ML20059F909
| ML20059F909 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/10/1994 |
| From: | Beckner W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059F911 | List: |
| References | |
| NUDOCS 9401140221 | |
| Download: ML20059F909 (25) | |
Text
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E UNITED STATES 7;, '
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 2055b0001 ENTERGY OPERATIONS. INC.
SYSTEM ENERGY RESOURCES. INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION HISSISSIPPI POWER AND LIGHT COMPANY DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.111 License No. NPF-29 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated August 11, 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.
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9401140221 940110 PDR ADOCK 05000416:
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. 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-29 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.111, are hereby incorporated into this license.
Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k/d4E-b hdu i
William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
l Changes to the Technical Specifications Date of Issuance: January 10, 1994 i
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ATTACHMENT TO LICENSE AMENDHENT NO.111 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT pAGES xx xx l-4 1-4 1-5 1-5 1-8 1-8 3/4 11-1 3/4 11-1 B 3/4 11-1 B 3/4 11-1 6-15a 6-15a 6-15b 6-15b 6-16 6-16 6-17 6-17 6-20 6-20 6-21 6-21 6-22 6-22
INDEX ADMINISTRATIVE CONTROLS
_SECTION PAGE 6.1 RESPONSIBILITY.....................................................
6-1 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS..............................6-1 l 6.2.2 UNIT STAFF....................................................
6-1 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
Function......................................................
6-2 Composition...................................................
6-2 Responsibilities..............................................
5-6 Authority.....................................................
5-6 6.2.4 S HI FT TECHNICA L ADVIS0R.......................................
5-6 6.3 UNIT STAFF QUALIFICATIONS..........................................
6-6 6.4 TRAINING...........................................................
6-6 6.5 REVIEV AND AUDIT l
E. 5.1 PLANT SAFETY REVIEW COMKITTEE (PSRC)
Function......................................................
6-6 Composition...................................................
6-7 Alternates....................................................
6-7 Heeting Frequency.............................................
6-7 Quorum.....................',...................................
6-7 Responsibilities..............................................
6-7 Authority............................
6-8 Records.......................................................
6-8 6.5.2 SAFETY REVIEW ColHITTEE (SRC)
Function......................................................
6-9 Composition...................................................
6-9 Alternates....................................................
6-9 Consultants...................................................
6-10 t
Meeting Frequency.............................................
6-10 Quorun........................................................
6-10 GRAND GULF-UNIT 1 xix Amendment No. 45 l
l INDEX ADMINISTRATIVE CONTROLS SECTION PAGE SAFETY REVIEW COMMITTEE (SRCl (Continued)
Review.......................................................
6-10 Audits.......................................................
6-11 Authority....................................................
6-12 Records......................................................
6-12 6.5.3 TECHNICAL REVIEW AND CONTROL Activities...................................................
6-12 6.6 R E PO R T A B.LE E V E NT A C T I 0 N........................................... 6-13 6.7 SAFETY LIMIT V10LAT10N............................................
6-13 6.8 PROCEDURES AND PROGRAMS......
6-14 6.9 REPORTING RE0VIREMENTS Routine Reports..................
........................... 6-15 Startup Reports..............................................
6-15 Annual Reports............................................
6-16 Annual Radiological Environmental Operating Report...........
6-17 Annual Radioactive Effluent Release Report................... 6-17 Monthly Operating Reports....................................
6-19 Core Operating Limits Report (C0LR)..........................
6-19 i
Special Reports.............................................
6-19a 6.10 RECORD RETENT10N................................................
6-19b 6.11 RADIATION PROTECTION PR0 GRAM.....................................
6-21 6.12 HIGH RADIATION AREA..............................................
6-21 6.13 PROCESS PROGRAM CONTROL (PCP)....................................
6-22 1
6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)...........................
6-22 i
I GRAND GULF-UNIT 1 xx Amendment No. 87106r111 7
i
DEFINST30NS I-AVERAGE DISINTEGRATION ENERGY 1.11 I shall be the average, weighted in proportion to the concentration of tach radionuclide in the reactor coolant at the time of sampling, of the sum of the average beta and gamma energies per disintegration, in HeV, for isotopes, with half lives greater than 15 minutes, making up at least 95% of the total non-todine activity in the coolant.
EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME 1.12 The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME s interval from when the monitored parameter exceeds its ECCS actuation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function, i.e.
discharge pressures re,ach their required values, etc.the valves travel to their re
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i Times shall include diesel generator starting and sequence loading delays wnere applicable. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
END-OF-CYCLE RECIRCULATION PuiP (RIP SYSTEM RESPONSE TIME 1.13 The END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME that time interval to compirte suppression of the electric arc between the fully open contacts of the re;;irculation pump circuit breaker from initial movement of the associated:
Turbine stop valves, and a.
b.
Turbine contro? valves.
The response time ma./ be measured by any series of sequential, overlapping or total steps such that the entire response time is measured, except for the breaker arc suppression time which is not measured but is validated by sur-veillance tests to conform to the manufacturer's design value.
FRACTION OF LIMITING POWER DENSITY 1.14 The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR existing at a given location civided by the limiting LHGR for that bundle type.
FRACTION OF RATED THERMAL POWER I.15 Tne FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERM PO.iER diviced by tre RAlED THERMAL POWER.
FRE00ENCY NOTATION l
1.16 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
1.17 DELETED i
GRAND GULF-UNIT 1 1-3 Amendment No. 18, 87 l
DEFINITIONS IDENTIFIED LEAKAGE 1.18 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 drywell 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.
1 SOLATION SYSTEM RESPONSE TIME 1.19 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 R00 PATTERN 1.20 A LIMITING CONTROL R0D 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 1.21 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 1.22 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 sensor through and including the actuated device, to verify 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 1.23 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 1.24 MEMBER (S) 0F THE PUBLIC shall be an individual in a controlled or unrestricted area.
However, an individual is not a member of the public during any period in which the individual receives an occupational dose.
GRAND GULF-UNIT 1 1-4 Amendment No. 111
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DEFINITIONS MINIMUM CRITICAL POWER RATIO 1.25 The MINIMUM CRITICAL POWER PATIO (MCPR) shall be the smallest CPR which i
exists in the core.
j OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.26 The 0FFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by l
Specifications 6.9.1.6, 6.9.1.7, 6.9.1.8 and 6.9.1.9.
"DERABLE - OPERABILITY
.27 A system, subsystem, train, component or device shall be OPERABLE or have PERABILITY when it is capable of performing its specified function (s) and L
when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL CONDITION - CONDITION l.28 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1.2.
PHYSICS TESTS 1.29 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 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.30 PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-isolable fault in a reactor coolant system component body, pipe wall or vessel wall.
GRAND GULF-UNIT 1 1-5 Amendment No. B7 111 7
DEFfNITIONS PRIMARY CONTAINMENT INTEGRITY l.31 PRIMARY CONTAINMENT INTEGRITY shall exist when:
a.
All containment penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an OPERABLE containment automatic isolation system, or 2.
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except for valves that are opened under administrative control as permitted by Specification 3.6.4.
b.
The containment equipment hatch is closed and sealed.
c.
Each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
d.
The containment leakage rates are within the limits of Specification 3.6.1.2.
e.
The suppression pool is in compliance with the requirements of Specification 3.6.3.1.
f.
The sealing mechanism associated with each primary containment penetration; e.g., welds, bellows or 0-rings, is OPERABLE.
PROCESS CONTROL PROGRAM (PCP) 1.32 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that proces-sing 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.
PURGE - pVRGING 1.33 PURGE or PURGING 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 required to purify the confinement.
RATED THERMAL POWER 1.34 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3833 MWT.
I 1
GRAND GULF-UNIT 1 1-6 Amendment No. 67,102 I
DEFINITIONS REACTOR PROTECTION SYSTEM RESPONSE TIME 1.35 REACTOR PROTECTION SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.
The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
REPORTABLE EVENT 1.36 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
ROD DENSITY 1.37 ROD DENSITY shall be the number of control rod notches inserted as a fraction of the total number of control rod notches.
All rods fully inserted is equivalent to 100% ROD DENSITY.
SECONDARY CONTAINMENT INTEGRITY 1.38 SECONDARY CONTAINMENT INTEGRITY shall exist when:
a.
All Auxiliary Building and Enclosure Building penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by an OPERABLE secondary containment automatic isolation system, or 2.
Closed by at least one manual valve, blind flange, rupture disc or deactivated automatic valve or damper, as applicable, secured in its closed positio7.
l b.
All Auxiliary Building and Enclosure Building equipment hatches and blowout panels are closed and sealed.
c.
The standby gas treatment system is in compliance with the require-ments of Specification 3.6.6.3.
d.
The door in each access to the Auxiliary Building and Enclosure Building is closed, except for normal entry and exit.
The sealing mechanism associated with each Auxiliary Building and e.
Enclosure Building penetration, e.g., welds, bellows or 0-rings, is OPERABLE.
GRAND GULF-UNIT 1 1-7 Amendment No. 44,102 1
DEFINITIONS SHUTOOWN MARGIN 1.39 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is i
subcritical or would be subcritical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which j
is assumed to be fully withdrawn and the reactor is in the shutdown condition; i
cold, i.e. 68'F; and xenon free.
SITE BOUNDARY 1.40 The SITE BOUNDARY shall be that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.
1.41 DELETED 1.42 DELETED STAGGERED TEST BASIS 1.43 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 com-ponent at the beginning of each subinterval.
THERMAL POWER 1.44 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNIDENTIFIED LEAKAGE 1.45 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE.
i UNRESTRICTED AREA 1.46 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY ac-cess to which is not controlled by the licensee for purposes of protection of MEMBERS OF THE PUBLIC from exposure to radiation and radioactive materials, or any area within the SITE B0UNDARY used for residential quarters or for indus-trial, commercial, institutional, and/or recreational purposes.
1.47 DELETED GRAND GULF-UNIT 1 1-8 Amendment No.87-111
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3/4.11 RADI0 ACTIVE EFFLVENTS 3/4.11.1 LIOUID EFFLVENTS L10VID HOLDVP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside temporary tank, not including liners for shipping radwaste, shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any of the above a.
specified tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tanks 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, and describe the events leading to the condition in the next Annual Radioactive l
Effluent Release Report.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVE!LLANCE REQUIREMENTS 4.11.1.4 The quantity.of radioactive material contained in each of the above specified 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.
i GRAND GULF-UNIT 1 3/4 11-1 Amendment No. 69,87 111 7
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RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS I
EXPLOSIVE GAS HIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume.
APPLICABILITY: Whenever the main condenser offgas treatment system is in operation.
ACTION-With the concentration of hydrogen in the main condenser offgas a.
treatment system exceeding the limit, restore the concentration to within the limit within 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits by monitoring the waste gas in the main condenser off gas treatment system with the hydrogen monitor OPERABLE as required by Specification 3.3.7.12.
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GRAND GULF-UNIT 1 3/4 11-2 Amendment No. 87
3/4.11 RADI0 ACTIVE EFFLUENTS BASES i
3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.4 LIOUID HOLDUP TANKS The tanks listed in this specification include all those tanks i
containing radioactive material that are not surrounded by liners, dikes, or walls capable of holding the contents and that do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.
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, Table 2, Column 2, at the
[
nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
I GRAND GULF-UNIT I B 3/4 11-1 Amendment No. 87 111 7
RAD 10 ACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.6 EXPLOSIVE GAS MIXTURE I
This specification is provided to ensure that the concentration of maintained below the flammability limits of hydrogen.poten tion of hydrogen below its flammability limit provides assurance that theMa requirements of General Design Criterion 60 of App 3/4.11.2.7 MAIN CONDENSER condenser provides reasonable assurance that the tot MEMBER OF THE PUBLIC at and beyond the SITE vertently discharged directly to the environment without treatment.
64 of Appendix A to 10 CFR Part 50. specification implements the requ This GRAND GULF-UNIT 1
\\
B 3/4 11-2 Amendment No. 87 i
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ADMlNTSTRATIVE CONTROLS PROCEDURESANDPROGRAMS(Continued) 6.
Feedwater leakage control system.
7.
Post-accident sampling system.
8.
Su)pression pool level detection portion of tha suppression pool saceup system.
The program shall include the following:
1.
Preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at refueling cycle intervals or less, b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.
This program shall include the following:
1.
Training of personnel,ing, and 2.
Procedures for monitor 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, t
and containment atmosphere samples under accident conditions.
The program shall include the following.
1.
Training of personnel, 2.
Procedures for sampling and analysis 3.
Provisions for maintenance of samplin,g and analysis equipment.
d.
Fadioactive 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
HEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable Theprogram(1)shallbecontainedinthe ODCH 2)shallbeimplementedbyoperatingarecedures,and 3 shali(includeremedialactionstobetakenwienevertheprog(ram) 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 setaoint determination in accordance with the methodology in the ODCH, GRAND GULF-UNIT 1 6-15 Amendment No. 80, 87
1 ADMINISJ_RATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 2.
Limitations on the concentrations of radioactive material i
released in liquid effluents' for UNRESTRICTED AREAS conforming to ten times the concentration values in 10CFR Part 20.1001 -
20.2401, Appendix B, Table 2, Column 2.
l 3.
Monitoring, sampling, and. analysis of radioactive liquid and 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 released from the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5.
Determination of cumulative and projected dose contributions 1
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 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 i
i Part 50, 7.
Limitations on the dose rate resulting from radioactive i
material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the i
following:
I a.
For noble gases:
Less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year 1
to the skin, and, 4
b.
For Iodine-131, for lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem / year to any organ, 8.
Limitations on the annual and quarterly air doses resulting i
from noble gases released in gaseous effluents from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, I
9.
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and GRAND GULF-UNIT 1 6-15a Amendment No. 87L 111 7
ADMINISTRATIVE CONTROLS I
PROCEDURES AND PROGRAMS (Continued) 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.
e.
Radioloaical Environmental Monitorina Proaram 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 i
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, i
2.
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 3.
Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental l
sample matrices are performed as part of the quality assurance program for environmental monitoring.
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 to the Nuclear Regulatory Commission pursuant to Section 50.4 of 10 CFR Part 50.
STARTUP REPORTS 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 l
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 unit.
GRAND GULF-UNIT 1 6-15b Amendment No. 111
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ADMINISTRATIVE CONTROLS STARTUP REPORTS (Continued) 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.
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.
I 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 I of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5.1 Reports shall include 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,I' e.g., reactor operations and surveil-lance, 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 totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of l
the total whole body dose received from external sources should be assigned to specific major work functions.
6.9.1.5.2 Reports shall include documentation of all challenges to safety and relief valves.
6.9.1.5.3 Reports shall include the results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.5.
The fol-1 lowing information shall be included:
(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 radiciodine performed prior to exceeding the limit, results of analysis while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit 2'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.
2/This tabulation supplements the requirements of 10 CFR 20.2206.
l GRAND GULF-UNIT 1 6-16 Amendment No. E&r111
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ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
6.9.1.7 The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.
The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.
6.9.1.9 The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
i GRAND CUtf " ~T 1 6-17 Amendment No. 87 111 7
1
ADMIN 1STRATlVE CONTROLS SEMIANNUALRADIDACTIVEEFFLUENTRELEASEREPORT(Continued i
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GRAND GULF-UNIT 1 6-18 Amendment No, 87
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ADMINISTRATIVE CONTROLS fjp RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of unit operation covering time interval at each power level.
b.
Records and lgs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety, c.
All REPORTABLE EVENTS.
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GRAND GULF-UNIT 1 6-19b Amendment No.106
ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION (Continued) d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
Records of changes made to the procedures required by Specification e.
6.8.1.
f.
Records of radioactive shipments.
g.
Records of sealed source and fission detector leak tests and results.
h.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Unit Operating License:
)
Records and drawing changes reflecting unit design modifications a.
made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
Records of radiation exposure as required by 10 CFR Part 20.
c.
d.
Records of gaseous and liquid radioactive material released to the environs.
Records of transient or operational cycles for those unit components e.
identified in Table 5.7.1-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required by the Operational Quality Assurance Manual not listed in Section 6.10.1.
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 PSRC and the SRC.
1.
Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.
Records of analyses required by the radiological environmental m.
monitoring program.
Records of reviews performed for changes made to the 0FFSITE DOSE n.
CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
GRAND GULF-UNIT 1 6-20 Amendment No. E 6h 111
' 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 10 CFR 20.1601(a) 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 (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 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 unit Health Physicist in the Radiation Work Permit.
~2.2 In addition to the requirements of 6.12.1, areas accessible to sonnel with radiation levels such that a major portion of the body could
- ceive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or the unit Radiation Control Supervisor.
Doors shall remain locked except during periods of access by personnel under an approved RWP 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
- 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 otherwise following plant radiation protection procedures for entry into high radiation areas.
F GRAND GULF-UNIT 1 6-21 Amendment No.111
e ADMINISTRATIVE CONTROLS j
sj2 HIGH RADIATION AREA (Continued)
Excess of 1000 mrem
- that are located within large areas, such as the containment, where rio enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspic.uously 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 activities within the area.
6.13 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP:
Shall be documented and records of reviews performed shall t e retained a.
as required by Specification 6.10.2n.
This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)
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.
b.
Shall become effective after review and acceptance by the PSRC and the approval of the General Manager, Plant Operations.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
Shall be documented and records of reviews performed shall be retained a.
as required by Specification 6.10.2n.
This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)
A determination that the change will maintain the level of radioactive effluent control reauired by 10 CFR 20.1302, 40 CFR l
Part 190, 10 CFR 50.36a, 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 PSRC and the approval of the General Manager, Plant Operations.
Shall be submitted to the Commission in the form of a complete, legible c.
copy of the entire ODCM as a part of or concurrent with the Annual j
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.
- Measurement made at 30 cm from source of radioactivity.
l GRAND GULF-UNIT 1 6-22 Amendment No. Bh111
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