ML20056E002
| ML20056E002 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/02/1993 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056E003 | List: |
| References | |
| NUDOCS 9308190172 | |
| Download: ML20056E002 (14) | |
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NUCLEAR REGULATORY COMMISSION 8
WASHINGTON. D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE0VOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACillTY OPERATING LICENSE ~
Amendment No.169 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 March 1, 1993, and amended by letter dated June 16, 1993, corolies 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 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.
E 9308190172 930802 PDR ADOCK 05000327 P
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Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment a
and paragraph 2.C.(2) of facility Operating License No. DPR-77 is hereby amended to read as follows (2) Technical Specifications j
1 The Technical Specifications contained in Appendices A and B, as I
revised through Amendment No. 169, are hereby incorporated in the license. The licensee shall operate the facility in accordance with j
the Technical Specifications, 3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days.
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FOR THE NUCLEAR REGULATORY COMMISSION u
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,p Frederick J. HebVon, Director Project Directorate 11-4 Division of Reactor Projects - I/II I
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical j
Specifications i
f Date of Issuance: August 2,1993 I
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t ATTACHMENT TO LICENSE AMENDMENT NO.169 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 i
Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are f
identified by the captioned amendment number and contain marginal lines indicating the area of change.
t REMOVE INSERT l-4 1-4 6-20 6-20 6-25 6-25 6-26 6-26 i
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1, b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE. or c.
Reactor coolant system leakage through a ste,m generator to the secondary system.
MEMBER (S) 0F THE PUBLIC 1.17 MEMBERS OF THE PUBLIC shall include all individuals who are not occupationally associated with the plant. This category shall include non employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category does not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the -licensee fo.' purposes of protection of individuals from exposure te radiation and radioactive materials.
OFFSITE DOSE CALCULATION MANUAL (ODCH) 1.18 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous-and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radio-logical Environmental Monitoring Programs required by Section 6.8.5 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications l
6.9.1.6 and 6.9.1.8.
OPERABLE - OPERABILITY 1.19 A system st system, train. or component or device shall De OPERABLE or have OPERABILITY when '.t is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, a normal and an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE - MODE
'i 1.20 An OPERATIONAL MODE (i.e.. H0DE) shall correspond to any one inclusive combination of core reactivity condition. power level and average reactor coolant temperature specified in Table 11.
EESKLLE.515 1.21 FHYS' TESTS shall be those tests performed to measure the fundamental nuclear charactern as of the reactor core and related instrumentation and 1) described in a
Chapter 14.0 of the FSAR 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise cpproved by the Commissipn.
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SEQUOYAH - UNIT 1 14 Amendment No. 12. 71,'148. 155,.169 1
r f,DMINISTRATIVECONTROLS (describe maintenance).. waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter. TLD. or film badge measure-ments. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
If the results of specific activity analysis in which the primary coolant exceeded thc limits of specification 3.4.8.a. then the following information shall be included along with the results of specific activity analysis results in which the primary coolant exceeded the limits of the specifications: (1) Reactor power history starting 4G hours prior to the first sample in which the limit was exceeded: (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of rae analysis after the radiciodine activity was reduced to less than the limit. Each resalt should include date and time of sampling and the radiciodine concentrations: (3) Ch an-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which t'te limit was exceeded: (4) Graph of the I-131 concentration and one other radiciodine isttope concentration in micro-curies per gram as a function of time for the duration of the specific activity above the steady state level: and (5) The time duration when the specific activity of the j
primary coolant exceeded the radiciodine limit.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2
6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The report shall include sumaries, interpretations and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2. IV.B.3 and IV.C of Appendix I to 10 CFR Part 50.
6.9.1.7 (Relocated to the ODCM.)
ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 2 6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The report shall include a summary of the qucntities of radioactive liquil 3nd gaseous ef fluents and solid waste released from the unit. The material provided sN ' be (1) consistent with the objectiv.cs outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
6.9.1.9 (Relocated to the ODCM or PCP.)
A sin @ submittal may be made for a multiple unit station. The submittal should combine those sections that are comon to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material frorr each unit.
SEQUOYAH - UNIT 1 6 20 Amendment Nos. 42, 58, 74, 117, 148, 169
ADMINISTRATIVE CONTROLS 6.13 PR0cr9 ;0NTROL PROGRAM (PCP) 6.13.1 Cnanges to the PCP.
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.p.
This documentation shall contain.
a.
sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.
a determination that the change will maintain the overall conformance of' l
the solidified waste product to existing requirements of Federal. State, or other applicable regulations.
2.
Shall become effective after review and approval in accordance with Section 6.5.1A.
6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 Changes to the ODCH:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.p.
This documentation shall contain:
a.
Sufficient information to support the change together with the -
appropriate analyses or evaluations justifying the change (s) and b.
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190. 10 CFR 50.36a. and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
2.
Shall become effective after review and acceptance by the SON RARC.
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3.
Shall be submitted to the Commission in the form of a complete. legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive l
Effluent Release Report for the period of the report in which any change to the ODCM was made. Each. change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was' implemented.
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l SEQUOYAH UNIT 1 6 25 Amencent Nos. 42. 58. 74. 148, 169 h
ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADIDACTIVE WASTE TREATHENT SYSTEMS (Liquid. Gaseous and Solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid.
gaseous and solid):*
1.
Shall be reported to the Commission in the Annual Radioactive Effluent Release l
Report for the period in which the evaluation was reviewed in accordance with Section 6.5.1A. The discussion of each change shall contain:
a.
A summary of the evaluation that led to the determination that the change t
could be made in accordance with 10 CFR 50.59:
b, sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.
a detailed description of the equipment, components and processes involved and the interfaces with other plant systems:
d.
an evaluation for the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of
'5 solid waste that differ from those previously predicted in the license application and amendments thereto; e.
an evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto:
f.
a comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste to the actual releases for the period prior to when the changes are to be made:
g.
an estimate of the exposure to plant operating personnel as a result of the change; and h.
documentation of the fact that the change was reviewed and found acceptable in accordance with Section 6.5.1A.
2, Shall become effective upon review and acceptance in accordance with Section 6.5.1A.
- Submittal of information required by this section may be made as part of the annual FSAR update.
SEQUOYAH : UNIT 1 6 26 Amendment Nos. 58. 74. 42. 148, 169
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NUCLEAR REGULA?0RY COMMISSION S
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t TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACillTY OPERATING LICENSE i
Amendment No.159 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 1, 1993, and amended by letter dated June 16, i
1993, complies with the standards and requirements of the Atomic i
Energy Act of 1954, as amended (the Act), and the Commission's rules and regulatione se' forth in 10 CFR Chapter I; 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; 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.
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I 2.
Accordingly, the license is amended by changes -to the Technical i
Specifications as indicated in the attachment to this license amendment and paragraph 2.C'(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as j
revised through Amendment No. 159, are hereby incorporated in the=
license.
The licensee shall operate the facility in accordance with 6
the Technical Specifications, i
-I 3.
This license amendment is effective as of its date of issuance, to _be j
implemented within 30 days.
I FOR THE NUCLEAR REGULATORY COMMISSION
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Frederick J. Hebdon, Director i
Project Directorate 11-4~
Division of Reactor Projects - I/11-Office of Nuclear Reactor Regulation
Attachment:
Changes to the. Technical Specifications Date of Issuance: August 2, 1993 b
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N
l' ATTACHMENT TO LICENSE AMENDMENT NO. 159 r
[ACILITY OPERATING LICENSE NO. DpR-79
-l 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 i
indicating the area of change.
-l REMOVE INSERT l-4 1-4 6-21 6-21 i
6-26 6-26 6-27 6-27 i
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i 4.4.
II
DEFINITIONS IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be:
Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or a.
valve packing leaks that are captured and conducted to a sump or collecting tank, or b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or Reactor coolant system leakage through a steam generator to the secondary c.
system.
MEMBERS OF THE PUBLIC 1.17 HEMBERS OF THE PUBLIC shall include all individuals who are not occupationally associated with the plant. This category shall include non employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category does not include non-employees such a vending machine servicemen or postmen who. as part of their formal job function, occasionally er.ter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.
1 0FFSITE DOSE CALCULATION MANUAL 1.18 The OFFSITE DOSE CALCULATION MANUAL (ODCH) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring i
alarm / trip setpoints and in the conduct of the Radiological Environmental Monitoring t
Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radio-logical Environmental Monitoring Programs required by Section 6.8.5 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operatirg and Annual Radioactive Effluent Release Reports required by Specifications l
6.9.1.6 and 6.9.1.8.
OPERABLE - OPERABILITY 1.19 A system subsystem. train, or component or device shall be OPERABLE or have t
OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation. controls, a normal and an emergency electrical power source cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s),
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i SEQUOYAH UNIT 2 14 Amendment No. 63, 134. 146, 159
ADMINISTR E CONTROLS i
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives cutlined in (1) the ODCH and (2) Sections IV.B.2 IV.B.3. and IV.C of Appendix I to 10 CFR Part' 50.
6.9.1.7 (Relocated to the ODCH.)
ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCH and PCP and (2) in conformance with j
10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
i 6.9.1.9 (Relocated to the ODCH or PCP.)
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1 A single submittal may be made for a multiple unit station. The submittal should combine those sections that a're common to all units at the station: however..for units with separate radwaste systems, the submittal shall specify the releases of -
radioactive material from each unit.
SEQUOYAH UNIT 2 6 21 Amendment No. 34, 50, 66, 107, 134, 159 -
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ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2p. This documentation shall contain:
a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
2.
Shall become effective after review and approval in accordance with Section 6.5.1A.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCH:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2p. This documentation shall contain:
a.
Sufficient informat. ion to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190. 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent. dose, or setpoint calculations.
2.
Shall become effective after review and acceptance by the SON RARC.
3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive l
Effluent Release Report for the period of the report in which any change to the ODCH was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed. and shall indicate the date (e.g., month / year) the change was implemented.
- SEQUOYAH'- UNIT 2 6 26 Amendment No. 34, 50. 66, 134,' 159
ADMINISTRATIVE CONTROLS 6.15 - MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid. Gaseous and Solid)
.6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):*
1.
Shall be reported to the Commission in the Annual Radioactive Effluent Report l
for the period in which the evaluation was reviewed in accordance with Section 6.5.1A.
The discussion of each change shall contain:
a.
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59:
b.
sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information:
c.
a detailed description of the equipment components and processes involved and the interfaces with other plant systems:
d.
an evaluation for the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; e.
an evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto:
f.
a comparison of the, predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste to the actual releases for the period prior to when the changes are to be made:
g.
an estimate of the exposure to plant operating personnel as a result of the change: and h.
documentation of the fact that the change was reviewed and found acceptable in accordance with Section 6.5.1A.
2.
Shall become effective upon review and acceptance in accordance with Section 6.5.1A.
- Submittal of information required by this section may be made as part of the annual FSAR update.
SEQUOYAH - UNIT 2 6 27
. Amendment No. 34. 50. 66. 134, 159