOYAH - UNIT 1 6-5 Amendment No. 12, 58, 74, 119, 152, 163 i
- - - - - ~ - --
ADM!NISTRATIVE 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 Plant Manager 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 shall include familiarization with l
relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.0 The Senior Vice President, Nuclear Power is responsible for the safe operation of all TVA power plants.
65._1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
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- 7.5 *,
iwi iM: si1all function to advise the Plant Manager on all matters tw o e.
Lu nuclear safety.
COMP 05:Tj0N 6.5.1.2 The PORC shall be composed of the:
Chairman:
Plant Manager Member:
Operations Manager Member:
Site Radiological Control Manager Member:
Maintenance Manager Member:
Technical Support Manager Member:
Quality Audit and Monitoring Manager l
Member:
Nuclear Engineering Representative l
SEQUOYAH - UNIT 1 6-6 Amendment No. 58, 74, 152 163
ADMINISTRAVIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Unit Operating License:
a.
Records and drawing changes reflecting unit design modifications made to systems and equipment described in tha Final Safety Analysis Report, b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
Records of radiation exposure for all individuals entering radiation c.
control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
e.
Records of transient or operational cycles for those unit components identified in Table 5.7-1.
f.
Records of reactor tests and experiments, g.
Records of training and qualification for current members of the facility staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required for lifetime reten-tion by the Nuclear Quality Assurance Plan.
l j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PORC, SQN RARC, and the NSRB.
1.
Records of analybes required by the radiological environmental monitoring program, m.
Records of secondary water sampling and water quality, n.
Records of the service life monitoring of all safety-r61ated hydraulic and mechanical snubbers, required by T/S 3.7.9, including the main-tenance performed to renew the service life, o.
Records for Environmental Qualification which are covered under the provisions of Paragraph 2.c.(12)(b) of License No. DPR-77.
p.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
SEQUOYAH - UNIT 1 6-23 Amendment No. 42, 58, 74, 148 163
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NUCLEAR REGULATORY COMMISSION WAsHINoTON, D C. 20!65 o.
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- s TENf4ESSEE VALLEY AUTHORITY DOCKET NO. 50-328 E 000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATif4G LICENSE Amendment No. 153 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 28, 1992, and modified by letter dated July 14, 1992, 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; D.
The issuance of this amendment will not be inimical to the common defensa 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 indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 '.s hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.153, are hereby incorporated in the license.
The licensee > hall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be impicmented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION cshu,3
')lde Frederick J. Heb@)n, Director e
Project Directorate 11-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 28, 1992 k
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I ATTACHMENT 10 llCENSE AMENDMENT NO.153 FACILITY OPERATING llCENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing tlie 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.
RIMYl IMIRI 3/4 6-5 3/4 6-5 t
3/4 6-6 3/4 6-6 3-4 6-24 3/4 6-24 I
s 5
ADMINISTRAT8VE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING (ISE)
FUNCTION 6.2.3.1 The ISE shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Repcrts and f,ther 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 nuchar sites to achieve an equivalent staffing of 5 full-time engineers performin the ISE functions applicable to Sequoyah.
RESPONSIBILITIES 6.2.3.3 The ISE shall be responsible for maintaining surveillance.of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The ISE shall make detailed recommendations for revised procedures, equipment modifications, or other means of improving plant safety to the Manager, Nuclear Experience Review / Independent Safety Engineering.
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 qualifications of ANSI N18.1-1971 for comparable positions except for the l
Site Radiological Control Manager 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, 142 153
]
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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 l'1 ant Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 l
and Appendix "A" of 10 CFR Part 55 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 tc 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 Manager Member:
Site Radiological Control Manager Member:
Maintenance Manager Member:
Technical Support Manager Member:
Quality Audit and Monitoring Manager Member:
Nuclear Engineering Representative j
SEQUOYAM - UNIT 2 6-6 Amendment No. 50, 66, 142 153
ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Unit Operating License:
a.
Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories, Records of radiation exposure for all individuals entering radiation c.
control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
Records of transient or operational cycles-for those unit components e.
identified in Table 5.7-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the facility staff.
h.
Records of in-service inspections performed pursuant to these Technical Specificat'ons, i.
Records of Quality Assurance activities required for lifetime reten-tion by the Nuclear Quality Assurance Plan.
l j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PORC, SQN RARC, and the NSRB.
1.
Records of analyses required by the radiological environmental -
monitoring program.
m.
Records of secondary water sampling and water quality, n.
Records of the service life monitoring of all safety-related hy-draulic and mechanical snubbers, required by T/S 3.7.9, including the maintenance performed to-renew the service life.
o.
Records for environmental qualification which are covered under the provisions of paragraph 2.C.(10)(b) of license No. OPR-79.
p.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
SEQUOYAH - UNIT 2 6-24 Amendment M. 28, 50, 66, 134 153
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