ML20046B166
| ML20046B166 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/29/1993 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20046B163 | List: |
| References | |
| NUDOCS 9308030211 | |
| Download: ML20046B166 (11) | |
Text
DEFINITIONS FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
. IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:
- a. Leakage into collection systems, such as pump seal or valve packing leaks, that is 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 the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.
ISOLATION SYSTEM RESPONSE TIME 1.16 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the isolation valves travel to their required
- positions. Times shall include diesel generator starting and sequence loading delays where applicable. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
LIMITING CONTROL ROD PATTERN 1.17 A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR.
LINEAR HEAT GENERATION RATE 1.18 LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
LOGIC SYSTEM FUNCTIONAL TEST 1.19 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e., all relays and contacts, all trip units, solid state logic elements, etc., of a logic circuit, from as close to the sensor as l practicable through and including the actuated device, to verify l OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested. ;
MAXIMUM FRACTION OF LIMITING POWER DENSITY
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1.20 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be the highest value of the FLPD which exists in the core.
MEMBER (S) 0F THE PUBLIC 1.21 MEMBER (S) 0F THE PUBLIC shall be an individual in a controlled or l UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC l during any period in which the individual receives an occupational dose. l j
FERMI - UNIT 2 m 1-3 Amendment No. ;
930B030211 930729 y r PDR ADOCK 05000341 b p PDR pg
I DEFINITIONS l 1.39~ DELETED ;
SOURCE CHECK 1.40 A SOURCE CHECK shall be the qualitative assessment of channel response when ;
the channel sensor is exposed to a radioactive source.
STAGGERED TEST BASIS 1.41 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 ,
1.42 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. ,
TU_RBINE BYPASS SYSTEM RESPONSE TIME 1.43 The TURBINE BYPASS SYSTEM RESPONSE TIME shall be that time interval from !
when the turbine bypass control unit generates a turbine bypass valve flow signal until the turbine bypass valves travel to their required positions.
The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured. l UN1UENTIFIED LEAKAGE ,
1.44 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE. ,
UNRESTRICTkDAREA 1 45 An UNRESTRICTED AREA shall be any area, access to which is neither limited nor controlled by the licensee. ,
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FERMI - UNIT 2 1-7 Amendment No. El ;
I
ADMINISTRATIVE CONTROLS
_ PROCEDURES AND PROGRAMS (Continued)
- 1. Training of personnel,
- 2. Procedures for monitoring, and
- 3. Provisions for maintenance. of sampling and analysis equipment.
- c. Post-accident Samplina 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,
- 2. Procedures for sampling and analysis, and
- 3. Provisions for maintenance of sampling and analysis equipment.
- d. Hiah Density Spent Fuel Racks i 1
A program which will assure that any unanticipated degradation of the high density spent fuel racks will be detected and will not ?
compromise the integrity of the racks.
- e. Radioactive Effluent Controls Proaram 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 3 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,
- 2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming l l to ten times the concentration values in 10 CFR Part 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 l the methodology and parameters in the ODCM.
FERMI -UNIT 2 6-16 Amendment No. E, JJ, JE, El
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. 1 ADMINISTRATIVE CONTROLS
_ PROCEDURES AND PROGRAMS (Continued)
- 4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents releas.ed 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 i 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 appropriate portions of these systems are used to reduce 4 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 to the- following:
- a. For noble gases: less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the :
skin and !
- b. For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to 1500 mrem /yr to any l organ. l
- 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 B0UNDARY conforming to Appendix I to ,
- 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 B0UNDARY conforming to Appendix I to 10 CFR Part 50,
- 10) Limitations on venting and purging of the Mark I containment through the Standby Gas Treatment System or the Reactor Building Ventilation System to maintain releases as low as reasonably achievable,
- 11) 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.
FERMI - UNIT 2 6-16a Amendment No. #
a
P ADMINISTRATIVE CONTROLS
_ STARTUP REPORT (Continued) 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 3 months until all three events have been completed.
ANNUAL REPORTS l 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 plant, utility, and ,
other personnel (including contractors), for whom monitoring was '
required, receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,*
(e.g., reactor operations and surveillance, inservice inspection, i routine maintenance, special maintenance [ describe maintenance], waste processing, and refueling). The dose assignments to various duty _
functions may be estimated based on pocket or thermoluminescent dosimeters (TLD) dosimeters 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 s'
whole-body dose received from external sources should be assigned to specific major work functions; and
- b. Documentation of all challenges to main steam line safety / relief ;
valves, and
- c. A summary of ECCS outage data including:
- 1. ECCS outage dates and duration of outages,
- 2. Cause of each ECCS outage, ,
- 3. ECCS systems and components in the outage, and !
- 4. Corrective action taken.
- d. The reports shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5. The following information shall be included:
- This tabulation supplements the requirements of 620.2206 of 10 CFR Part 20. l FERMI - UNIT 2 6-17 Amendment No. JJ ,
ADMINISTRATIVE CONTROLS ,
. SPECIAL REPORTS -
6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.
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CORE OPERATING LIMITS REPORT 6.9.3 Selected cycle specific core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each reload cycle ;
or any remaining part of a reload cycle. The analytical methods used to determine the core operating limits shall be tnose previously reviewed and approved by the NRC in General Electric Company reports NEDE-240ll-P-A and NEDE-20566-P. The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The ,
COLR, including any mid-cycle revisions or supplement thereto, shall be submitted upon issuance to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector prior to use.
6.10 RECORD RETENTION ,
6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for i at least the minimum period indicated.
6.10.2 The following records shall be retained for at least 5 years:
- a. Records and logs of unit operation covering time interval at each i power level. '
- b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.
- c. ALL REPORTABLE EVENTS.
- d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications.
- e. Records of changes made to the procedures required by Specification j 6.8.1.
- f. Records of sealed source and fission detector leak tests and results.
- g. Records of annual physical inventory of all sealed source material of record. L FERMI - UNIT 2 6-21 Amendment No. JJ, EA, E7 ,
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ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION - (continued) 6.10.3 The following records shall be retained for the duration of the unit l
_- Operating License: :
- a. Records and drawing changes reflecting unit design modifications !
made to systems and equipment described in the Final Safety Analysis !
Report. _ l
- b. Records of new and irradiated fuel inventory, fuel transfers, and ;
assembly burnup histories.
- c. Records of doses received by all individuals for whom monitoring was required. ,
- d. Records of gaseous and liquid radioactive material released to the environs, ee. Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.
- f. Records of reactor tests and experiments.
- g. Records of training and qualification for current members of the ,
unit staff.
- h. Records of inservice inspections performed pursuant to these Technical Specifications.
- i. Records of quality assurance activities required by the Operational Quality Assurance Manual.
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 OSR0 and the NSRG.
- 1. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.5 including the date at which the service life commences and associated installation and ->
maintenance records.
- m. Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of
- the analysis at a later date. This should include procedures ,
effective at specified times and QA records showing that these procedures were followed.
- n. Records of reviews performed for changes to the OFFSITE DOSE CALCULATION MANUAL and PROCESS CONTROL PROGRAM.
- o. Records of radioactive shipments. 'l 1
FERMI - UNIT 2 6-22 Amendment No. JJ, Ef, EJ ,
-w--r .- _ n- __._ - ___ __ - ___
ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM 6.11.1 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 of 10 CFR Part 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 i F
d
- Radiation protection personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement during the _
performance of their assigned radiation protection duties, provided they are !
otherwise following plant radiation protection procedures for entry into high radiation areas.
FERMI - UNIT 2 6-22a Amendment No. JJ, Jf l
ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)
- 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 levels in the area have been established and personnel have been made knowledgeable of them.
- c. A radiation protection qualified individual (i.e., qualified in l 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 Radiation Protection Supervisor ** in the RWP.
6.12e2 In addition to the requirements of Specification 6.12.1, areas l accessible to individuals with radiation levels such that an individual could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose equivalent greater than 1000 mrems but less than 500 rads at one meter from sources of radioactivity shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Nuclear Shift Supervisor on duty and/or the radiation protection supervision. Doors shall remain locked except during l periods of access by individuals under an approved RWP which shall specify the l dose rate levels in the immediate work area and the maximum allowable stay l time for individuals in that area. For individual areas accessible to l individuals with radiation levels such that a major portion of the individual's body could receive in I hour a dose in excess of 1000 mrems* but less than 500 rads at one meter from sources of radioactivity that are located within large areas, such as the containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual 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, continuous surveillance, direct' or remote (such as use of closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activiti~es within the area.
6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 Changes to the PCP:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n. This documentation shall contain:
- Measurement made at 30 centimeters from source of radioactivity.
- An alternative title may be designated for this position. All requirements of these Technical Specifications apply to the position with the alternative title as apply with the specified title. Alternative titles shall be specified in the Updated Final Safety Analysis Report. L FERMI - UNIT 2 6-23 Amendment No. JJ, AZ
1 ADMINISTRATTVE CONTROLS l
6.13 RR0 CESS CONTROL PROGRAM (PCP) (Continued).
1
- 1) Sufficient information.to support the change together with the ,
appropriate analyses or evaluations justifying the change (s) i and i
- 2) A determination that the change will maintain the overall conformance of'the solidified waste product to existing 6 requirements of Federal, State, or other applicable .
regulations. :
- b. Shall become effective after review and acceptance by the OSR0 3 and the approval of the Plant Manager.
1 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) .
6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14,2 Changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be !
retained as required by Specification 6.10.3n. This documentation shall contain:
- 1) Sufficient information to support the change together with the [
appropriate analyses or evaluations justifying the changes (s) ,
and l
- 2) 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. ;
- b. Shall become effective after review and acceptance by the OSR0 j and the approval of the Plant Manager. ;
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as 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 i 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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FERMI - UNIT 2 6-24 Amendment No. /J, E2
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RADI0 ACTIVE EFFLUENTS i
I BASES 3/4.11.1 LIOUID EFFLUENTS .
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3/4.11.1.4 LIOUID HOLDUP TANKS The tanks listed in this specification include all those outdoor !
radwaste tanks that are not surrounded by liners, dikes, or walls capable of i holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. 1 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 i than the limits of 10 CFR Part 20, Appendix B, Table 2, Column 2, at the l !
nearest potable water supply and the nearest surface water supply in an :
UNRESTRICTED AREA. i i
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FERMI - UNIT 2 B 3/4 11-2 Amendment No. E2
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