ML20058L114
| ML20058L114 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/09/1993 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058L118 | List: |
| References | |
| NUDOCS 9312160152 | |
| Download: ML20058L114 (28) | |
Text
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UNITED STATES f.
[ l 4f.2 j
NUCLEAR REGULATORY COMMISSION
- I
'f WASHINGTON. D.C. 20555-0001 4,
,o TENNESSEE VALLEY AUTHORITY DOCKET NO.50-32Z SE000YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 License No. OPR-77 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 16, 1993, 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,
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.
a i
i i
9312160152 931209 PDR ADOCK 05000327 i
P PDR i
l' 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-77 is hereby amended to read as follows:
(2) Iechnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 174, 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.
2 FOR THE NUCLEAR REGULATORY COMMISSION bGMf 0 S0b f%
Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications 1
Date of Issuance: December 9, 1993 i
f i
F
ATTACHMENT TO LICENSE AMENDMENT NO.174 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET N0. 50-327 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.
REMOVE INSERT 1-4 1-4 1-7 1-7 3/4 11-2 3/4 11-2 B3/4 11-1 B3/4 11-1 6-17 6-17 6-18 6-18 6-19 6-19 6-23 6-23 6-24 6-24 6-25 6-25 6-26 6-26 i
n i
1-
b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the
'i operation of leakage detection systems or not to be PRESSURE B0UNDARY LEAKAGE, or c.
Reactor coolant system leakage through a steam generator to the secondary system.
MEMBER (S) 0F THE 591LC 1.17 MEMBER OF THE 'UBLIC means an individual in a controlled or unrestricted area. However, an..dividual is not a member of the public during any period in which the individual receives an occupational dose.
OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.18 The 0FFSITE DOSE LALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active 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 F rogram. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological 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 6.9.1.6 and 6.9.1.8.
OPERABLE - OPERABILITY i
1.19 A system, subsystem, train, or component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessar-attendant instrumentation, controls, a normal and an emergency electrical awer source, cooling or seal water, lubrication or other auxiliary equipment tnat 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 1.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and
- 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
i SEQUOYAH - UNIT I 1-4 Amendment No. 12, 71, 148, 155, 169. 174
UNIDENTIFIED LEAKAGE 1.36 UNIDENTIFIED LEAKAGE shall be all leakage uhich is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
UNRESTRICTED AREA 1.37 UNRESTRICTED AREA shall be any area to which access is neither limited nor controlled by the licensee.
VENTILATION EXHAUST TREATMENT SYSTEM 1.38 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate f
form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).
Engineered Safety Feature (ESF) atmospheric cleanup-systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING l
1.39 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
1 i
SEQUOYAH - UNIT 1 1-7 Amendment No. 12, 71, 155, 174 i
RADI0 ACTIVE EFFLUENTS LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the fol-lowing tanks shall be limited by the following expression:
concentration of isotooe i 33, (effluent concentration s 6,700 limit of isotope 1) i excluding tritium and dissolved or entrained noble gases.
a.
Londensate Storage Tank b.
Steam Generator Layup Tank c.
Outside temporary tanks for radioactive liquid APPLICABILITY: At all times.
t ACTION:
a.
With the quantity of radioactive material in any of the above listed i
tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
SEQUOYAH - UNIT 1 3/4 11-2 Amendment No. 42, 148, 174
1 3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 This specification is deleted.
J 3/4.11.1.2 This specification is deleted.
3/4.11.1.3 This specification is deleted.
3/4.11.1.4 LIOUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the l
specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR 20.1001-20.2401, Appendix B, Table 2, Column 2, at
'l l
the nearest potable water supply and the nearest surface water supply in an unrestricted area.
3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 This specification is deleted.
3/4.11.2.2 This specification is deleted.
3/4.11.2.3 This specification is deleted.
3/4.11.2.4 This specification is deleted.
I SEQUOYAH - UNIT 1 B 3/4 11-1 Amendment No. 42, 148,174
ADMINISTRATIVE CONTROLS i
d.
DELETED t
e.
Postaccident Samolino f
A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.
The program shall include the following:
i (1) Training of personnel, (ii) Procedures for sampling and analysis, (iii)
Provisions for maintenance of sampling and analysis equipment, f.
Radioactive Effluent Controls Procram r
A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the
- ODCH, 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to ten times the concentrations stated in 10 CFR 20.1001-20.2401, Appendix B, Table 2, Column 2, 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the
-l methodology and parameters in the ODCM, 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, i
1 SEQUOYAH - UNIT 1 6-17 Amendment Nos. 12, 32, 58, 74,
)
148, 159, 174
ADMINISTRATIVE CONTROLS l
6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE B0UNDARY SHALL BE LIMITED to the following:
- 1. For noble gases:
Less than or equal to a dose rate of 500 mrem /yr to the total body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and
- 2. For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
Less than i
or equal to a dose rate of 1500 mrem / year to any organ.
8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and
- 10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
g.
Radiolooical Environmental Monitorino Procram A pmgram shall be provided to monitor the radiation and radionuclides in 13:: environs of the plant. The program shall provide (1) repre-sertative measurements of radioactivity in the highest potential. expo-sure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,
- 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE B0UNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and
- 3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
SEQUOYAH - UNIT 1 6-18 Amendment Nos. 12, 32, 58, 74, 148, 174
7 ADMINISTRATIVE CONTROLS I
6.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance with 10 CFR 50.4.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the i
license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
I 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation,. or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
l ANNUAL REPORTS' 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis for the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mre manremexposureaccordingtoworkandjobfunctions,g/yrandtheirassociated e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance l' A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
U This tabulation supplements the requirements of 6 20.2206 of 10 CFR Part 20.
l SEQUOYAH - UNIT 1 6-19 Amendment Nos. 12, 32, 58, 72, 74, 148, 174 j
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ADMINISTRATIVE CONTROLS i
6.10.2 The following records shall be retained for the duration of the Unit Operating License:
i 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 i
burnup histories.
c.
Records of radiation exposure for all individuals entering radiation j
control areas.
d.
Records of gaseous and liquid radioactive material released to the environs and the resulting calculated dose to an individual member of the l
public.
I 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 i
staff.
h.
Records of in-service inspections performed pursuant to these Technical l
Specifications.
l 1.
Records of Quality Assurance activities required for lifetime retention by the Nuclear Quality Assurance Plan.
- j. Records of reviews performed for changes made to procedures or equipment j
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.
t
- a. Records of secondary water sampling and water quality.
n.
Records of the service life monitoring of all safety-related hydraulic 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.(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 Nos. 42, 58, 74, 148, 163, 174
ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each high radiation area in which the intensity of l
radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit * (RWP).
l Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing positive control over the activities within the area and shall perform control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Site Radiological Control Manager in the RWP.
l 6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Site Radiological Control Manager.
- Radiological Control personnel or personnel escorted by Radiological Control personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned 1
]
radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
SEQUOYAH - UNIT 1 6-24 Amendment No. 42, 58, 74, 148, 152, 174 l
i
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) i 6.13.1 Changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained
-t 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 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.lA.
6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 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:
i 1
a.
Sufficient information to support the change together with tae appropriate analyses or. evaluations justifying the change (s).ind b.
A determination that the change will maintain the level of radioactive
)
effluent control pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR l
50.36a, and Appendix I to 10 CFR Part 50 and not adversely impt.ct the.
accuracy or reliability of effluent, dose, or setpoint calcult.tions.
2.
Shall become effective after review and acceptance by the SQN 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 Effluent Release Report for the period of the report in which i
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.
SEQUOYAH - UNIT 1 6-25 Amendment No. 42, 58, 74, 148, 169, 174 1
I 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 I
(liquid, gaseous and solid):**
j 1.
Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed in accordance with Section 6.5.1A.
The discussion of each change shall j
contain:
j 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 i
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 operatir 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.
1 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 FSAR update.
l SEQUOYAH - UNIT 1 6-26 Amendment No. 42, 58, 74, 148, 169, 174
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UNITED STATES
[ h,i%f.h !j NUCLEAR REGULATORY COMMISSION f
WASHINGTON D.C. 20565-0001 s, v /
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 165 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 June 16, 1993, 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; i
C.
There is reascnable 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.
l 1 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 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 165, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with I
the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days.
1 FOR THE NUCLEAR REGULATORY COMMISSION bObY Y. hA Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changas to the Technical Specifications Date of Issuance:
December 9, 1993 i
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t
5 6
ATTACHMENT TO LICENSE AMENDMENT NO. 165 FACILITY OPERATING LICENSE NO. DPR-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.
REMOVE INSERT 1-4 1-4 t
1-7 1-7 3/4 11-2 3/4 11-2 B3/4 11-1 B3/4 11-1 i
6-17 6-17 6-18 6-18 6-20 6-20 f
6-24 6-24 6-25 6-25 6-26 6-26 6-27 6-27 l
t s
t l
DEFINITIONS IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be:
a.
Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or 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 c.
Reactor coolant system leakage through a steam generator to the secondary system.
MEMBER (S) 0F THE PUBLLQ I.17 MEMBER OF THE PUBLIC means an individual in a controlled or unrestricted area. However, an individual is not a member of the public during any period l
in which the individual receives an occupational dose.
j OFFSITE DOSE CALCULATION MANUAL l
1.18 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid i
effluent monitoring alarm / trip setpoints, and in the conduct of the i
Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.5 and (2) descriptions of the information that should be included in the Annual Radiological Environmental 1
Operating and Annual Radioactive Effluent Release Reports required by Specifications 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 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).
l 1
)
SEQUOYAH - UNIT 2 1-Amendment No. 63, 134, 146, 159, 165 w
DEFINITIONS SOLIDIFICATION 1.32 Deleted.
SOURCE CHECK 1.33 Deleted.
STAGGERED TEST BASIS 1.34 A STAGGERED TEST BASIS shall consist of:
- a. A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals,
- b. The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THERMAL POWER 1.35 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNIDENTIFIED LEAKAGE 1.36 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED i
LEAKAGE or CONTROLLED LEAKAGE.
UNRESTRICTED AREA l
l 1.37 UNRESTRICTED AREA shall be any area to which access is neither limited nor controlled by the licensee.
l l
4 l
SEQUOYAH - UNIT 2 1-7 Amendment No. 63, 134, 146, 165
i RADI0 ACTIVE EFFLUENTS LIOUID HOLDUP TANKS i
LIMITING CONDITION FOR OPERATION i
3.11.1.4 The quantity of radioactive material contained in each of the fol-lowing tanks shall be limited by the following expression:
concentration of isotone i Ei (effluent concentration s 6,700 l
limit of isotope 1) excluding tritium and dissolved or entrained noble gases, a.
Condensate Storage Tank i
b.
Stea;n Generator Layup Tank c.
Outside temporary tanks for radioactive liquid i
APPLICABILITY: At all times.
ACTION:
j a.
With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the i
tank contents to vhin the limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
f SURVEILLANCE RE0VIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per i days when radioactive materials are being added to the tank.
I I
SEQUOYAH - UNIT 2 3/4 11-2 Amendment No. 134, 165
f 3/4.11 RADI0 ACTIVE EFFLUENTS i
BASES r
3/4.11.1 L10010 EFFLUENTS 3/4.11.1.1 This specification is deleted.
3/4.11.1.2 This specification is deleted.
3/4.11.1.3 This specification is deleted.
t 3/4.11.1.4 L10VID HOLDUP TANKS Restricting the quantity of radioactive material contained in the j
specified tanks provides assurance that in the event of an uncontrolled release i
of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20.1001 - 20.2401, Appendix B, Table 2, Column 2, at the l
nearest potable water supply ;nd the nearest surface water supply in an unrestricted area.
3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 This specification is deleted.
3/4.11.2.2
~
This specification is deleted.
3/4.11.2.3 This specification deleted.
3/4.11.2.4 i
This specification is deleted.
SEQUOYAH UNIT 2 B 3/4 11-1 Amendment No. 34, 134, 165
ADMINISTRATIVE CONTROLS e.
Postaccident Samolino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:
(1) Training of personnel, (ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment.
f.
Radioactive Effluent Controls Procram A program shall be provided confor: ting with 10 CFR 50.36a for the cor. trol of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are i
exceeded. The program shall include the following elements:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the ODCM, 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to ten times the concentrations stated in 10 CFR 20.1001 -
20.2401, Appendix B, Table 2, Column 2, 3)
Monitoring, sampling, and analysis of radioactive liquid and i
gaseous effluents in accordance with 10 CFR 20.1302 and with I-the methodology and parameters in the ODCM, 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents release from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appro-priate portions of these systems are used to reduce releases SEQUOYAH - UNIT 2 6-17 Amendment No. 28, 50, 66, 134, 165
ADMINISTRATIVE CONTROLS 6.8.5 f.
Radioactive Effluent Controls Proaram (Cont.)
of radioactivity when the projected doses in a 31-day period i
would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY SHALL BE LIMITED to the following:
1.
For noble gases: Less than or equal to a dose rate of-500 mrem /yr to the total body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and f
2.
For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem / year to any organ.
8)
Limitations on the annual and quarterly air doses resulting l
from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from eact unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and 10)
Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
g.
Radioloaical Environmental Monitorino Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, 2)
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE B0UNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and SEQUOYAH - UNIT 2 6-18 Amendment No. 28, 50, 66, 134, 165
ADMINISTRATIVE CONTROLS ANNUAL REPORT 1/
6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis for the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem manremexposureaccordingtoworkandjobfunctions,fyrandtheirassociated e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignment ta various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
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 the 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 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 the limit was exceeded; (2) Results of the last isotopic analysis for radio-iodine performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of one analysis after the radiciodine activity i
was reduced to less than the limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-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 the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries 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 primary coolant exceeded the radioiodine limit.
1/
A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
This tabulation supplements the requirements of 6 20.2206 of 10 CFR F
Part 20.
l SEQUOYAH - UNIT 2 6-20 Amendment No. 34, 50, 66, 107, 134, 165
1 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 i
assembly burnup histories.
c.
Records of radiation exposure for all individuals entering radiation l
control areas.
d.
Records of gaseous and liquid radioactive material released to the environs and the resulting calculated dose to an individual member of the public.
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.
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.
j m.
Records of secondary water sampling and water quality.
n.
Records of the service life monitoring of all safety-related hydrau-lic and mechanical snubbers, required by T/S 3.7.9, including the maintenance performed to renew the service life.
l o.
Records for environmental qualification which are covered under the provisions of paragraph 2.C.(10)(b) of license No. DPR-79.
p.
Records of reviews performed for changes made to the OFFSITE DOSE i
CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
l SEQUOYAH - UNIT 2 6-24 Amendment No. 28, 50, 66, 134, 153, 165
ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each high radiation area in which the l
intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit * (RWP). Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been estab-lished and personnel have been made knowledgeable of them.
e c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This indi-vidual shall be responsible for providing positive control over the activities within the area and shall perform control over the activ-ities within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Site Radiological Control Manager in the RWP.
l 6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /
hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Site Radiological Control Manager.
- Radiological Control personnel or personnel escorted by Radiological Control personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned l
radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
SEQUOYAH - UNIT 2 6-25 Amendment No. 34, 50, 66, 134, 142, 165
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGR$M (PCP) 6.13.1 Changes to the PCP:
1.
Shall be documented and recceds 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 <hange will maintain the overall con-formance of th9 solidified waste product to existing require-ments of Federai, State, or other applicable regulations.
2.
Shall become effective after review and approval in accordance with Section 6.5.lA.
6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 Changes to the ODCM:
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 level of l
radioactive effluent control pursuant to 10 CFR 20.1302, 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 SQN 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 Effluent Release Report for the period of the i
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.
l SEQUOYAH - UNIT 2 6-26 Amendment No. 34, 50, 66, 134, 159, 165
ADMINISTRATIVE CONTROLS l
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 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 proces-ses 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 i
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 FSAR update.
l SEQUOYAH - UNIT 2 6-27 Amendment No. 34, 50, 66, 134, 159, 165
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