ML20057C193
| ML20057C193 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/21/1993 |
| From: | Bajwa S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057C194 | List: |
| References | |
| NUDOCS 9309280058 | |
| Download: ML20057C193 (24) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D.C. 20555 6 1 SOUTHERN NUCLEAR OPERATING COMPANY.' INC, DOCKET NO-50-348
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JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 1
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 100 License No. NPF-2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
[
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated August 24, 1992, is revised December 17, 1992, March 4, 1993, and April 29, 1993, complies with the standards and ruuirements 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 j
safety of the public, and (ii) that such activities will be conducted in compliante with the Commission's regulations; i
D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and j
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; i
and paragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby j
amended to read as follows:
l (2)
Technical Specifications The Technical Specificaticns contained in Appendices A and B, as revised through Amendment No. 100, are hereby incorporated in the i
license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
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-This license amendment is effective as of its date of issuance and shall be implemented by December 31, 1993.
FOR THE NUC. EAR REGULATORY COMMISSION M
.A S. Singh Bajwa, Acting Director Project Directorate 11-1 H
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance: September 21, 1993 5
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~1 ATTACHMENT TO LICENSE AMENDMENT NO. 100 TO FACILITY OPERATING LICENSE NO. NPF-2 EOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
]
Remove Paaes Insert Paaes B 3/4 3-2 B 3/4 3-2 i
i B 3/4 11-2 B 3/4 11-2 t
6-15 E-15 l
l 6-15a 6-15b
.i 6-16 6-16 i
6-22 6-22 l
6-22a i
6-23 6-23 t
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I I
INSTRUMENTATIOR BASES REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION (Continued)
The measurement of response time at the specified frequencies provides assurance that the reactor trip and ESF actuation associated with each channel is completed within the time limit assumed in the accident analyses.
No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrata the total channel response time as defined.
Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measuretents or
- 2) utilizing replacement sensors with certified response times.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.I RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
Alarm / trip setpoints for the containment purge have been established for a purge rate of 5,000 scfm in all MODES and for purge rates of 25,000 scfm and 50,000 scfm in MODES 4, 5, and 6.
The containment purge setpoints are based on a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the effluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2 Column 1 for these isotopes, and on a X/Q of 5.6 X 10-6 sec/m3 at the site boundary.
The alarm / trip setpoint for the fuel storage pool area has been established l based on a flow rate of 13,000 scfm; a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the effluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, Column I for these isotopes, and on a X/Q of 5.6 X 10-6 sec/m3 at the site boundary.
3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with.the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
e For the purpose of measuring F (Z), Fjg, and Fxy a full incore flux map Q
is used.
Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system.
Full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.
FARLEY-UNIT I B 3/4 3-2 AMENDMENT NO. 8, 100
4 PAD 10 ACTIVE EFFLUENTS BASES 3/4.11.1.3 LIOUID WASTE TREATMENT This specification deleted. Refer to the Offsite Dose Calculation Manual.
3/4.11.1.4 LIOUID HOLOUP TANKS Restricting the quantity of radioactive material contained in the 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 Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification deleted.
Refer to the Offsite Dose Calculation Manual.
J FARLEY-UNIT I B 3/4 11-2 AMENDMENT NO. 26, 100
ADMINISTRATIVE CONTROLS b.
In-Plant Radiation Monitorino A program which will ensure the capability to accurately determine the airborne iodine concentration in certain plant areas where personnel may be present under accident conditions. This program shall include the following:
(i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analyses equipment.
c.
Secondarv Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:
(i)
Identification of a sampling schedule for the critical variables and the control points for these variables, (ii)
Identification of the procedures used to measure the values of the critical variables, (iii)
Identification of process sampling points, including monitoring the condenser hotwells for evidecce of condenser in-leakage, (iv) Procedures for the recording and management of data, (v)
Procedures defining corrective actions for off-control-point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
Post-accident 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 training of penonnel, the procedures for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.
e.
Radioactive Effluent Controls Prooram 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 FARLEY-UNIT 1 6-15 AMENDMENT NO. 26,100
ADMINISTRATIVE CONTROLS 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 setpoint determination in accordance with the methodology in the ODCM, ii) Limitations at all times on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to ten times the concentrations stated in 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401),
Table 2, Column 2, iii) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the 00CH, iv)
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, v) 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, vi)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems t-) ensure that the appropriate portions of these systo ; are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 peret at of the guidelines for the annual dose or dose comitment :onforming to Appendix I to 10 CFR Part 50, vii) Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at and beyond the site boundary as follows:
a.
For noble gases:
Less than or equal to a dose rate of 500 ares / year to the total body and less thar. or equal to a dose rate of 3000 mrem / year to the skin, and b.
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.
FARLEY-UNIT 1 6-15a AMENDMENT NO. 9,82,100
i ADMINISTRATIVE CONTROLS viii)
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, 1x)
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 x)
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.
f.
Radioloaical Environmental Monitorina 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, ii) A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of this census, and iii)
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 perforned as part of the quality assurance program for environmental monitoring.
g.
Solid Radioactive Wastes Control Proaram The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste.
FARLEY-UNIT 1 6-15b AMENDMENT NO. 100
ADMINISTRATIVE CONTROLS 6.9.1.2 The startup repo 4 shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured i
values of the operating canditions 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.
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 operation) supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REPORTV 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.S Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated manrem exposure according to work and job functions,U e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.. Small exposures totaling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
V 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.
F This tabulation supplements the requirements of paragraph 20.2206 of 10 CFR Part 20.
FARLEY-UNIT 1 6-16 AMENDMENT NO. fd, 100
ADMINISTRATIVE CONTROLS 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 bi ricaded and conspicuously posted as a high radiation area and entrance thereto shal be controlled by requiring issuance of a Radiation Work Permit.* Any individual or group of individuals permitted to enter such areas shr.11 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.
A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physics Supervisor.
6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem but less than 500 rads shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Permit which shall specify the dose rate levels in.the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem ** but less than 500 rads *** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, rrovided they are following plant radiation protection procedures for entry into high radiation areas.
Measurement made at 30 cm from the radiation source or from any surface that the radiation penetrates.
- Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.
FARLEY-UNIT 1 6-22 AMENDMENT NO. W, 100
ADMINISTRATIVE CONTROLS areas, then that area shall be roped off, conspicuously posted.and a flashing light shall be activated as a warning device.
In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
FARLEY-UNIT 1 6-22a AMENDMENT NO.
100
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementatior.
6.13.2 Licensee initiated changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
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 acceptance by the PORC and the approval of the General Manager - Nuclear Plant.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the ODCH:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
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 radioactiva effluent control required by 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 PORC and the approval of the General Manager - Nuclear Plant.
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 Semiannual Radioactive 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.
FARLEY-UN1'..
6-23 AMENDMENT NO.221 100
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NUCLEAR REGULATORY COMMISSION g
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SOUTHERN NUCLEAR OPERATING COMPANY. IN(2 DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No. NPF-8 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated August 24, 1992, as revised December 17, 1992, March 4, 1993, and April 29, 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 l
forth in 10 CFR Chapter I; l
9 8.
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 (1) 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 license 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.
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. NPF-8 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 92, are hereby incorporated in the license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
~
. 3.
This license amendment is effective as of its date of issuance and shall be implemented by December 31, 1993.
+
FOR THE NUCLEAR REGULATORY COMMISSION j/h S. Singh Bajwa, Acting Director Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: September 21, 1993 m
'h 6
6 3
7
ATTACHMENT TO LICENSE AMENDMENT NO. 9?
TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Paces Insert Paaes B 3/4 3-2 B 3/4 3-2 B 3/4 11-2 B 3/4 11-2 6-15 6-15 6-15a 6-15b 6-16 6-16 6-22 6-22 6-22a 6-23 6-23 r
i
INSTRUMENTATf0N BASES REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION (Continued)
The measerement of response time at the specified frequencies provides assurance that the reactor trip and ESF actuation associated with each channel is completed within the time limit assumed in the accident analyses.
No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.
Sensor response time verificat Nn may be demonstrated by either 1) in place, onsite or offsite test measurements or
- 2) utilizing replacement sensors with certified response times.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
Alarm / trip setpoints for the containment purge have been established for a purge rate of 5,000 scfm in all MODES and for purge rates of 25,000 scfm and 50,000 scfm in H0 DES 4, 5, and 6.
The containment purge setpoints are based on a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the effluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, Column 1 for these isotopes, and on a X/Q of 5.6 X 10-6 sec/m3 at the site boundary.
The alarm / trip setpoint for the fuel storage pool area has been established I based on a flow rate of 13,000 scfm; a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the effluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, Column I for these isotopes, and on a X/Q of 5.6 X 10-6 sec/m3 at the site boundary.
1 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the i
reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
For the purpose of measuring F (Z), F$H, and Fxy a full incore flux map Q
is used.
Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system.
Full incon flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.
)
FARLEY-UNIT 2 B3/43-2 AMENDMENT NO.
92
i
\\
RADI0 ACTIVE EFFLUENTS BASES i
3/4.11.1.3 LIOUID WASTE TREATMENT This specification deleted.
Refer to the Offsite Cose Calculation Manual.
3/4.11.1.4 LIOUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the 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 Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an-unrestricted area.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification deleted.
Refer to the Offsite Dose Calculation Manual.
9 Y
e FARLEY-UNIT 2 B 3/4 11-2 AMENDMENT NO. 92
ADMINISTRATIVE CONTROLS b.
In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine the airborne iodine concentration in certain plant areas where personnel may be present under accident conditions. This program shall include the following:
(i) Training of personnel, (ii)
Procedures for monitoring, and (iii)
Provisions for maintenance of sampling and analyses equipment.
c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:
(i)
Identification of a sampling schedule for the critical variables and the control points for these variables, (ii)
Identification of the procedures used to measure the values of the critical variables, (iii)
Identification of process sampling points, including monitoring the condenser hotwells for evidence of condenser in-leakage, (iv)
Procedures for the recording and management of data, (v)
Procedures defining corrective actions for off-control-point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
Post-accident Samolina 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 training of personnel, the procedures for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.
e.
Radioactive Effluent Controls Procram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to i
members of the public from radioactive effluents as low as FARLEY-UNIT 2 6-15 AMENDMENT NO. 13, 92 e
o ADMINISTRATIVE CONTROLS 1
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:
i) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance t
tests and setpoint determination in accordance with the methodology in the ODCM, ii)
Limitations at all times on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to ten times the concentrations stated in 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401),
Table 2, Column 2, iii) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM, iv)
Limitations on the annual and quarterly doses or dose comitment 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, v) 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, vi)
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 confoming to Appendix I to 10 CFR Part 50, vii)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at and beyond the site boundary as follows:
a.
For noble gases: Less than or equal to a dose rate of 500 aren/ year to the total body and less than or equal to a dose rate of 3000 mres/ year to the skin, and b.
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 ares / year to any organ.
FARLEY-UNIT 2 6-15a AMENDMENT NO. 6,M,92
ADMINISTRATIVE CONTROLS v111)
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, ix)
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 x)
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.
f.
Radiolooical 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:
i) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, ii) A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of this census, and tii)
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.
g.
Solid Radioactive Wastes Control Procram The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste.
FARLEY-UNIT 2 6-15b AMENDHENT NO. 92
ADMINISTRATIVE CONTROLS 6.9.1.2 The startup report shall address each of the tests identified in the Final Safety Analysis Report 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.
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 operation) supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REPORTl/
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.
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated manrem exposure according to work and job functions,2/ e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totaling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
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.
Z/ This tabulation supplements the requirements of paragraph 20.2206 of 10 CFR Part 20.
FARLEY-UNIT 2 6-16 AMENDMENT NO.
92
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ADMINISTRATIVE CONTROLS 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 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.* 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 radiation monitoring device which continuously indicates the a.
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, A health physics qualified individual (i.e., qualified in radiation c.
protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physics Supervisor.
6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem but less than 500 rads shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Permit which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.
For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem ** but less than 500 rads *** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are following plant radiation protection procedures far entry into high radiation areas.
Measurement made at 30 cm from the radiation source or from any surface that the radiation penetrates.
- Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.
FARLEY-UNIT 2 6-22 AMENDMENT NO. H, 92
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ADMINISTRATIVE CONTROLS areas, then that area shall be roped off, conspicuously posted and a flashing l
light shall be activated as a warning device.
In lieu of the stay time i
specification of the RWP, direct or remote (such as use of closed circuit TV i
i cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the' activities within the area.
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I FARLEY-UNIT 2 6-22a AMENDMENT NO. 92 l
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 Licensee initiated changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
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 acceptance by the PORC and the approval of the General Manager - Nuclear Plant.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the ODCH:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
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 20.1302, 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.
L 2.
Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.
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 Semiannual Radioactive 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.
P FARLEY-UNIT 2 6-23 AMENDMENT NO. 49, 92
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