ML20095C389
| ML20095C389 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/03/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20093C341 | List: |
| References | |
| DPR-44-A-102, DPR-56-A-104 NUDOCS 8408220530 | |
| Download: ML20095C389 (175) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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g WASHINGTON, D C. 20555
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.102 License No. DPR-44 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated November 29, 1982, as supplemented by letter dated March 7,1984, 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 provisinns 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 Comission'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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
8408220530 840803 PDR ADOCK 05000
4 2-Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amer.dment No.102, are hereby incorporated in-the license.
PEC0 shall operate the. facility in accordance with the Technical Specifications.
3.
This license. amendment is effective as of December 31, 1984.
r FOR THE NUCLEAR REGULATORY COMMISSION jlbV l62b John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 3, 1984
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UNITED STATES y'
'g NUCLEAR REGULATORY COMMISSION cy WASHINGTON, D. C. 20555
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PHILADELPHIA ELECTRIC COMPANY PUBLIC 5ERVICE ELECTRIC AND GA5 COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated November 29, 1982, as supplemented by letter dated March 7,1984, 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 CF't 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 Comission'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. DPR-56 is hereby amended to read as follows:
4 Technical Specifications a
The Technical Specifications contained in Appendices A and B, as revised through Amendnent No.104, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of December 31, 1984.
FOR THE NUCLEAR REGULATORY COMMISSION 4
/# d p 47 4 /f/
g John. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 3,1984 l
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ATTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY OPERATING LICENSE N0. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert 11 ii iii iii iva iva vi vi via 1
1 2
2 3
3 4
4 5
5 6
6 7
7 8
8 8a 58 58 59 59 75 75 84 84 92 92 93 93 203 203 204 204 205 205 206 206 207 207 208 208 209 209 209a 210 210 211 211 212 212 213 213 214 214 215 215 216 216 216a-1 216a-2 216a-3 216a-4 216a-5 216a-6 J
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2-Remove Insert 216b-1 216t-2 216c-1 216c-2 216d-1 216d-2 216d-3 216d-4 216d-5 216d-6 216e 216f-1 216f-2 216f-3 216f-4 216f-5 216f-6 216f-7 l
248 248 248a 252 252 252a i
254 254 254a 254a
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256 256 256a 257 257 4
257a 258 258 259 259 259a 259b 261 261 261a 265 266 267 Replace the following pages of the Appendix "B" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert i
i 13 13 41 41 48 48
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TABLE OF CONTBNTS (Cont'd)
SURVEILLANCE LIMITING COND 'ZONS FOR' OPERATION REQUIREMENT P3 l
3,6 PRIMARY SYSTEN BOUNDARY 4.6 143 A.
Thermal and Pressurisation Limitations A
143 B.
Coolant Chemistry B
145 C.
Coolant Leakage C
146 D.
Safety and Relief Valves D
147 E.
Jet Pumps E
148 F.
Jet Pump Flow Mismatch F
148 G.
Structural: Integrity G
149 3.7 CONTAINMENT SYSTENs 4.7 165 A.
Primary Containament A
165 B.
standby Gas Treatment System B
175 C.
Secondary containment C-176 D.
Primary containment Iselation valves D
177 3.9 RADIOACTIVE MATERIALS 4.8 203 x
A.
General'
- A 203 T-l B.
Liquid Effluents 3
204 '.,
i C..
Gaseous Effluents C
208 i
D.
40CFR190 D
216 j
E.
Radiological Environmental Monitoring E
~
F.
Solid Radioactive Maste F
216a-5 G.
Mechanical Vacuum Pump G
Il6a-6 3.9'AUEILIARY ELECTRICAL SYSTEMS
- 4. 9.
217 A.
Auxiliary Electrical Equipment A
217 B.
Operation with Inoperable Equipment B
219 C.
Emergency Servloe Water System C-221 3.10 CORE 4.10 225 A.
Refueling Interlocks A
225 B.
Core Monitoring B
227 C.
Spent Fuel Pool Water Level C
228 D.
Beavy Loads Over Spent Fuel D
228 E.
Spent Fuel Decay Time E
228 3.11 ADDITIONAL SAFETY RELATED PLANT CAPABILITIES 4.11 233 A.
Main Control Room ventilation A
233 B.
Alternate Beat Sink Facility B
234 C.
Emergency Shutdown Control Panel C
234 i
4 i
11 Amendment No.'J7, g,102 gg g...M,y.,.:.ga;.;p.4
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PBAPS TABLE OF CONTENTS (Cont'd)
SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REOUIREMENT 3.12 RIVER LEVEL 4.12 237 A.
High River Water Level A
237 B.
Low River Water Level B
237 C.
Level Instrumentation C
238 3.13 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCE 4.13 240a 3.14 FIRE PROTECTION 4.14 2 doc A.
Water Fire Protection System A
240c B.
CO2 Fire Protection System B
240g C.
Fire Detection C
2401 D.
240j 1
3.15 SEISMIC MONITORING INSTRUMENTATION 4.15 240n 5.0 MAJOR DESIGN FEATURES 241 6.0 ADMINISTRATIVE CONTROLS 2A3 6.1 Res ponsibility 243 6.2 Organization 2d 3 6.3 Facility Staf f Qualifications 246 6.4 Training 246 6.5 Review and Audit 246 6.6 Reportable Occurrence Action 253 i
6.7 Safety Limit Violation 253 6.8 P rocedures 253 6.9 Reporting Peauirements 254 6.10 Record Retention 260 1
6.11 Radiation Protection Program 261 6.12 Fire Protection Inspections 261 6.13 High Radiation Area 262 6.14 Integrity of Systems outside Containment 263 6.15 Iodine Monitoring 263 6.16 Environmental Qualification 264 i
6.17 Offsite Dose Calculation Manual 265 I
6.18 Major Changes to Radioactive Waste j
Treatment Systems 266-iii Amendr.1ent No. 39, #7, 7#, /$,102
PBAPS Unit 2 LIST OF FIGUPES Figure Title Pace 3.6.1 Minimum Temperature for Pressure 164 Tests such as required by Section XI 3.6.2 Minimum Temperature for Mechanical 164a Heatup or Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for Core Operation 164b (Criticality) 3.6.4 Transition Temperature Shif t vs.
164c Fluence 3.8.1 Site Boundary and Ef fluent Release 216e Points 6.2-1 Manage $ient Organization Chart 244 6.2-7 Organization for Conduct of Plant 745 Operations i
iva Amendment No. S6,102
PBAPS Unit 2 LIST OF TABLES Table Title Pace
_ )
i 4.2.B Minimum Test and Calibration Frequency 81 for CSCS 1
4.2.C Minimum Test and Calibration Frecuency 83 for Control Rod Blocks Actuation 4.2.D Minimum Test and Calibration Frecuency 84 for Radiation Monitoring Systems 4.2.E Minimum Test and Calibration Freauency 85 for Drywell Leak Detection 4.2.F Minimum Test and Calibration Frecuency 86 for Surveillance Instrumentation 4.2.G Minimum Test and Calibration Frecuency 88 for Recirculation Pump Trip
.3.5.K.2 Operating Limit MCPR Values for 133d Various Core Exposures
,3.5.K.3 Operating Limit MCPR Values for 133e Various Core Exposures 4.6.1 In-Service Inspection Program for Peach 15Q Bottom Units 2 ani 3 3.7.1 Primary Containment Isolation Valves 179 3.7.2 Testable Penetrations With Double 184 O-Ring Seals 3.7.3 Testable Penetrations with Testable IRA Bellows 3.7.4 Primary Containment Testable Isolation 195 Valves 4.8.1 Radioactive Liould Waste Sampling and 216b-1 Analysis 4.8.2 Radioactive Gaseous Waste Sampling and 216c-1 Analysis 4.8.3.a Radiological Environmental Monitoring 216d-1 P rogram 4.8.3.b Reporting Levels for Radioactivity 216d-5 by Concentrations in Environmental Sample vi Aidendment No. 37, #, W,102
PBAPS Unit 2 I
LIST OF TABLES Table Title Pace 4.8.3.c Maximum values for Minimum Detectable 216d-6 Levels of Activity 3.ll.D.1 Safety Related Shock Suppressors 234d 3.14.C.1 Fire Detectors 240k l
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via l
Amendment No. 102 e
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PBAPC s
l 1.0 DEFINITIONS The succeeding frequently used terms are explicitly defined so that a uniform interpretation of the specifications may be achieved.
l I
Alteration of the Reactor Core - The act of moving any component i
in the region above the core support plate, below the upper grid and within the shroud.
1 Normal control rod movement with the control drive hydraulic system is not defined as a core alteration.
Normal movement of f
in-core instrumentation and the traversing in-core probe is not l
defined as a core alteration.
l Channel - A channel is an arrangement of a sensor and associated components used to evaluate plant variables and produce discrete outputs used in looic.
A channel terminates and loses its i
identity where individual channel outputs are combined in logic.,
1 i
i Cold condition - Reactor coolant temperature eeual to or less than 212 F.
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Cold Shutdown - The reactor is in the shutdown mode, the reactor coolant temperature equal to or less than 212 F, and the reactor l
vessel is vented to atmosphere.
}
Critical Power Ratio (CPR) - The critical power ratio is the 1
ratio of that assembly power which causes some point in the asser.bly to experience transition boiling to the assembly power l
1 at the reactor condition of interest as calculated by application l
of the GEXL correlation.
(5eference NEDO-10958).
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j Dose Equivalent I-131 - That concentration of I-131 ( Ci/ge) i j
which alone would produce the same thyroid dose as the cuantity i
and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 a
j actually present.
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i Amendment tio.102 1
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PBAPS 1.0 DEFINITIONS (Cont'd)
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Engineered Safecuerd - An engineered safeguard is a safety system i
the actions of which are essential to a safety action reouired in j
response to accidents.
i i
l Fraction of Limiting Power Density (FLPD) - The ratio of the linear hat generation rate (LHGR ? eAisting at a given location to the design LRGR for that bundle type.
Functional Tests - A functional test is the manual operation or initiation of a system, subsystem, or component to verify that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the required volume of water).
Gaseous Redwaste Treatment System - Any system designed and j
instelled to reduce radioactive gaseous ef fluents by collecting primary coolant system offgases from the primary system and j
providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
I r
l Hot Shutdown - The reactor is in the shutdown mode and the, i
reactor coolant temperature greater than 212 F.
i l
Hot Standby Condition - Hot Standby Condition means operation with coolant temperature greater than 212 F, system pressure less j
than 1055 psig, and the mode switch in the Startup/ Hot Standby l
position.
The main steam isolation valves may be opened to provide steam to the reactor feed pumps.
Immediate - Immediate means that the reouired action will be i
initiated as soon as practicable considering the safe operation of the unit a6d the importance of the recnsired action, j
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- l Amendment No. 102 I
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PBAPS 1.0 DEFINITIONS (Cont'd)
Instrument or Channel Calibration - An instrument or channel calibration means the adjustment of an instrument or channel signal output so that it corresponds, within acceptable range, and accuracy, to a known value(s) of the parameter which the instrument or channel monitors.
The known value of the parameter shall be injected into the channel or instrument as close to the primary sensor as practicable.
Instrument or Channel Check - An instrument or channel check is a cualitative determination of acceptable operability by observation of instrument or channel behavior during operation.
This determination shall include, where possible, comparison of the instrument or channel with other independent instruments neasuring the same variable.
Instrument or Channel Functional Test - An instrument or c).annel functional test means the injection of a simulated signal into the channel or instrument as close to the primary sensor as practicable to verify the proper instrument channel response, alarm and/or initiating action.
Limitino Condi tions for operations (LCO) - The limiting conditions for operation specify the minimum acceptable levels of system performance necessary to assure safe startup and operation of the facility.
When these conditions are met, the plant can be operated safely and abnormal situations can be. safely controlled.
Limiting Safety System Setting (LSSS) - The limiting safety system settings are settings on instrumentation which initiate the automatic protective action at a level such that the safety limits will not be exceeded.
The region between the saf ety limit and these settings represents margin with normal operation lying below these settings.
The margin has been established so that with proper operation of the instrumentation, the safety limits will never be exceeded.
Locie - A logic is an arrangement of relays, contacts and other components that produces a decision output.
4 Amendment No. 102
PBAPS 1.0 DEFINITIONS (Cont'd)
F (a) Initiating - A logic that receives signals from channels and produces decision outputs to the actuation logic.
(b) Actuation - A logic that receives signals (either from initiation logic or channels) and produces decision outputs j
to accomplish a protective action.
i i
Logic System Functional Test - A logic system functional test means a test of all relays and contacts of a logic circuit to insure all components are operable per desi Where practicable, action will go to completion; gn intent.i.e., pumps will be started and valves operated.
J Maximus Fraction of Limiting Power Density (MFLPD) - The Maximum Fractius of Limiting Power Density (MFLPD) is the highest value existing in the core of the Fraction of Limiting Power Density l
(FLPD).
t j
MEMBERS OF THE PUBLIC - Members of the public shall include all persons who are not occupationally associated with the plant, j
This category does not include employees of the utility, i ts contractors, or vendors.
Also excluded from this category are persons who enter the site to service eauipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
}
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Minimum Critical Power Ratio (MCPR) - The minimum in-core critical power ratio corresponding to the most limiting fuel j
assembly in the core.
I Mode of Operation - A reactor mode switch selects the proper I
interlocks for the operational status of the unit.
The following are the modes and interlocks provided: Refuel Mode, Run Mode, j
Shutdown Mode, Startup/ Hot Standby Mode.
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l PBAPS l.0 DEFINITIONS (Cont'd)
Offsite Dose Calculation Manual - Contains the current methodology and parameters used in the calculation of of fsite 3
doses due to radioactive gaseous and liould effluents and describes the environmental radiological monitoring program.
OPERABLE - OPERABILITY - A system, subsystem, train, component, or device is OPERABLE or has OPERABILITY when it is capable of performing its specified function and all instrumentation, controls, normal and emergency electrical power sources, ecoling or seal water supplies, lubrication systems, and other auxiliary equipment that are reauired for the system, subsystem, train, component, or device to perform its function are also capable of performing their related support function.
l Operating - Operating means that a system or component is performing its intended functions in its required manner.
Operating Cycle - Interval between the end of one refueling outage for a particular unit and the end of the next subsecuent refueling outage for the same unit.
Primary Containment Integrity - Primary containment integrity means enat the crywell and pressure suppression chamber are intact and all of the f ollowing condition 3 are satisfied:
1.
All primary containment penetrations reggired to be closed during accident conditions are either:
a)
Capable of being closed by an OPERABLE containment automatic isolaticn valve system, or b)
Closed oy at least one manual valve, blind flange, or deactivsted automatic valve secured in its closed position, except as may be provided in Specifications
- 3. 7.D. 2 and 4. 7.D. 2.
Manual valves =ay be opened to perf orm necessary operational activities.
2.
At least one door in each airlock is closed and sealed.
3.
All blind flanges and manways are closed.
i 4
Amendment No. 102,
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PBAPS 1.0 DEFINITIONS (Cont'd)
Protective Action - An action initiated by the protection system j
when a limit is reached.
A protective action can be at a channel j
or system level.
i Protective Function - A system protective action which results from the protective action of the channels monitoring a particular plant condition, i,
Purce - Purgina - 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 i
reauired to purify the confinement.
Rated Power - Rated power refers to operation at a reactor power of 3,293 MWtr this is also termed 100 percent power and is the i
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maximum power level authorized by the operating license.
Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters j
when the reactor is at rated power.
Reactor Power Operation - Reactor power operation is any operation with the mode switch in the "Startup" or "Run" position with the reactor critical and above it rated power.
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1 l
Reactor Vessel Pressure - Unless otherwise indicated, reactor vessel pressures listed in the Technical Specifications are those j
measured by the reactor vessel steam space detectors.
l Refuel Mode - With the mode switdh in the refuel position, the reactor is shutdown and interlocks are established so that only j
one control rod may be withdrawn, i
Refueline Outage - Refueling outage is the period of time between the shutdown of the unit prior to a refueling and the startup of the unit af ter that refueling.
For the purpose of designatine 1
frecuency of testing and surveillance, a refueling outage shall mean a regularly scheduled outager however, where such outages occur within 8 months of the completion of the previous refueling 7
I l
l Amendment No.102. - - - -.... -. -
I 5
PRAPS l
1.0 DEFINITIONS (Cont'd) i outage, the required surveillance testing need not be performed until the next regularly scheduled outage.
1 Run Mode - In this mode the reactor system pressure is at or j
above 850 psig and the reactor protection system is energized j
with APRM protection (excluding the 154 high flux trip) and RBM l
interlocks in service.
2 Safety Limit - The safety limits are limits below which the i
reasonable maintenance of the cladding and primary systems are assured.
Exceeding such a limit requires unit shutdown and review by the Nuclear Regulatory Commission before resumption of i
unit operation.
Operation beyond such a limit may not in itself
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result in serious consequences, but it indicates an operational deficiency subject to regulatory review.
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j secondary containment Integrity - Secondary Containment integrity means that the reactor building is intact and the following j
conditions are met j
1 1.
At least one door in each access opening is closed.
4 i
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2.
The standby gas treatment is operable.
j 3.
All Reactor Building ventilation system automatic isolation i
valves are operable or deactivated in the isolation position.
j 1
Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being perfermed.
I shutdown Mode - Placing the mode switch to the shutdown position initiates a reactor scram and power to the control rod drives is j
removed.
After a short time period (about 10 sec), the scram signal is removed allowing a deram reset and restoring the normal l
valve lineup in the control rod drive hydraulic systemt also, the j
main steam line isolation scram and main condenser low vacuum l
scram are bypassed if reactor vessel pressure is below 1055 psig.
i ]
Amendment No. 102 i
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PSAPS 1.0 DEFINITIONS (Cont'd) 1 Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.
+
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SITE BOUNDARY - That line beyond which the land is not owned, i
j leased or otherwise controlled by licensee.
i Source Check - A source check shall be the qualitative assessment of channel response when the channel. sensor is exposed to a j
radioactive source.
t Startup/ Rot Standby Mode - In this mode the reactor protection scram trips, initiated by condenser low vacuum and main steam l
line isolation valve closure, are bypassed when reactor pressure is less than 1055 psig, the reactor protection system is i
energized with IRM neutron monitoring system trip, the APPR 154 i
high flux trip, and control rod withdrawal interlocks in service.
This is of ten ref erred to as just Startup Mode.
This is intended i
j to imply the Startup/ Hot Standby position of the mode switch.
Surveillance Frecuency - Periodic surveillance tests, checks, i
calibrations, and examinations shall be performed within the j
specified surveillance intervals.
The operating cycle interval i
i as pertaining to instrument and electrical surveillance shall not i
exceed 18 months.
These specified time intervals may be exceeded by 254.
In cases where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval.
i Surveillance tests are not required on systems or parts of the j
systems that are not required to be operable or are tripped.
If tests are missed on parts not required to be operable or are i
tripped, then they shall be performed prior to returning the l
system to an operable status.
i j
Transition Boiling - Transition boiling means the boiling regime between nucleate and film boiling.
Transition boiling is the regime in which both nucleate and film boiling occur j
intermittently with neither type being completely stable,.
i i
l Trip system - A trip system means an arrangement of instrument channel trip signals and auxiliary eouipment required to initiate l
-e-Amendment No. 102 i
.__m______.__,_
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FRAPS i
1.0 DEFINITIONS (Cont'd) action to accomplish a protective trip function.
A trip system may require one or more instrument channel trip signals related to one or more plant parameters in order to initiate trip system i
action.
Initiation or protective action may require the tripping l
of a single trip system or the coincident tripping of two trip t
systems.
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Unrestricted Area - Any area for chich access control is not required for purposes of protection of individuals from exposure to radiation.
Ventilation Exhaust Treatment System - A ventilation exhaust treatment system is any system designed and installed to reduce j
gaseous radiciodine or radioactive material in particulate form in effluents.
ventino - The controlled process of discharging air or gas from a l
confinement to maintain operating conditions, such that i
replacement air or gas is not provided or required during venting.
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~Ba-Amendment No. 102 I
PBAPS LIMITING CONDITI0ttS FOR OPERATION StmVEILLANCE RFCCIREMENTS C.
Control Rod Block Actuation C.
Control Rod Block Actuation 1.
The limiting conditions of Instrumentation shall be operation for the instru-functionally tested, cali-mentation that initiates brated and checked as indi-control rod blocks are given cated in Table 4.2.C.
in Table 3.2.C.
System logie shall be fune-2.
The minimum number of oper-tionally tested as indica-able instrument channels ted in Table 4. 2.C.
specified in Table 3.2.C for the Rod Block Monitor may be reduced by one in one of the trip systems for maintenance and/or testing, provided that this condi-tion does not last longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any thirty day period.
. Amendment No. 102
PBAPS LIMITING CONDITIONS FOR OFFRATION SUPVEILLANCE REOUIRFMFPTF 3.2.D. Radiation Monitoring 4.2.D.
Radiation Monitoring systems-Isolation and sys t ems-I sola ti on and Initiation Functions Ini tiation Functi ons 1.
Reactor Building Isolation 1.
Reactor Buildina Isolation and Standby Gas Treatment and Standby Gas Treatment System System The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali-Tabl e 3. 2.D.
brated and checked as indi-cated in Table 4.2.D.
System logic shall be func-tionally tested as indica-ted in Table 4. 2.D.
E.
Drywell Leak Detection E.
Drywell Leak Detection The limiting conditions of Instrumentation shall be operation for the instru-calibrated and checked as mentation that monitors indicated in Table 4.2.E.
drywell leak detection are given in Table 3.2.E.
. Amendment No. 102
TABLE 3.2.D RADIATION MONITORING SYSTEMS'THAT INITIATE AND/OR ISOLATE SYSTE9E
~
Micimum No. of
/
Operable No. of Instrument f
Instrument Channels Provided Action Channels Trip Function Trip Level Setting by Design (2) 2 Refuel Area Exhaust Monitor Upscale, <16 mr/hr 4 Inst. Channels A or 8 2
Reactor Building Aree Upscale, <16 ar/hr 4 Inst. Channels B
Exhaust Monitors NOTES FOP TABIE 3.2.D
- 1. Whenever the systems are required to be operable, there shall be two operable or tripped icctrument channels per trip system. If this cannot be met, the indicated action shall be tchen.
- 2. Actim A. Cease operation of the refueling equiyeent.
D. Isolate secondary containment and start the standby gas treatment system.
e e
TABLE 4.2.D MINIM 1M TEST r, CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS
=
h Instrument Functional Instrument Instrument Channels Test Calibration Check (2)
- 1) Refuel Area Exhaust (1)
Once/3 months Once/ day Moni tors - Upscale
- 2) Reactor Building Area (1)
Once/3 months once/ day Logic System Functional Frequency
{
Tenzt (4) (6)
- 1) Reactor Building Isolation Once/6 months
- 2) Standby Gas Treatment Once/6 months f
System Actuation 4
e e
1 I
i q
- 3. 2 BASES (Cont ' d )
The APRM rod block function is flow biased and prevents a significant reduction in MCPR, especially during operation at reduced flow.
The APRM provides gross core protections i.e., limits the gross core power increase f rom withdrawal of control rods in the normal withdrawal cequence.
The trips are set so that MCPR is maintained greater than the fuel cladding integrity safety limit.
The RBM rod block function provides local protection of the core; i.e.,
the prevention of boiling transition in the local region of the core, for a single rod withdrawal error from a limiting control rod patt ern.
The IRM rod block function provides local as well as gross core protecti on.
The scaling arrangement is such that trip setting is less than a factor of 10 above the indicated level.
The downscale indication on an APRM or IRM is an indication the instrument has failed or the instrument is not sensitive enough.
In oither case the instrument will not respond to changes in the control rod motion and thus, control rod motion is prevented.
The downscale trips are set at 2.5 indicated on scale.
1 The flow comparator and scram discharge volume high level components have only one logic channel and are not required for safety.
The flow comparator must be bypassed when operating with one recirculation water pump.
The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.
For effective em'ergency core cooling for small pipe breaks, the HPCI l
cystem must function since reactor pressure does not decrease rapidly (nough to allow either core spray or LPCI to operate in time.
The automatic pressure relief function is provided as a backup to the HPCI in the event the NPCI does not provide this function when necessary cnd minimize spurious operation.
The trip settings given in the specification are adequate to assure the above criteria are met.
The specification preserves the effectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes the risk of inadvertent operation; i.e., only one instrument channel out of service.
l Amendment iio. 76, B, 70, N,102
i PBAPS 3.2 BASES (Cont ' d )
Four sets of two radiation monitors cre provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system.
Four instrument channels monitor the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor.
Each set of the instrument channels is arranged in a 1 out of 2 twice trip logie.
Trip settings of (16 mr/hr for the monitors in the refueling area ventilation exhaust ducts are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is. processed by the standby gas treatment system.
Flow integrators are used to record the integrated flow of liquid from the drywell sumps.
The alarm unit in each integrator is set to annunciate before the values specified in Specification 3.6.C are exceeded.
An air sampling system is also provided to detect leakage inside the primary containment.
For.eech parameter monitored, as listed in Table 3.2.F, therg are two (2) channels of instrumentation.
By comparing readings between the two (2) channels, a near continuous surveillance of instrument performance is available.
Any deviation in readings will initiate an early recalibration, thereby maintaining the quality of the instrument readings.
The recirculation pump trip has been added at the suggestion of ACRS as a means of limiting the consecuences of the unlikely occurrence of a failure to scram during an anticipated transient.
The response of the plant to this postulated event f all within the envelope of study events given in, General Electric Company Topical Report, NE DO-104 39, dated March, 1971.
Amendment No.102
_g3_
l r
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PBAPS LIMITING 00NDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials Applicability Applicability Applies to the radioactive Applies to the periodic monit-of fluents f rom the plant.
oring and recording of radio-active affluents.
Obiective Objective To assnre that radioactive To ascertain that radioactive material is not released to releases are as low as the environment in an uncon-reasonably achievable and trolled manner and to assure within allowable values.
that any material released 10 kept as low as reasonably cchievable and, in any event, in within the limits of 10 CFR 20.
Speci fication Speci fication A.
General A.
General 1
It is expected that releases Operating procedures shall of radioactive material in be developed and used, and offluents will be kept at small eauipment which has been f ractions of the limi ts speci-installed to maintain control fied in Section 20.106 of 10 over radioactive materials CFR Part 20 and as further in gaseous and liauid ef fluents specified in these Technical produced during normal reactor Specifications. At the same operations, including expected time the licensee is permitted operational occurrences, shall the flexibility of operation, be maintained and used, to keep compatible with considerations levels of radioactive material of health and safety, to assure in effluents released to areas that the public is provided a at and beyond the SITE BOUNCARY dspendable source of power as low as reasonably achievable.
oven under unusual operating conditions which may tem-porarily result in releases higher than such small fractions, but still within the limits specified in Specifications 3.8.B.1 and 3.8.C.1, and in Section 20.106 of 10 CFR Part
- 20. It is expected that in using this operational flex-ibility under unusual operating conditions the licensee will 203 Amendment No. 102
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RFOUIREMFNTS srert his best ef forts to keep levels of radioactive anterial in effluents as low as reasonably achievable.
3.8.B Licuid Radwaste Effluents 4.8.B Liquid Radwaste Effluents 1.
The concentration of radio-la. Facility records shall be active material released to maintained of the radio-areas at and beyond the SITE active concentrations DOUNDARY (See Figure 3.8.1) and volume before dilution shall be limited to the con-of each batch of licuid centration specified in ef fluent released, and of 10 CFR 20 Appendix B, Table II, the average dilution flow Column 2 for radionuclides and length of time over other than noble gases and which each discharge 2x10 uCi/ml total activity occurred.
concentration for all dis-Ib. Prior to release of each solved or entrained noble batch of licuid ef fluent, gases. With the concentration a sample shall be taken of radioactive material re-from that batch and analyzed leased to areas at and beyond for the concentration of the SITE BOUNDARY exceeding each significant gamma energy these limits, without delay peak. The release rate decrease the release rate shall be based on the of radioactive materials circulating water flow and/or increase the dilution rate at the time of flow rate to restore the discharge, concentration to within the Ic. Radioactive licuid waste limi ts.
sampling and activity analysis shall be performed in accordance with Table 4.8.1.
2.
The dose or dose commit-2.
Cumulative dose contri-ment to a MEMBER OF THE butions shall be determined PUBLIC from radioactive in accordance with the materials in liauid effluent methodology and parameters releases from the two in the Offsite Dose reactors at the site to Calculational Manual (ODCM )
areas at and beyond the SITE at least once per month.
BOUNDARY (see Figure 3.8.1) shall be limited to:
- a. During any calendar cuarter to < 3.0 mrem to the total body and to
< 10.0 arem to any organ,
- and,
- b. During any calendar year Amendment No. 102 204 i
l
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.1 l
LIMITING CDNDITIONS FOR OPERATION SURVEILLANCE PFOUIRFFFNTS to < 6.0 mrem to the
~
total body and to
< 20.0 mrem to any organ.
When the calculated dose from the release of radioactive materials in liquid effluents exceeds any of the above limits, prepare and submit to the Commission within 21 working days, pursuant to Specification 6.9.3, a Special Report which identifies the causes for exceeding the limits and corrective actions td.at have been taken to reduce the releases of radioactive materials in liquid effluents and proposed corrective actions to be taken to assure that subsequent releases are within the limits.
This Special Peport shall al so include (1) results of radio-logical analyses of the drinking water source and (2) the radiolooical impact on the potentially affected drinking water supplies with regard to i
40 CFR 141, Safe Drinking Water Act. Reactor shut-down is not reauired.
3.
During release of radioactive 3a. The licuid radwaste ef-wastes, the following fluents radiation monitor conditions shall be met:
shall be calibrated
- a. The minimum dilution every 12 months with a water recuired to known radioactive source satisfy 3.8.B.1 shall positioned in a reproducible be met,
geometry with respect to the
- b. The gross activity sensor and every cuarter monitor and flow monitor by means of a source on the waste ef fluent check. Additionally, an line shall be operable instrument functional test except as specified in shall be performed every 205 Amendment No. 4 102
PBAP'S LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMFNTS 3.8.B.3.d and 3.8.B.3.e, month and an instrument below.
check shall be performed
- c. The effluent control every day during release, monitor shall be set in Functional test shall accordance with the denionstrate operability methodology and parameters of the radwaste discharge in the ODCM to alarm and automatic isolation valve, automatically close the and control room an-waste discharge valve nunciation if any of the prior to exceeding the following conditions ex-let:
limits specified in
- 1. Instrument indicates 3.8.B.1 above.
measured levels above
- d. From and after the date the alarm / trip set-that the gross activity point.
monitor on the waste
- 2. Instrument indicates effluent line is made a downscale f ailure.
or found to be inoperable for any reason, effluent 3b. The liquid effluent flow releases may continue monitor shall be cali-only if best ef forts brated every 12 months.
are taken to make such Additionally, an instru-monitor operable, ment check shall be provided that prior performed every day to initiating a during release.
release :
1.
At least two i n-dependent samples of the tank's contents are analyzed, and 2.
At least two technically cualified members of the Facility Staff independently verify the release rate cal-culation and discharge line valving.
- e. From and af ter the date that the flow menitor on the waste effluent line is,made or found to be inoperable for any reason, e f fluent releases via this pathway may continue only if best efforts are taken to make such monitor operable, provided that the flow rate is estimated at j
least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> durine actual releases.
Pump performance curves 206 Amendment No. U,102
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCF RFOUIREMENTS being discharged not -routinely used to without treatment, process licuids for identi fication of dis charge.
any inoperable equipment or sub-systems and the reason for the inoperability.
- b. Action taken to restore the in-operable equipment to operable status.
- c. Action taken to prevent a recurrence.
Reacter shutdown is not required.
3.8.C Gaseous Effluents 4.8.C Gaseous E f fluents 1.
The dose rate in areas at la. The dose rate due to noble and beyond the SITE gases in gaseous effluents BOUNDARY (see Figure shall be determined to be 3.8.1) due to radioactive within the limits in materials in gaseous accordance with the methods effluents released from the and procedures of the
.two reactors at the site shall ODCM.
be limited to the following:
- a. The dose rate for Ib. The dose rate due to noble gases shall be iodi ne-131, iodi ne-133, limited to < 500 tritium, and all radio-mrem /yr to the total nuclides in particulate body and < 3000 mram/yr form with half lives to the skin.
greater than 8 days in gaseous ef fluents shall
- b. The dose rate for be determined to be iodine-131, iodine-133, within the limits in tritium, and for all accordance with the radionuclides in methods and procedures particulate form with of the ODCM by ottaining half lives greater representative samples than 8 day /yr to and performing analyses s shall be (1500 mrem in accordance with the any organ, sampling and analysis program specified in When the dose rates exceed Tabl e 4. 8. 2.
the above limits, without delay, decrease the release rate to comply with the limit.
Amendment No.102 208
^
PRAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREITNTS
~
2..
The air dose in areas at 2.
Cumulative dose contributions and beyond the SITE for noble gases shall be BOUNDARY (see Figure determined in accordance 3.8.1} due to noble gases with the methodology and in gaseous effluents released parameters in the ODCM from the two reactors at the at least once per month, site shall be limited to the followings
- a. During any calendar quarter for gamma radiation: < 10 mrad.
During any calendar quarter for beta radiation: 1 20 mrad.
- b. During any calendar year for gamma radiation:
< 20 mrad.
During any calendar year for beta rad iati on: 1 40 mrad.
When the calculated air dose from radioactive
~
noble gases in gaseous ef fluents exceeds any of the above limits, prepare and submit to the Com-mission within 21 working days, pursuant to Speci-fication 6.9.3, a Special Report which identifies the causes for exceeding the limits and defines the corrective actions that have been taken to reduce the releases and proposed corrective actions to be taken to assure that sub-sequent releases will be within the above limits.
Reactor shutdown is not recuired.
3.
The dose to a MEMBER OF 3.
Cumulative dose contributions THE PUBLIC from iodine-131, for iodine-131, i odine-133, iodi ne-133, tritium and tritium, and radionuclides from all radionuclides in particulate form with half in particulate form with lives greater than 8 days Amendment No. 102 209 Amendment No. $$
PBAPS LIMITING CONDITIONS FOR OPERATION SURVFILLANCE RFOUIREMEb?rF half-lives greater than shall be determined in 8 days in gaseous effluents accordance with the released from the two methodology and parameters reactors at the ' Ate to in the ODCM at least once areas at and beyond the per month.
SITE BOUNDARY (see Figure 3.8.1) shall b'e limited to the following
- a. During any calendar quarter: j,15 mrem.
- b. During any calendar years f,30 mrem.
When the calculated dose from the release of iodine-131, iodine-133, tritium and radionuclides in particulate form, with half-lives greater than R days in gaseous effluents exceeds any of the above limits, prepare and submit to the Commission within 21 working days, pursuant to Specification 6.9.3, a Special Report which identi fies the causes for exceeding the limits and defines the corrective actions that have been taken and proposed corrective actions to assure that sub-sequent releases will be within the above limits.
Reactor shutdown is not recui r ed.
4.
During release of gaseous 4a. The reactor building wastes the following con-exhaust vent and main ditions shall be met to stack noble cas radiation avoid exceeding the monitors shall be cali-limits specified in brated every 12 months with 3.8.C.1:
a known radioactive source
- a. The main off-gas stack positioned in a reproducible minimum dilution flow of geometry with respect to 10,000 cfm shall be the sensor, and every maintained.
quarter by means of a
- b. One reactor building functional test. The exhaust vent monitor channel functi onal test 21 0 Amen &1ent No.102
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREME!?TS and one main stack noble gas monitor shall also demonstrate that control room alarm an-shall be operable and set nunciation occurs if any of to alarm in accordance i
with the methodology the following conditions exist:
)
1.
Instrument indicates and parameters in the measured levels ODCM. From and after the above the alarm date that both reactor setpoint.
building exhaust vent 2.
Instrument _ indicates monitors or both main a downscale f ailure.
stack noble gas monitors Additionally, an instrument are made or found to be check shall be performed inoperable for any reason, every day.
effluent releases via 4b. The reactor building their respective pathway exhaust vent and the may continue provided at main stack flow rate least two independent monitors shall be grab samples are taken at least once per 8 hrs.
calibrated every 12 and these samples are months. Additionally, an instr ument check shall analyzed for 9ross activity within 24 de performed every day.
hours, and at least two 4c. The reactor building exhaust vent and the main technically qualified stack iodine and particulhte members of the facility sampler flow rate monitors staff independently verify the release shall be calibrated, every rate calculations.
12 months. Additionally, an instrument check shall
- c. One reactor building be performed every day.
exhaust vent iodine filter and one main stack iodine filter and one reactor build-ing exhaust vent particulate filter i
and one main stack particulate filter with their respective flow rate monitors shall be.
operable. From and af ter the date that a13 iodine filters or all particulate filters for either the reactor building exhaust vent monitor or the main.
stack monitor are made or found to be inoperable for any reason, ef fluent releases via their respective pathway may Amendment No. 102 211
O
..i i PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS
- i continue provided samples are continuously collected with auxiliary sampling equipment for periods on the order of 7 days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period.
- d. One reactor building exhaust vent flow rate monitor and one main stack flow rate monitor shall be operable and set to alarm in accordance with the methodology and parameters in the ODCM.
From and after the date that both reactor building exhaust vent flow rate monitors or both main stack flow rate monitors are made or found to be inoperable for any reason, effluent releases via their respective pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- e. With less than the minimum number of radioactive gas-ecus effluent monitoring instrumentation channels OPERABLE exert best efforts to return the instruments to OPERABLE status within 30 days and if unsuccessful explain in the next Semi-annual Radioactive Effluent Release Report why the in-operability was not cor-rectedin a timely manner.
5.
Gaseous effluents shall Sa. Doses due to gaseous be processed throuch ef fluent releases to 1
the appropriate gaseous areas at and beyond waste treatment system the SITE BOUNDAPY as described below shall be projected prior to discharce at least once per Amendment No. 102
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMEMF I
- a. Gases from the Steam month in accordance Jet Air Ejector Dis-with the methodology charge shall be and parameters in processed throuch the the ODCM.
recombiner, holdup pipe, off-gas filter, and 5b. The appropriate gaseous off-gas stack.
radioactive waste system equipment as described
- b. Gases from the Mechanical in Specification 3.9.C.5 Vacuum Pump and Gland Steam shall be demonstrated Exhauster discharge operable every quarter, shall be processed unless utilized to through the off-gas process gaseous waste i
- stack, during the previous 13 weeks, by analyzing
- c. Peactor, turbine, the gaseous waste radwaste, and recombiner processed through the building atmospheres appropriate eauipment shall be processed to determine that it through permanently meets the requirements of or temporarily installed Specification 3.8.C.1.
equipment in the appropriate building ventilation system Sc. An air sample shall be and the Reactor Building obtained and analyzed Ventilation Exhaust Stack, from all building areas with the exception of the with an unmonitored following unmonitored exhaust once per month, exhausts:
1.
Recirculation M-G Set and Reactor Buildina Cooline Water equipment' rooms.
2.
Control room utility and toilet rooms.
3.
Cable spread room.
4.
Emergency switchgear rooms.
5.
125/250 VDC Battery rooms and the 250 VDC Battery rooms.
6.
Administration Building maintenance decontam-ination area.
With gaseous waste being discharged without treatment l
as required above, prepare and submit to the Commission within 21 working days i
213
/Wendment No.102
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS pursuant to specification 6.9.3 a Special Report which includes the following informations
- a. Explanaticm of why gaseous i
radwaste was being dis-charged without treatment, identification of any inoperable equipment or subsystems and the reason for its inoperability.
- b. Action taken to restore the inoperable equipment to operable status.
- c. Summary description of action taken to prevent a recurrence.
Reactor shutdown is not required.
G.
The concentration of hydrogen 6a. An instrument check of the downstream of the recombiners operation of the hydrogen shall be limited to less monitors shall be performed than or equal to 2% by once per day.
volume.
- a. With the concentration 6b. The hydrogen monitors and of hydrogen downstream associated alarms downstream of the recombiner greater of the recombiner shall than 2% but less than or be calibrated once per equal to 4% by volume, month.
restore the concentration to within the limit within 6c. Calibration shall include 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
the use of standard gas
- b. With the concentration of samples containing a hydrogen downstream of the nominal recombiner greater than 4%
1.
1% hydrogen, balance by volume, an orderly nitrogen by volume.
reduction of power shall be 2.
4% hydrogen, balance initiated within one hour nitrogen by volume.
to bring the hydrogen down-stream of the recombiner to less than or equal to 24 by volume,
- c. Except as specified in 3.8.c.6.d, two hydrogen j
monitors downstream of the recombinors shall be operable during power operation.
214 Amendment No. 102
,-r-----v-r-nw--,- - -,-wn-m--...----r---
. _ - - =
=_
-l LIMITING CDNDITIONS FOR OPERATION SURVEILLANCE REQUIREME17FS
- d. With the number of hy'drogen monitors operable one less than required, operation may continue for up to 14 days provided grab samples are taken and analyzed daily. With both hydrogen monitors inoperable operation may continue for up to 14 days provided grab samples are taken and analyzed every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during power operation.
7a. The radioactivity release 7a. The radioactivity release rate of noble gases from the rate of noble gases from Steam Jet Air Ejector dis-the Steam Jet Air Ejector charge as determined by discharge shall be determined quantitative analysis of to be within limits at the identifiable gansa emitters following frequencies by shall not exceed 320,000 performing an isotopic uCi/sec af ter 30 minutes analysis of a representa-decay. With the radio-tive sample of gases taken activity release rate of at the discharge of the noble gases from Steam Steam Jet Air Ejector.
Jet Air Ejector discharge exceeding 320,000 uCi/sec 1.
At least once pqr month af ter 30 minutes decay unless the unit has i
restore the radioactivity been out of service for 1
release rate to within the entire month,
its limit within 72 hrs.
2.
Within 4 hrs. following or be in hot standby an increase, if the within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
off-gas monitors indicate an increase of greater than 50% in the steady state fission gas release after factoring out increases due to i
t 7b. One Steam Jet Air Ejector 7b. The Steam Jet Air Ejector j
radiation monitor shall radiation monitors shall be be operable during opera-calibrated every quarter i
tion of a main condenser and an instrument check Steam Jet Air Ejector.
shall be performed once I
Upon loss of both Stear.
per day. Additionally a Jet Air Ejector radiation functional test will be i
monitors, releases may performed every month. The continue via this pathway channel functional test for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided shall also demonstrate that 2' %
Amen &ient No. 102 j
l
5 PBAPS LIMITING CDNDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS temporary monitors are control room alarm an-used. Otherwise, be in at nunciation occurs if any of least NOT STANDBY within the following conditions 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, exist:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Instrument indicates a downscale failure.
- 82. Purging of the primary containment shall be through the Standby Gas Treatment System whenever primary containment integrity is required as specified in 3.7.A.2.
- b. Primary containment purging via the Reactor Building Ventilation Exhaust System may be performed whenever primary containment integrity is not required as specified in 3.7.A.2.
3.8.D 4'O CFR 190 4.8.D 40 CFR 190 1.
The dose or dose commit-1.
Cumulative dose contribu-ment to a MEMBER OF THE tions f rom liquid and gaseous PUBLIC f rom all uranium effluents shall be determined fuel cycle sources within in accordance with the 8 kilometers is limited methodology and parameters to < 25 mrem to the total in the ODCM.
body or any organ (except 2.
Cumulative dose contribu-the thyroid which is limited tions from direct radiation to <75 arem) over the from the reactor units calendar year. With the and from radwaste storage calculated dose from the shall be determined in release of radioactive accordance with the method-materials in liquid or ology and parameters in the gaseous ef fluents, exceeding ODCM.
twice the limits of speci-ficati ons 3.8.B. 2, 3.8.C.2, or 3.8.C.3 calculations shall be made to determine I
whether the limits have been exceeded.
2.
The calculations should be 216 Amendment No.102 1
PBAPS LIMITING CONDITIONS FOlt OPERATION SURVEILLANCE RECUIREMENTS made, including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the limits have been exceeded. If such is the case, prepara and submit to the Commission, within 21 working days, pursuant to Specification 6.9.3, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and schedule for achieving conformance with the above limits.
This Special Report shall include an analysis that estimates the radiation exposure to a MEMBER OF THE PUBLIC, including all effluent pathways and direct radiation, including the releases covered by
'this report, for the calendar year. It shall also describe levels of I
radiation and concen-trations of radioactive j
material involved and the cause of the. exposure levels or concentrations.
If the estimated dose exceeds the above limits and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance i
in accordance with 40 CFR 190. Submittal of the report is con-sidered a timely request and a variance is granted until staff action on the request is complete.
Amendment No. 102
-216a-t-
u PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.E Radiological Environmental 4.8.E Radiological Environmental Monitoring Monitoring
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1.
All deviations from the 1.
The radiological environmental sampling schedule for the monitoring samples shall be radiological environmental collected at the locations monitoring program, as and analyzed as specified required by 4.8.E.1, shall in Table 4.8.3.a and the be documented in the annual ODO(. Deviations are _ permitted
- report, from the required sampling
- a. When the radiological schedule if specimens are environmental monitoring unobtainable due to hazardous program is not conducted conditions, seasonal unavaila-as des'cribed in the ODCM, bility, malfunction of auto-prepare and submit.to natic sampling eauipment or the Commission, in the other legitimate reasons. If Annual Radiological equipment malf unction occurs,.
Environmental Operating an ef fort shall be made Reports, a description to complete corrective of the reasons for not action prior to the end I
conducting the program of the next sampling period.
as required and the plans for preventing a.
The concentration of radio-a recurrence.
activity as a result of
- b. When the level of plant effluents in an-radioactivity as the environmental sampling result of plant ef fluents medium shall be evaluated i
in an environmental on a cuarterly basis j
sampling medium at against the ecuation:
)
one or more of the
]
locations specified concentrati on (1) +
in the ODCM exceeds reporting level (1) 4 the reporting levels of Table 4.8.3.b when concentration (2) +..> 1.0
~
averaged over any reporting level (2) calendar quarter, prepare and submit All radionuclides used to the Commission by in this evaluation shall the closing of the be averaged on a 2
j month following the calendar quarterly basis.
l end of the af fected calendar quarter, a Special Report which includes an evaluation of cny release conditions, environmental factors or other aspects which l
caused the reporting level of Table 4.8.3.b i
to be exceeded. The Special Report shall also define the corrective i
j Amendment No.102
-216a - -
i PBAPS i
LIMITING CDNDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS actions to be taken to reduce radioactive affluents-so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year reporting level of Table 4.8.3.b. When more than one of the radio-nuclides in Table 4.8.3.b l
sampling medit;, this report shall be submitted if:
concentration (1 )
+
reporting level (IT concentrati on (2) +
..>l.0 reporting level- (2)
When radionuclides other than those in Table 4.8.3.b are detected and are the.
result of plant effluents, this. report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifica-tions. The report is not required if the measured level of radioactivity was not the result of plant ef fluents; however, s
in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
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- c. When milk samples become permanently unavailable from any of the sample locations listed in the ODCM, identi fy locations for obtaining i
replacement samples and add them to the radiological environmental monitoring program within 21 working 1
days. Specific locations from which samples are 1
Amendment No. 102
-216a i
PBAPS LIMITING CONDITIONS -FOR OPERATION SURVEILLANCE REQUIREMENTS unavailable may then be deleted f rom the monitoring program. Identify the cause of the unavailability of samples and identify the new locations for ob-taining replacement samples in the next Radioactive Dose Assessment Report and include in the report revis ed figures and tables for the ODCM reflecting the new locations.
2.
A land use census shall be 2a. The land use census shall conducted and shall identify be conducted every the location of the nearest 12 months by a door-milk animal in each of the to-door survey by 16 meteorological sectors consulting local within a distance of five agriculture authorities miles.
or by some other appropriate means.
~
- a. When a land use census identifies a new loca-tion which yields a calculated dose or dose commitment greater than the values currently being calculated in Speci fication 3.8.C.3, identify the new loca-tion in the next Radioactive Dose Assessment Report,
- b. When a land use census identifies a location which yields a calculated dose or dose commitment (via the same exposure pathway) at least 20%
greater than a location from which samples are currently being obtained in accordance with Specification 3.8.E.1, add the new location i
to the radiological environmental monitoring i
prcgram within 21 work-ing days. The indicator sampling location having
-216a I Amendment No.102
1 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this acnitoring program af ter October 31 of the year in which this land use census was conducted'.
Identify the new location in the next Radio-active Dose Assessment Report and include in the report revised figures and tables for the ODO( reflecting the new locaticms.
3.
Analyses shall be performed 3a. A summary of the results on radioactive materials obtained as part of the supplied as part of the EPA Interlaboratory Comparison Environmental Radioactivity Program shall be included Intercomparison Studies Program, in the Annual Radiological or another Interlaboratory Environmental Operating Comparison Program that has Report pursuant to been approved by the Commission.
Specification 6.9.3.
- a. With analyses not being performed as required above report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Operating Report.
3.8.F Solid Radioactive Waste 4.8.F Solid Radioactive Waste 1.
The solid radwaste system 1.
The PCP shall be used to shall be used in accordance ensure meeting the burial l
with a Process Centrol ground and shipping re-Program (PCP) to process cuirements prior to shipment wet radioactive wastes to of radioactive wastes from j
meet shipping and burial the site.
ground reouirements,
- a. With the provisicms of the Process Control Program not satisfied, suspend shipments of defectively packaged solid radio-active waste from the site. Reactor shutdown is not required.
Amendment No. 102
-216a,
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.G Mechanical Vacuum Pump 4.8.G Mechanical Vacuum Pump
-l; 1.
The mechanical vacuum pump At least once during each shall be capable of being operating cycle verify isolated and secured on a automatic securing and signal of high radio-isolation of the mechanical activity in the steam vacuum pump.
lines whenever the main steam isolation valves are open.
2.
If the limits of 3.8.G.1 l
are not met the vacuum pump " ~ ~' ~ ~ ~ ~
shall be isolated.*
I I
i Amendment No.102 216a-6 i
An
PBAPS TABLE 4.8.1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS Sample Lower Limit of Detection Sample Type Sample Frecuency Sample Analysis (LLD)(1)f4)(5)
-7 Waste Tank to Each Batch (2)
Quantitative 5 x 10 uci/ml be released Analysis of Identifiable Gamma Emitters
-6 I-131 1 x 10 uCi/ml
-6 P roportional Monthly (3)
Fe-55 1 x 10 uCi/ml Composite of
-5 Batches Tritium 1 x 10 uCi/ml-
-7 Gross Alpha 1 x 10
,uci/ml
-8 P roportional Monthly (3)
Sr-89 5 x 10 uCi/ml Composite of
-8 Batches Sr-90 5 x 10 uCi/ml
-5 One Batch Monthly dissolved noble 1 x 10 uCi/ml gases Notes l
1.
The Sample Lower Limit of Detection is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
The values for the lower limit of detection are based on a 95% confidence level.
16b-1 Amendment No. 102 i
i l
l
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u.
PBAPS 2.
A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analysis, each batch shall be d
isolated and thoroughly mixed to assure representative sampling.
3.
A composite sample is one in which the quantity of the sample is proportional to the quantity of liquid waste discharged and in which the method of sampling results in a sample representative of the liquids released.
4.
The principal gamma emitters _ for which the minimum detectable level specification will apply are exclusively the following radicmuelides: Mn-54, Fe-59, Co-58, co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the sample detectable limit for the analyses should not be reported as being present at the sample detectable limit level.
When unusual circumstances result in sample detectable limits higher than required, the reasons _shall be documented in the Semi-Annual E f fluent Report.
The values listed are believed to be attainable.
5.
Certain mixtures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher concentrations.
Under these circumstances use of known ratios of radienuclides will be appropriate to calculate the levels of such radienuclides.
I i
216b-2 Amendment No, 102 e
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PBAPS TABLE 4.R.2 RADIOACTIVE GAFFOUS QSTE SAPPLIFG AFD AMALYSIS FF0F VAIN OFF-GAS STACK AFD RFACTOR BUII.DIPG VENT F.XFA CET STACK Sample Lower Limit of Sample Type Sample Frecuency Sample Analysis Detecti on (LLD)(3)(4)
-4 Grab Sample Monthly (2)
Quantitative 1 x 10 uCi/ce(3)
Analysis of Identifiabl e Gamma Emitters
-6 Grab Fample Quarterly Tritium 1 x 10 uCi/cc Charcoal Yeekly(3)
I-131 1y 10 uCi/ce(?)
-10 Farticulate reekly(3)
Cuantitative 1 x 10 uCi/cc(?)
Filters Analyris of 18entifiab3e Gamma Fmitterr
-12 I-131 1 x 10 uCi/ce(?)
Pa rti culat e Monthly Gross Alpha 1 x 10 uCi/cc (composite of weekly filters)
-11 Particulat e Monthly Sr-Po 1 x 30 uCi/cc Filters
-11 (ccmposite of Sr-90 1 x 10 uCi/cc weekly filters )
Nobl e Gas Continuously Noble Gas s
X u
/cc 8
3 Stack) 1 Neb 3e cas Ccntinuous3y Foble cas
-f j
Ponitor Crossjg or)d 3 x Jn uCi/cc (Foof Vents) 216c-1 Amendment No. 102 i
\\
.l PBAPS l
Notes i
1.
The Sample Lower Limit of Detection is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
The values for the lower limit of detection are based on a 9b4 confidence level.
2.
Sampling and analysis shall be performed following shutdown, startup or a thermal power change exceeding 15 percent of rated thermal power within one hour from a steady state condition unless (1) analysis shows that the dose equivalent I-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) the noble gas activity monitor shows that ef fluent activity has not increased by more than a factor of 3.
3.
Samples shall be changed at least once per 7 days and analyses l
shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 3 days following each shutdown, startup or thermal power change exceeding 15 percent of rated thermal power in one hour and analyses shall i
be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.
When samples. collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD may be increased by a factor of 10.
This recuirement does not apply if (1) analysis has shown that the dose ecuivalent I-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that ef fluent activity has not increased more than a factor of 3.
4.
Certain mixtures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher conce ntra tions.
Under these circumstances use of known ratios of j
radionuclides will be appropriate to calculate the levels of such radionuclides.
Nuclides which are below the sample detectable i
limit for the analyses should not be reported as being present at the sample detectable limit level, i
Amendment No. 102 216c-2 l
i
TABLE 4.8.3.m Iwn1Of(CICAL 11NIIOte2frAL HF11104ItG HGWM t&sati r of Samples Ex[asure Patimoy ad Sarapilng and Tyge and Frc<n-rcy
_ _arul/or Scaple Sample incation[al, Collection Frunnescy(bg of Analysis e
- 1. pliuct RAnlATICN At least 40 routine aceitorirq At least monthly Casana dose at least stations either with two or more
- monthly, dasi.neters or with one instrunamt or for measuring ard recordirq dcrae or rate continuously to te placed as At least ouarterly follos: 1) an inner ring of sta-Cassaa ame at least tions in tha general area of the spirterly.
Sint is0UNIARY #d an outer rirq in the 3 to 6 mile rarvje from tie site. A station is in eadi sector of each ring except as dictated by local geojral ry.1he balance of k
tie stations are in stu:lal interest areas such as Enpulatirn centers, neartsy residences, sdsmis aral in areas to serve as control
- stations, g
- 2. AIRHOINE
- 3 Rallolotire &
Sa+1es frcan 5 locations:
Contiruma sappler R:mitoleilne Cannisters g"
Part iculates operation with smple Y-T11analysisweekV g
- a. 3 samples from close to the collection at least S11E EGJt4 arf locations (in weekly or re m tred n
different sectors) of the by dust loading, Particulate Smplert (f) highest cala 1ated annual uhichever is more cross beta radio-
~o aferage grours11evel D/Q.
frecyaent.
activity analysis follo<ing filter o
- b. I sample from tie vicinity changes Canna isotopic N
of a casununity having the analysis of couposite highest calculated annual (by location) matterly, average grousv11evel D/Q.
- c. I sample from a cantrol location unlikely to te affected by tie plant.
-216d.
l I
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m tE 4.8.3.a icantinug NADIOttnien. twuel?tngrAL tm:1osits psocpan lasder of Samples Dqmure Pattu.sy and Samoltrq and Type and Fren mncy
_arst/or S.manie _
Sample incation(a)_
collectica Freaueracygg of Analysis
- 3. t:ATERurnee b
- a. Surface
- a. I sample upstrean couposite szsaple Cansaa Isotopic (d) analysis
- b. I saanle dunstream over 1 saunth monthly, curiosite for
- period, tritium aralysis at least rpsarterly.
b
- b. Drinkiry
- a. I sisaple of each of 1 to 3 Cngosite sanple Charmite for gross of the nearest water sugplies over monthly leta and gasreald) that could te affected by its oraarosite isotopic analyses g
disd.arge, period.
sonthly. Chaposite for en tritium analysis at 3
- b. I sa.aple frun a control least quarterly.
locaticui en a"
- c. Sediment from I sample fras dwnstrease area Se.al-annually Gamma isotopic (d)
Shoreline with existing or potential analysis semi-recreational value.
annually.
- 4. INGFSTION o"
- a. Hilk
- a. Sanples from milkirq animals San!-sonthly then Gamma isotopic (d) analysis in 3 locations within 3 alles animals are on or 134,117 Ce ty distance having the highest pasture, sonthly chealcal separation dose potential.
at other times, quarterly. I-131 analysis of each sample.
- b. I sample fran allking animals at a control location (unlikely to be affected ty the plant).
- b. Fish
- a. I sa:ple of each commercially Sample in season, or Cassna isotopic (d) analysis ard recreationally important semi-annually if they on edit,le portions.
l species in vicinity of dis-are tot seasonal i
charge reint when available.
- b. I sapple of same species in areas not influenced lif plant discharge wfen available.
-216d *
~
4 4
k
-u
- rAntE 4.9.3.a.{Crmtinnedl IVJ)IOt(1GICAL I2NilOISWPAL WEll'IORItG PIOGRAM tender of Samples 1
ExInsure Pattudy and Sa;npilsg and Type and Fregaency and/or Scenple Sample location {al
. Collection Frc<aaency(b,c[
of Analysis
- c. Food Prcxbcts
- a. Sa@les of 3 different kin 5s nmthly when Causna isotopic (d) and of broad leaf vegetation grown available if milk 1-131 analysis, nearest offsite garden of sampling is higtest annual average ground-rot performed.
level D/0 if milk samplirq is not performe.l.
- b. I sample of each of the similar Monthly when Ganna isotopic (d) and brom5 leaf vegetation grown available if allk I-131 analysis.
15-30 km distant in Lle least samplirq is 3
g prevalent wind direction if not performed.
to milk sa.npling is not performed.
- s$
I_D_i_f_:S_
5 al Fixed sahple locations are stom in tie Offsite Dose Calculation Manual, Table VII.A.1 and i
Figures VII.A.1, VII.A.2, and VII.A.3.
At times it may rot te possible or practfcalG to obtain 2
samples of tie media of choice at the most desired location or time. In these instances o
suitable alternate media ard locations may be closen for the particular pattway in cpestion.
Such raccesary deviations are rerorted in the Annual Environmental Radiolojical Operating
,g Report.
b) Ccanposite sanples shall be collected by collectirq an aliquot at intervals not exceeding two tours.
/
c) Sainple cnllection fsecpncies are defined as follms:
1.tekly:
7 calendar days + two days i
Bi-weekly:
14 calendar days 1 three days tenthly a calendar : month i eight days
]
Oaarterly:
a three noith calendar pericx3
+ ten days Sant-annually: a six month calerular perlod i twenty days
-216d.
i
TAnfE 4.8.3 (Continued)
J RADIOtt1GICAI, DWlHOt4WNFAL IH11'K) RING IWlGHAM d) Canna isotopic analysis me.sns Lie identification and causntification of classuna-seitting rallonuclides that may te attritutable to the effluents from the facility, f:ach 1 os1 xx is crnsidered one thernoturninescent cbsimeter, 4
4 al f) If tie gross teta activity in air attritutable to plant operation is greater then ten times the yearly mean of control samples, ganana isotopic analys,is shall te performed on the inilvidual samples.
N
- 3 "3
et 2O emme O
N 4
4
-216d.
O e
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TABLE 4.8.3.b REPORTING LEVELS FOR RADIOACTIVITY CONCEMRATIONS IN ENVIRONMEWAL SAMPLES N
Reporting I.evels 8"
Water Airborne Particulate Fish Milk Food Products y
Analysis (pCi/1) or. Gases (pCi/m3)
(pci/kg. wet)
(pCi/1)
(pci/kg. wet) g H-3 20,000*
ru Mn-54 1,000 30,000 Fe-59 400 10.000 Co-58 1,000 30,000 co-60 300 10,000 E
Zn-65 300 20,000 E
i Zr-Nb-95 400 Y
I-131 0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 For drinking water samples.
This is 40 CFR Part 141 value.
1 h
.ee 4
-6 1
TABLE 4.8.3.c MAXIMUM VALUES FOR MINIMUM DETECTABLE LEVELS OF ACTIVITY (MDL) a Food Airborne Fish Products Sediment I
Water Particulate (PCi/kg,
Milk (pCi/kg, (pCi/kg,
. Analysis (pci/1)
(pci/m3) wet)
(oci/1) wet) dry) gross 2.5
.006 beta 3H 1200 54Mn 9
80 59Fe 18 160 58,60Co 9
80 652n 18 160 952r-Nb 9
131I
.04 0.6 36 134,137Cs 9,11
.04 90 10 4,0 100 140Ba-La 9
9 TABLE NOTATION a'- Analyses shall be perf.7rmed in such a manner that the stated MDLs will be achieved under routine conditions at a 954 confidence level.
Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides or other uncontrollable circumstances make these MDLs unachievable.
i i
-216d-6 Amendment No.102
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- Amendment No.102
l PBAPS 3.8.A & 4.8.A BASES General It is expected that releases of radioactive material in effluents will be kept at small fractions of the limits specified in Section 20.106 of 10 GR, Part 20.
At the same time, the licensee is permitted the flexibility of operation, compatible with consideraticzis of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in i
releases higher than such small fractions, but still within the limits specified in Secticn 20.106 of 10 GR, Part 20.
It is expected that in using this operational flexibility under unusual operating conditicris the licensee will exert his best efforts to keep levels of' radioactive material in effluents as low as practicable.
- 3. 8.B & 4. 8.B B ASES Concentration This specificatien is provided to ensure that the concentr'ation of radioactive materials released in liquid waste effluents to areas at and beyond the SITE BOUNDARY will be within the concentration levels specified in 10 GR, Part 20, Appendix B, Table II, Column 2.
This instantaneous limitation provides additional assurance that the levels of radioactive materials in bodies of water in areas at or beyond the SITE BOUNDARY will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 GR, Part50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 GR, Part 20.106(e) to the population.
The concentratien limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2.
Dos e This specification is provided to implement the recuirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting condition for Operation implements the guidance set forth in Section II.A of Appendix I and provides the recuired operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of Amendment No.102
-216f _ _ _ _... -
t PBAPS radioactive material in licuid effluents will be kept "as low as reasonably achievable".
The dose calculations in the ODO1 implement the requirements in Section III.A of Appet. dix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate I
pathways is'unlikely to be substantially underestimated.
The i
equations described in the Off site Dose Calculation Manual for i
calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the l
methodology provided in Regu3 atory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 GR Part 50, i
Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113,
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977.
This specificaticn applies to the release of liquid ef fluents f rom the site.
Instruments:len i
The radioactive liauid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive
- materials in licuid ef fluents durina actual or potential release of liquid affluents.
The operability and use of this instrumentation is consistent with the recuirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR, Part 50.
System Operation The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid ef fluents recuire treatment prior to release to the environment.
The requirement that the appropriate portions of this system be used when specified provides assurance that the releases to radioactive materials in liquid effluents will be kept "as low as reasonably achievable".
This specification implements the requirements of 10 CFR, Part 50.36a, General Design Criterion 60 of Appendix A to 10 GR, Part 50 and design objective Section II.D of Appendix I to 10 GR, Part 50.
The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Secticm II.A of Appendix I, 10 CFR, Part 50, for liquid ef fluents.
i Amendment No.102
-216f._ --
PBAPS 3.8.C & 4.8.C BASES i
Dos e I
This specification is provided to ensure that the dose 'from radioactive materials in gaseous effluents at and beyond the SITE BOUN M RY will be within the annual dose limits of 10 CFR Part 20.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNMRY, to annual average concentrations exceeding' the limits specified in Appendix B, Table II of 10 CFR Part 20.106(b)
For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNMRY, the occupancy will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNMRY.
Examples of calculations for such MEMBERS OF THE PUBLIC with the appropriate occupancy factors i
are given in the ODQ4.
The specified limits restrict, at all l
times, the gamma and beta dose rates above background to a MEMBER OF THE PUBLIC, at or beyond the SITE BOUNMRY to < 500 mres/ year to the total body or to 13000 area / year to the sEin.
These dose rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhqtlation pathway to 1 1500 mres/ year.
Dose, Noble Gases This specification is provided to implement the requirements of i
Sections II.B, III.A and IV.A of Appendix I,10 CFR Part 50.
The Limiting Condition for Operation implements the guidance set i
forth in Section II.B of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable".
The Surveillance Requirements implement j
the requirements in Section III.A of Appendix I that conformance j
with the guidances of Appendix I be shown by calculational
{
procedures based on models and data much that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is i
unlikely to be substantially underestimated.
The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous ef fluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I",
Revision 1,
-216f Amendment No. 102 i
l l
PBAPS October 1977 and the atmospheric dispersion model submitted on l
September 30, 1976, in a report titled: "Information Requested in i to letter from George Lear to E. G. Bauer dated February 17, 1976".
The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
Dese - Iodine-131, Tritium and Radionuclides in Particulate Form I
This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I,10 CFR Part 50.
The Limiting conditica for Operation implements the guidance set i
forth in Section II.C of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable".
The ODW calculational methods i
specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The ODW calculational methods,
for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory. Guide 1.109, " Calculation of Annual Doses to Mart from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and the Atmospheric Dispersion Model submitted on September 30, 1976 in a report titled: "Information Requested in to letter from George Lear to E. G. Bauer dated February 17, 1976".
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate specifications for iodine-131, tritium, and radienuclides in particulate form with half lives 4
greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.
I The pathways that were examined in the development of these i
calculatims were: 1) individual inhalation of airborne radionuclides, 2) deposition of radienuclides onto green leafy vegetation with subseauent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
I i
I Amendment No.102
-216f l
PBAPS F
Instrumentati on The radioactive gaseous effluent instrumentation is provided to
~
monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The operability and use of instrumentation is consistent with the requirements of General Design criteria 60, 63 and 64 of Appendix A to 10 CFR, Part 50.
System Operation i
l The operability of the gaseous radwaste treatment system ensures that this system will be available for use whenever gaseous ef fluents require treatment prior to release to the environment.
The requirement that appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".
This specification implements the j
requirements of 10 CFR, Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR, Part 50 and design obj ective section II.D of Appendix I to 10 CFR, Part 50.
The specified limits governing the use of appropriate portions of the gaseous radwaste treatment system were specified as a suitable fraction of the 4.
guidance set forth in Sections II.B and II.C of Appendix I, 10 CFR, Part 50, for gaseous ef fluents.
Main Condenser Restricting the gross radioactivity release rate of noble gases from the main condenser provides reasonable assurance that the total body exposure to an individual at the SITE BOUNDARY will not exceed a small fraction of the limits of 10 CFR, Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment.
This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR, Part 50.
Hydrocen Gas Mixture j
This specification is provided to ensure that the concentration of potentially explosive hydrogen gas mixtures contained in the waste gas holdup system is maintained below the flammability i
limits of hydrogen.
Maintaining the concentration of hydrogen below its flammability limits provides assurance that the releases of radioactive materials will be controlled in Amendment No. 102
-216f !
i
PBAPS conformance with the requirements of General Design criterion 60 of Appendix A to 10 CFR Part 50.
Containment Purge, Specification 3.8.C.8 requires that the primary containment atmosphere receive treatment for the removal of gaseous iodine and particulates prior to release to provide-reasonable assurance that purging operations will not result in exceeding the annual i
dose limits of 10 CFR Part 20 for areas at or beyond the SITE BOUNDARY.
Total Dose This specificaticri is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 GR Part 30.
This specification requires the preparation and submittal of a Special Report whenever the calculated doses.from plant radioactive effluents exceed twice the design objective doses of Appendix I.
It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within the reporting requirement level.
The Special Report will describe a course of action that should result in the limitation of the annual d'ose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.
For I
the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers (km) must be considered.
If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected ),
in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is considered to be a timely reauest and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.
The variance only relates to the l
limits of 40 CFR Part 190, and does not apply in any way to the i
other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1 and 3.11.2.
An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
4 i
t Amendment No.102
-216f.
S PBAPS 3.8.E & 4.8.E BASES j
Monitoring Program The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead-to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the two reactors at the site.
This monitoring program implements section IV.B.2 of Appendix I to 10 CFR Part 50 and supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the ef fluent measurements and the modeling of the environmental 4
exposure pathways.
The reauired detection capabilities for environmental sample analyses are tabulated in terms of the Minimum Detectable Level (MDL).
The MDL's required by Table 4.8.1 and 4.8.2 cf the specifications are considered optimum for routine environmental measurements in industrial laboratories.
The monitoring program -
was developed utilizing the experience of the first seven years of commercial operation.
Program changes may be initiated, based on the additional operational experience.
Land Use Census This specification is provided to ensure that significant changes 4
in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census.
This census satisfies the reouirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.
Interlaboratory Comparison Program i
The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices, are performed as part of the quality assurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
i Amenament No. 102
-216f V
PBAPS 6.5.1.6 Continued h.
Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Plan, to the Chairman of the Operation and Safety Review Committee, i.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Plan, to the Chairman of the Operation and Safety Review Committee.
j.
Review of every unplanned release reportable under 6.9.2.b.(5) of radioactive material to the environs; evaluate the event: specify remedial action to prevent recurrencer and document the 4
event description, evaluation, and corrective action and the disposition of the corrective action in the plant records.
Authority 6.5.1.7 The Plant Operation Review Committee shall:
a.
Recommend to the Station Superintendent written j
approval or disapproval of iter.s considered under i
- 6. 5.1.6 (a ) thro ugh (d ) above.
I b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question, as defined in 10 CFR 50.59.
i c.
Provide immediate written notification to the j
Superintendent, Generation Division-Nuclear or, in his absence, the Superintendent, Generation Division-Fossil-Hydro, and the Operation and Safety Review Committee of disagreement between 1
the PORC and the Station Superintendent; however, the Station Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
i Amendment No. 79, 37, g3,102
-248-
~.
PBAPS Records 6.5.1.8 The Plant Operation Review Committee sha'l maintain writhen minutes of each meeting and cop!.ss shall be provided to the Superintendent, Generation Division-Nuclear and Chairman of the Operation ud Safety Review Committee.
J Amendment No.102 1
-248a-l
,,,_,,,,,,,,-.,.___,,g.g.,
,,,__.-w.
j f
4 9
PBAPS 6.5.2.8 Continued h
The Facility Erargency Plan and implementing e.
procedures e'. least once per two years.
f f.
The Facility Security Plan and implementing procedures at least once per two ycars.
l 5
g.
The Offsite Dose Calculation Manual and implementing procedures at least once per two years.
i h.
The performance of activities recuired by the Quality Assurance Program regarding the i
i radiological monitoring program to meet the provisions of Regulatory Guide 4.1, Revision 1, l
April 1975, at least once per calendar year.
4 i.
Any other area of facility operation considered appropriate by the OSR Committee or the Vice President, Electric Production.
Authority i
1 6.5.2.9 The OSR Committee shall report to and advise the Vice President, Electric Production on those areas of responsibility specified to Section 6.5.2.7 and 6.5.2.8.
Records f
6.5.2.10 Records of OSR Committee activities shall be prepared, f
l approved, and distributed as indicated below:
l 2
i a.
Minutes of each OSR Committee meeting shall be prepared, a,neroved and forwarded to the Vice l
President,1 tectric Production within 14 days following e.ch meeting.
l l
b.
Reports of review encompassed by Section 6.5.2.7.e, f,g, and h above, shall be prepared,
approved and forwarded to the Vice President, Electric Production within 14 days following completion of the revisy.
Amendment No. J2, $7,102
-252-
l 4
PBAPS c.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President, Electric Production and to the management positions responsible for the areas audited within 30 days after completion of the audit.
i i
e
-252a-Ar.iendment No.102 l
i PBAPS 1
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Station Superintendent or his designated alternate per Specification 6.1.1 prior to implementation and periodically as set forth in J
administrative procedures.
t 6.8.3 Temporary changes to procedures of 6.8.1 above may be made, provided:
I l
a.
The intent of the original procedure is not altered.
i i
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit
- affected, c.
The change is documented, reviewed by the PORC and l
approved by the Station Superintendent within 14 days of implementation.
I l
6.8.4 Written procedures shall be established, implemented and i
maintained covering the activities of the radiological j
effluent technical specifications as referenced belows i
I a.
Offsite Dose Calculation Manual
}
i i
b.
Quality Assurance Program for the environmental j
monitoring using the guidance in Regulatory Guide j
4.1, Revision 1, April 1975.
I 6.9 Reporting Requirements In addition to the applicable reporting requirements of l
Title 10, code of Federal Regulations, the following identified reports shall be submitted to the Administrator of the appropriate Regional Of fice unless l
otherwise noted.
l l
l Amendment No. M, #, #7,102
-254-E..
1 PBAPS 6.9.1 Routine Reports I
a.
Startup Report. A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.
The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating condition ~s or characteristics
' obtained during the test program and a comparison of these values with design predictions and i
i speci fications.
Any corrective actions that were l
required to obtain satisfactory operation shall l
also be described.
Any additional specific j
details required in license conditions based on j
other commitments shall be reported in this report.
l Startup reports shall be submitted within 90 days following resumption or commencement of commercial full power operation.
j b.
Annual Occupational Exposure Tabulation (1) i i
A tabulation shall be made on an annual basis of l
the number of station utility and other personnel 1
(including contractors) receiving exposures greater than 100 ares /yr and their associated man-rem exposure according to work and job function, l
(2) e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
This tabulation shall be submitted for the previous calendar year prior to March 1 of each year.
The dose assignment to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposure totalling less than 20% of the individual total dose need not be accounted - for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major job functions.
1 l
l l
(1)
A single submittal may be made for a multiple unit station.
i (2)
This tabulation supplements the requirements of 10 CFR 20.407.
)
Amendment No. 37, S3, 102
-254a-
o 4
I PBAPS 6.9.2 Continued (7)
Conditions arising from natural or man-made events that, as a direct result of the event require plant shutdown, operation of safety systems, or other protective measures required by technical specifications.
(8)
Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in i
the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
(9)
Performance of structures, systems, or components that requires remedial action or corrective
]
measures to prevent operation in a manner less conservative than assumed in the accident analyses i
I in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
Note: This item is intended to provide for reporting of i
potentially generic problems.
1 (10)
Occurrence of an unusual or important radiological event that has potential environmental impact from unit operation, or that has high public interest i
concerning environmental impact f rom unit operation.
b.
Thirty Day Written Reports.
The reportable occurrences discussed below shall be the subject of written reports to the Director of the appropriate Regional Office within thirty days of occurrence of the event.
The written report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
Amendment No. 102
-256-
PBAPS (1)
Reactor protection system or engineered safety f eature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
(2)
Conditions leading to operation in a. degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
Note: Routine surveillance testing, instrument calibration, or preventative maintenance which require system configurations as described in items 2.b(1) and 2.b(2) need not be reported except where test results themselves reveal a degraded mode as described above.
l 4
(3)
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
1 (4)
Abnormal degradation of systems other than those i
specified in item 2.a(3) above designed to contain radioactive material resulting from the fission process.
Note: Sealed sources or calibration sources are not included under this item.
Leakage of valve packing or gaskets within the limits for identified leakage set forth in technical specifications need not be reported under this 3
item.
(5)
An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid ef fluents, i
- 2) more than 150 curies of noble gas from a roof vent or 15,000 curies of noble gas f rom the stack in gaseous effluents, or 3) more than 0.05 curies i
of radiciodine from a roof vent or 5 curies of 2
l radiciodine from the stack in gaseous ef fluents.
The report of an unplanned off site release of i
radioactive material shall include a description of the event and equipment involved, the cause(s) of the unplanned release, the actions taken to Amendment No. 102
-256a-
PBAPS A
prevent recurrence, and the consequences of the 4
unplanned release.
6.9.3 Unioue Reporting Reauirements Special reports shall be submitted to the Director of the appropriate Regional Office within the time. period specified for each report.
These reports shal1 be i
submitted covering the activities identified below 4
pursuant to the recuirements of the applicable reference specification:
a.
Loss of shutdown margin, Specification 3.3.A and 4.3.A within 14 days of the event.
b.
Reactor vessel inservice inspection, Specification 3.6.G and 4.6.G within 90 days of the completion of the reviews.
i
~
c.
Report seismic monitoring instrumentation inoperable for more than 30 days (Specification 3.15B) within the next 10 working days.
Submit a seismic event analysis (Specification 4.15B) within 10 working days of the event.
d.
Primary containment leak rate testing j
approximately three months af ter the completion of the periodic integrated leak rate test (Type A) required by Specification 4.7.A.2.c.2.
For each periodic test, leakage test results from Type A, B and C tests shall be reported.
E and C tests are local ler.k rate tests required by Specification t.
4.7.A.2.f.
The report shall contain an analysis and interpretation of the Type A test results and a summary analysis of periodic Type B and Type C l
tests that were performed since the last Type A i
test.
l l
e.
Calculated dose from release of radioactive j
e f fluents, Specification 3.8.B.2, 3.8.B.4, 3.8.C.2, 3.8.C.3, 3.8.C.6, and 3.8.D.
)
l f.
Sealed source leakage in excess of limits, Specification 3.13.2.
l Amendment No.17, #7, Ea, 7s,102
-257-I
.c g.
The concentration of radioactivity in excess of the environmental monitoring program reporting
~
levels per Specification 3.8.E lb.
h.
Effluent Releases (1)
Annual Radiological Environmental Operating Report i
Routine radiological environmental operating reports covering the previous calendar shall be submitted prior to May 31 of each year.
The annual radiological environmental operating reports shall include summaries, interpretations, and evaluations of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies with operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.
Th9 reports shall also include the results of the annual land use census recuired by Specification 3.8.E.2.
The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in Table 4.8.3, as i
well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as pcssible i
in a supplementary report.
The reports shall also include or reference f rom previous reports the followings a summary description of the radiological i
4 Amendment No. 102
-258-
l l
PBAPS j
environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, and measuring ecuipment used; at least two maps of all sampling locations keyed to a table giving distances and directions from the midpoint between reactor vents; the results of land use censuses required by Specification 3.8.E.2; the results of the Interlaboratory Comparison Program and discussion of all analyses in which the LLD required by Tables 4.8.1 and 4.8.2 was not achievable.
(2)
Semiannual Radioactive Effluent Release Report Routine radioactive effluent release reports covering the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liauid and gaseous effluents and solid waste released from the site.
i The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 i
j CFR Part 61) shipped offsite during the report periods i
a.
Container volume, b.
Total curie quantity (specify whether j
determined by measurement or estimate),
i c.
Principal radionuclides (specify whether determined by measurement or estimate),
d.
Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms), and
-2H-Amendment No.102
. - ~ - - - - -
l PBAPS e.
Type of container (e.g., LSA, Type A,
~ i Type B, Large Quantity).
j l
The Radioactive Effluent Release Reports l
shall include a list and description of l
unplanned releases from the site to areas at i
and beyond the SITE BOUNDARY of radioactive materials in gaseous and liquid effluents j
made during the reporting period. -
l l
The Radioactive Effluent Relekse Reports shall include any changes made during the reporting period to the OF7 SITE DOSE CALCULATION MANUAL (ODOf), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.8.E.2.
(3)
Radiation Dose Assessment Report The radiation dose assessment reports shall be submitted within 120 days af ter January 1 l
of each year.
The Radiation Dose Assessment Report shall include an annual summary of hourly meteorological data collected over the 3
I previous year.
This annual summary may be I
either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind i
direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind j
speed, wind direction, and atmospheric j
stability.** This same report shall include an assessment of the radiation doses due to j
the radioactive liquid and gaseous effluents I,
released from the unit or station during the i
previous calendar year.
This same report 1
shall also include an assessment of the radiation doses from radioactive liquid and gaseous ef fluent to MEMBERS OF THE PUBLIC due j
to their activities inside the SITE BOUNDARY during the report period.
All assumptions l
used in making these assessments (i.e.,
specific activity, exposure time and 4
j location) shall be included in these reports.
The meteorological conditions concurrent with l
the time of release of radioactive materials f
Amendment No. 102
-259a-
..l 4
in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.
Approximate methods are acceptable.
The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The Radiation Dose Assessment Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards i
for Nuclear Power Operation.
Guidance for I
calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1, October 1977.
If doses f rom plant effluents do not exceed twice t,he Appendix I limits, a statement to that effect shall constitute a 40 CFR 190 assessment.
In lieu of submission with the first half year Radioactive Effluent Release l
Report, the licensee will retain this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
I i
i ff i
I l
l l
l Amendment No. 102
-259b-l
. i 6.10.2 Continued d.
Records of radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
g.
. Records of training and qualification for current members of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required by the OA Manual, except as described in 6.10.1 above.
e j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
j k.
Records of meetings of the PORC and the OSR Committee, i
1.
Records for Environmental Qualification which are l
covered under the provisions of paragraph 6.16.
m.
Records of analyses required by the radiological l
environmental monitoring program that would permit
{
evaluation of the accuracy of the analysis at a later date.
This should include procedures ef fective at specified times and QA records showing that these procedures were followed.
1
-26l-Amendment No.,M,102 Order dated 10/24/80
.._... o 4
PBAPS 6.11 Radiation Protection Program Procedures for personnel radiation protection shall be prepared consistent with requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
j i
6.12 Fire Protection Inspections a.
An independent fire protection ard loss prevention program inspection shall be performed at least once per 12 months utilizing either qualified off site licensee personnel or an outside fire protection firm.
b.
An inspection of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once i
per 36 months.
a 4
i 4
i i
1
-261a-l Amendment No. 102
PBAPS 6.17 offsite Dose Calculation Manual (CDCM) 6.17.1 The ODCM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, f
6.17.2 Licensee initiated changes to the ODCM:
l 1.
Shall be submitted to the Commission in the semiannual Radioactive Ef fluent Release Report for the period in which the change was made.
This submittal shall contains i
a.
Suf ficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted should consist of a package of those pages of the ODS to be changed with each page numbered j
and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s) i b.
A determination that the change will not, i
reduce the accuracy or reliability of dose j
calculations.
a
}
2.
Shall become effective upon a date specified and agreed to by the PORC following their review and l
acceptance of the change (s).
1 6.18 Maior Changes to Radioactive Waste Treatment systems 6.18.1 The radioactive waste treatment systems are those i
systems described in specifications 3.8.B.3, 3.8.B.4, 3.8.C.4 and 3.8.C.5, which are used to maintain control over radioactive materials in gaseous and liould e f fluents.
6.18.2 Major changes to the radioactive wasta systems shall be made by either of the followiny methods.
For the purpose of this specification major changes' is defined in specification 6.18.3 below.
Amendment No. 102
-265-l
. ~.. _ _.,. _ _. _ _ _ _ - _..-,. _ _,-. _.
-_m.---.._--,-
c-m,.
PBAPS A.
Licensee initiated changes:
1)
Licensee initiated changes shall be reported to the Commission as part of the Modification Report recuired by 10 CFR 50.59.
The discussion of each change shall contain:
a.
A sumuary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59; b.
Suf ficient detailed information to totally support the reason for the change without benefit of additional or i
supplemental information; c.
A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.
A comparison of the predicted releases of radioactive materials, in liquid and gaseous ef fluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; e.
An estimate of the exposure to plant operating personnel as a result of the change; and f.
Documentation of the f act that the change was reviewed and found acceptable by the PORC.
- ~.
~
2)
The change shall become effective upon review and acceptance by both the PORC and OSR Committee.
.. ~
l s
l i
AmendmentNo.162'
-266-
\\
-l B.
Commission initiated changes 1)
The applicability of the change to the facility shall be determined by the PORC after consideration of the facility design.
2)
The licensee shall provide the commission with written notification of its determination of applicability including any necessary revisions to reflect facility design.
3)
The change shall be reviewed by the OSR Committee at its next regularly scheduled i
meeting.
l 4)
The change shall become effective on a date proposed by the licensee and confirmed by the commission.
6.18.3
" Major Changes" to radioactive waste systems shall include the following:
A)
Changes in process equipment, components, structures and effluent monitoring instrumentation from those described in the Final Safety Analysis Report (FSAR) and evaluated in the staff's Safety Evaluation Report (SER);
B)
Changes in the design of radwaste treatment systems that significantly alter the characteristics and/or quantities of ef fluents released f rom those previously considered in the FSAR and SER; C)
Changes in system design which invalidate the accident analysis as described in the SER; and D)
Changes in system design that result in a signi ficant increase in occupational exposure of operating personnel.
-267-Amendment No.102
PSAPS TABL2'0F CDNT2NTS Page No.
1.0 Definitiens. Abbreviations and Svmbols 1
1.1 Definitions 1.2 Abbreviations 1
1.3 Sy=bols 2
3
~
2.0 (Deleted) 3.0.
- Monitorine Recuirements 5
2.1 Thermal 3.1 5
2.2
.( Del eted) 3.2 (Deleted) 2.2.1 (Del eted) 2.2.2 (Deleted) 3.2.1 (Deleted) 2.2.3
( Deleted) 3.2.2 (Deleted) 2.2.4.(Deleted) 3.2.3 (Del eted) 2.2.4 (Deletedi 2.3
( eletedl 3.3 (Deletedl 4.0 Re: ort ' evels 5.0 Monitorine Recuirements 11.
4.1 (Deleted) 5.1 (Deleted) 4.2 (Del eted) 5.2. Deleted) 5.3 ((Deleted.)
4.3 (Deleted) l 5.0 Envirer.eental Serveillance and Scecial Study.orecrats 14 5.1
[ Deleted)
(
t 5,2 (Deleted) 5.2 (Deleted) 5;4 (Deleted) l 7.0 A6:inistrative Controls 48 l
7.1 Organization Review and Audit 7.1.1 Organization 48 i
7.1.2. Review and Audit 48 48 t
I
.i.
A. tn=ent No.102
(
LEFT BLANK INTENTIONALLY l
I.
. Amendment No 102 s
5 i
LEFT BLANK INTENTIONALLY
' Amendment No. 102
)
i 4
7.0 Adminis trative Control s 7.1 Oroanization, Review and Audi t 7.1.1 Oroanization A.
The Plan't ' Superintendent is responsible
- for the operation of the I
facility and to assure that the facili ty opera tes wi thin the limi ts set forth in the envi ronmental technical speci fications.
B.
In all matters pertain.ing to operation of the' f acility and to the environmental techni~ cal specifications, the Plant Superintendent shall report to, and consult with the Superintencent, !?u: lear Section of the Generation Division or, in his absence, the Superintendent, Fossil and Hydro Section of the Generation Division.
The management organi zation is shown in Figure 7 1-1.
7.12 Revicw and Audit Committees for review and audi t of plant operation are des-cribed in Section 6.5 of Appendix A to the Operating License.
Amendment No. 102
ATTACHMENT TO LICENSE AMENDMENT NO. 104 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert ii ii iii iii iv iv vi vi via 1
1 2
2 3
3 4
4 5
5 6
6 7
7 8
8
~
8a 58 58 59 59 l
75 75 84 84 92 92 93 93 203 203 204 204 205 205 206 206 207 207 208 208 209 209 209a 210 210 211 211 212 212 213 213 214 214 215 215 216 216 216a-1 216a-2 216a-3 216a-4 216a-5 216a-6 l
. Remove Insert 216b-1 216b-2 216c-1 216c-2 216d-1 216d-2 216d-3 216d-4 216d-5 216d-6 216e 216f-1 216f-2 216f-3
~
254 254 254a 254a 256 256 256a 257 257 257a 258 258 259 259 259a 259b 261 261 261a 265 266 267 Replace the following pages of the Appendix "B" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert i
i l
13 13 41 41 48 48
l TABLE OF C058itTS (Cent'd) -
SURVEILLANCE l
LIMITING CONDITIONS FOR'OPERATIO_N REQUIREMENT Pag.e.
l 1
3.6 PRIMARY SYSTEM BOUNDARY 4.6 143 A.-
Thermal and Pressurization Limitations A
143 B.
Coolant Chemistry B
145 C.
Coolant Leakage C
146 D.
Safety and Relief Valves D
147 E.
Jet Pumps E
148 F.
Jet Pump Flow Mismatch F
148 G.
Structural-Integrity G
149 3.7 CONTAINMENT SYSTEMS 4.7 165 l
A.
165 1
.B.
Standby Gas Treatment System B
175 C.
176 D.
Primary Containment Iselation valves D
177
.h 1 RADIOACTIVE MATERIALS 4.8 203 A.
General A
203 B.
Liquid Effluents B
204 C.
Gaseous Effluents C
208 D.
40CFR190 D
216 E.
Radiological Environmental Monitoring 3
216a-2 F.
Solid Radioactive Waste F
216a-5 G.
Mechanical Vacuum Pump G
~216e-6 3.9' AUXILIARY ELECTRICAL SYSTEMS 4.9 217 A.
Auxiliary Electrical Equipment A
217 B.
Operation with Inoperable Equipment B
219 C.
Emergency Service Water System C
221
~
3.10 CORE 4.10 225 A.
Refueling Interlocks A
225 B.
Core Monitoring B
227 C.
Spent Fuel Pool Water Level C
228 D.
Heavy Loads Over Spent Fuel D
228 E.
Spent Fuel Decay Tima E
228 3.11 ADDITIONAL SAFETY RELATED PLANT CAPABILITIES 4.11 233 A.
Main Control Room Ventilation A
233 B.
Alternate Heat Sink Faollity B
234 C.
Emergency Shutdown Control Panel C
234
/
1 11 Amendment No. N, 9,104 4
PBAPS TABLE OF CONTENTS (Cont'd)
Pace SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENT 3.12 RIVER LEVEL 4.12 237 i
A.
High River. Water Level A
237 B.
Low River Water Level B
237 C.
Level Instrumentation C
233 3.13 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCE 4.13 240a 3.14 FIRE PROTECTION 4.14 2 doc A.
Water Fire Protection System A
240c B.
CO2 Fire Protection System B
240g C.
Fire Detection C
240i D.
240j 3.15 SEISMIC MONITORING INSTRUMENTATION 4.35 240n 5.0 MAJOR DESIGN FEATURES 241 6.0 ADMINISTRATIVE CONTROLS 2d3 6.1 Responsibility 243 6.2 Organization 24 3 6.3 Facility Staf f Qualifications 246 6.4 Training 246 6.5 Review and Audit 246 6.6 Reportable Occurrence Action 253 6.7 Safety Limit violation 253 6.8 P rocedures 253 6.9 Reporting Peauirements 254 6.10 Record Retention 260 6.11 Radiation Protection Program 263 6.12 Fire Protection Inspections 261 6.13 High Radiation Area 262 6.14 Integrity of Systems Outside Containment 263 6.15 Iodine Monitoring 26:3 6.16 Environmental Qualification 264 6.17 Offsite Dose Calculation Manual 265 -
6.18 Major Changes to Radioactive Waste Treatment Systems 26 5 iii Amendment No. 39, 47, 73, 74, 104 l
Unit 3 PBAPS LIST OF FIGURES Fiqur_e Title Pg 1.1-1 APRM Flow Bias Scram Relationship To 16 Normal Operating conditions
- 4. l'.1 Instrument Test Interval Determination curves 55 4. 2'. 2 Probability of System Unavailability vs. Test Interval 98 3.4'.1 Required Volume and Concentration of 122 Standby Liquid Control System Solution
.., "a 3.4'.2
~^
Required ~ Temperature vs. Concentration.
123 for Standby Liquid Control System Solution 3.5.K.1 NCPR Operating Limit vs. Tau, LTA 142 3.5'.K 2 MCPR Operating Limit vs. Tau, PTA E P8X8R 142a Fuel 3.5'.l.A Deleted 3.5.l.B Deleted 3.5'.l.C Deleted 3.5'.l.D Deleted 3.5.1.E Kf Factor vs. Core Flow 142d 3.5~.1.F MAPLHGR vs. Planar Average Exposure,
, 142e Unit 3, 8XS PTA Fuel 3.5.1.G Deleted 3.5.1.H MAPLEGR vs. Planar Average Exposure, 142g Unit 3, P8X8R Puel (P8DRB284H) 3.5.1.I MAPLHGR vs. Planar Average Exposure, 142h Unit 3, P8X8R LTA,(P8DRB299) 3.5.1.J MAPLEGR vs. PlanaT Average Exposure, 1421 Unit 3, P8X8R Fuel (Generio 3.5.1.K MAPLHGR vs. Planar Average Exposure, 142j Unit 3, P8X8Q LTA (P8DQB326) 3.6.1 Minimum Temperature for Pressure Tests 164 such as required by Section XI 3.6.2 Minimum Temperature for Mechanical Heatuo 164a or Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for Core Operation 164b (Criticality) 3.6.4 Transition Temperature shift vs. Fluence 164c 3.8.1 Site Boundary and Effluent Release Points 216e l
6.2-1 Management Organization Chart 244 6.2-2 Organisation for conduct of Plant Operation 245 iv Amendment No. #5, #$, $2, 79, 92, 104 i
l
Y PBAPS Unit 3 LIST OF TABLES Tabl e Title Pace 4.2.B Minimum Test and Calibration Frecuency 81 for CSCS 4.2.C Minimum Test and Calibration Frecuency 83 for Control Rod Blocks Actuation 4.2.D Minimum Test and Calibration Frecuency 84 for Radiation Monitoring Systems 4.2.E Minimum Test and Calibration Frecuency 85 for Drywell Leak Detection 4.2.F Minimum Test and Calibration Frequency 86 for Surveillance Instrumentation 4.2.G Minimum Test and Calibration Frecuency 88 for Recirculation Pump Trip" 3.5.K.2 Operating Limit MCPR Values for 133d Various Core Exposures 3.5.K.3 Operating Limit MCPR Values for 133e Various Core Exposures 4.6.1 In-Service Inspection Program for Peach 150 Bottom Units 2 and 3 3.7.1 Primary Containment Isolation Valves 179 3.7.2 Testable Penetrations With Double 184 0-Ring Seals 3.7.3 Testable Penetrations With Testable 184 Bellows 3.7.4 Primary Containment Testable Isolation 185 Valves 4.8.1 Radioactive Lieuid Waste Sampling and 216b-1 Analysis 4.8.2 Radioactive Gaseous Waste Sampling and 216c-1 Analysis 4.8.3.a Radiological Environmental Monitoring 2166-1 P rogram 4.8.3.b Reporting Levels for Radioactivity 2166-5 Concentrations in Environmental Samples vi Amendment No. 104
6 A
PBAPS Unit 3 LIST OF TABLES Table Title Pace 4.8.3.c Maximum Values for Minimum Detectab.le 216d-6 Levels of Activity 3.11.D.1 Safety Related Shock Suppressors 234d 1
3.14.C.1 Fire Detectors 240k via Amendment No. 104
PBAPS 1.0 DEFINITIONS The succeeding frequently used terms are explicitly defined so that a uniform interpretation of the specifications may be achieved.
I Alteration of the Reactor Core - The act of moving any component in the region above the core support plate, below the upper grid and within the shroud.
Normal control rod movement with the control drive hydraulic system is not defined as a core alteration.
Normal movement of in-core instrumentation and the traversing in-core probe is not defined as a core alteration.
Channel - A channel is an arrangement of a sensor and associated 1
components used to evaluate plant variables and produce discrete outputs used in logic.
A channel terminates and loses its identity where individual channel outputs are combined in logic.,
Cold Conditien - Reactor coolant temperature eoual to or less than 212 F.
Cold Shutdown - The reactor is in the shutdown mode, the reactor coolant temperature equal to or less than 212 F, and the reactor vessel is vented to atmosphere.
Critical Power Ratfo (CPR) - The critical power ratio is the ratio of,that arsembly power which causes some point in the assembly to experience transition boiling to the assembly power I
at the reactor condition of interest as calculated by application of the GEXL correlation.
(13ef erence NEDO-lO958).
j Dose Ecuivalent I-131 - That concentration of I-131 ( Ci/gm) which alone would produce the same thyroid dose as the cuantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
l Amendment No.104 l l
PBAPS l.0 DEFINITIONS (Cont'd)
Encineered Safecuard - An engineered safeguard is a safety system the actions of which are essential to a safety action reouired in response to accidents.
Fracticrt of Limiting Power Density (FLPD) - The ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHGR for that bundle type.
Functicrial Tests - A functional test is the manual operation or initiation of a system, subsystem, or component to verify that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the recuired volume of water).
Gaseous Radwaste Treatment System - Any' system designed and installed to reduce radioactive gaseous affluents by collecting l
primary coolant system offgases f rom the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
Hot Shutdown - The reactor is in the shutdown mode and the, reactor coolant temperature greater than 212 F.
Hot Standby Condition - Hot Standby Condition means operation with coolant temperature greater than 212 F, system pressure less than 1055 psig, and the mode switch in the Startup/ Hot Standby position.
The main steam isolation valves may be opened to provide steam to the reactor feed pumps.
Immediate - Immediate means that the recuired acticri will be initiated as soon as practicable considering the safe operation of the unit a6d the importance of the recuired action.
i 5
i Amendment No.104 i
l l
PBAPS 1.0 DEFINITIONS (Cont'd)
Instrument or Channel Calibration - An instrument or channel calibration means the adjustment of an instrument or channel signal output so that it corresponds, within acceptable range, and accuracy, to a known value(s) of the parameter which the instrument or channel monitors.
The known value of the parameter shall be injected into the channel or instrument as close to the primary sensor as practicable.
Instrument or Channel Check - An instrument or channel check is a cualitative determination of acceptable operability by observation of instrument or channel behavior during operation.
This determination shall include, where possible, comparison of the instrument or channel with other independent instruments measuring the same variable.
Instrument or Channel Functional Test - An instrument or channel f unctional test means the injection of a simulated signal into the channel or instrument as close to the primary sensor as practicable to verify the proper instrument channel response, alarm and/or initiating action.
Limitino Conditions for operations (LCO) - The limiting conditions for operation specify the minimum acceptable levels of system performance necessary to assure safe startup and operation of the facility.
When these conditions are met, the plant can be operated safely and abnormal situations can be safely controlled.
Limitina Safety System Settina (LSSS) - The limiting safety system settings' are settings on instrumentation which initiate the automatic protective action at a level such that the safety limits will not be exceeded.
The region between the saf ety limit and these settings represents margin with normal operation lying below these sectings.
Thre margin has been established so that with proper operation of the instrumentation, the saf ety limits will never be exceede3.
Locic - A logic is an arrangement of relays, contacts and other components that produces a decision output.
l l
Amendment No.104 l l
PBAPS 1.0 DEFINITIONS (Cont'd) i (a) Initiating - A logic that receives signals from channels and produces decision outputs to the actuation logic.
(b) Actuation - A logic that receives signals (either f rom initiation logic or channels) and produces decision outputs to accomplish a protective action.
Logic System Functional Test - A logic system functional test means a test of all relays, and contacts of a logic circuit to insure all components are operable per design intent.
Where practicable, action will go to completion; i.e., pumps will be started and valves operated.
l Maximum Fraction of Limitino Power Density (MFLPD) - The Maximum Fraction of Limiting Power Density (MFLPD) is the highest value existing in the core of the Fraction of Limiting Power Density i
(FLPD).
MEMBERS OF THE PUBLIC - Members of the public shall include all persons who are not occupationally associated with the plant.
i This category does not include employees of the utility, its j
contractors, or vendors.
Also excluded from this category are i
persons who enter the site to service eauipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
Minimum Critical Power Ratio (MCPR) - The minimum in-core critical power ratio corresponding to the most limiting fuel assembly in the core.
1 I
Mode of Operation - A reactor mode switch selects the proper interlocks for the operational status of the unit.
The following are the modes and interlocks provided: Refuel Mode, Run Mode, Shutdown Mode, Startup/ Hot Standby Mode.
l 1 j
Amendment No.104
PBAPS N
1.0 DEFINITIONS (Cont ' d )
Offsite Dose Calculation Manual - Contains the current methodology and parameters used in the calculation of of fsite doses due to radioactive gaseous and liould effluents and describes the environmental radiolegical monitoring program.
OPERABLE - OPERABILITY - A system, subsystem, train, component, or device is OPERABIE or has OPERABILITY when it is capable of performing its specified function and all instrumentation, controls, normal and emergency electrical power sources, cooling or seal water supplies, lubrication systems, and other auxiliary equipment that are recuired for the system, subsystem, train, component, or device to perform its function are also capable of performing their-related support function.
Operatina - Operating means that a system or component is performing its intended functions in its required manner.
Operatina Cvele - Interval between the end of one refueling outage for a particular unit and the end of the next subsecuent refueling outage for the same unit.
Primary containment Intecrity - Primary containment integrity means tnat the crywell anc pressure suppression chamber are intact and all of the f ollowing conditions are satisfied:.
1.
All primary containment penetrations reqpired to be closed during accident conditions are either:
a)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or l
b)
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as may be provided in Specifications
- 3. 7.D. 2 and 4. 7.D. 2.
Manual valves may be opened to perform necessary operational activities.
2.
At least one door in each airlock is closed and sealed.
3.
All blind flanges and manways are closed.
l Amendment No. 104 _
(
4 r
- c. -,. -
w
-9.-.-.--.,
7 7
p 9w- - - -py
+
7 PBAPS 1.0 DEFINITIONS (Cont'd)
Protective Action - An action initiated by the protection system when a limit is reached.
A protective action can be at a channel or system-level.
Protective Function - A system protective action which results from the protective action of the channels monitoring a particular plant condition.
Purae - Puraine - 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 reauired to purify the confinement.
Rated Power - Rated power refers to operation at a reactor power of 3,293 MWt; this is also termed 100 percenc power and is the maximum power level authorized by the operating license.
Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power.
i Reactor Power Operation - Reactor power operation is any operation with the mode switch in the "Startup" or "Run" position with the reactor critical and above 1% rated power.
Reactor Vessel Pressure - Unless otherwise indicated, reactor vessel pressuree listed in the Technical Specifications are those measured by the reactor -vessel steam space detectors.
.I Refuel Mode - With the mode switch in the refuel position, the reactor is shutdown and interlocks are established so that only j
one control rod may be withdrawn.
Refueline Outace - Refueling outage is the period of time between the shutdown of the unit pr.4 or to a refueling and the startup of the unit after that refueling.
For the purpose of designatino i
frecuency of testing and surveillance, a refueling outage shall mean a regularly scheduled outage; however, where such outages occur within 8 months of the completion of the previous refueling i
1 l
Amendment No. 104 - -. -
+
j l
PBAPS 1.0 DEFINITIONS (Cont ' d )
outage, the required surveillance testing need not be performed until the next regularly scheduled outage.
Run Mode - In this mode the reactor system pressure is at or above 850 psig and the reactor protection system is energized with APRM protection (excluding the 154 high flux trip) and RBM interlocks in service.
Safety Limit - The safety limits are limits below which the reasonable maintenance of the cladding and primary systems are assured.
Exceeding such a limit requires unit shutdown and review by the Nuclear Regulatory Commission before resumption of unit operation.
Operation beyond such a limit may not in itself result in serious consequences, but it indicates an operational deficiency subject to regulatory reoiew. -
secondary containment Integrity - Secondary containment integrity means that the reactor building is intact and the following conditions are mets 1.
At least one door in each access opening is closed.
2.
The standby gas treatment is operable.
3.
All Reactor Building ventilation system automatic isolation valves are operable or deactivated in the isolation position.
i Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.
Shutdown Mode - Placing the mode switch to the shutdown position initiates a reactor scram and power to the control rod drives is removed.
After a short time period (about 10 sec), the scram signal is removed allowing a scram reset and restoring the normal valve lineup in the control rod drive hydraulic system; also, the main steam line isolation scram and main condenser low vacuum j
scram are bypassed if reactor vessel pressure is below 1055 psig.
Amendment No. 104 '
i l
t PBAPS 1.0 DEFINITIONS (Cont'd)
Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.
SITE BOUNDARY - That line beyond which the land is not owned, 3
leased or otherwise controlled by licensee.
6 Source Check - A source check shall be the qualitative assessment of channel response when the channel. sensor is exposed to a radioactive source.
Startup/ Hot Standby Mode - In this mode the reactor protection scram trips, initiated by condenser low vacuum and main steam line isolation valve closure, are bypassed when reactor pressure is less than 1055 psig, the reactor protection system is energized with IRM neutron mo' itoring system trip, the APRM 15%
n high flux trip, and control rod withdrewal interlocks in service.
This is often referred to as just Startup Mode.
This is intended to imply the Startup/ Hot Standby position of the mode switch.
Surveillance Frecuency - Periodic surveillance tests, chedks, calibrations, and examinations shall be performed within the specified surveillance intervals.
The operating cycle interval as pertaining to instrument and electrical surveillance shall not exceed 18 months.
These specified time intervals may be exceeded by 25%.
In cases where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval.
Surveillance t9sts. are not required on systems or parts of the systems that are not required to be operable or are tripped.
If tests are mirsed en parts not required to be operable or are i
tripped,.then they shall be performed prior to returning the system to an operable status.
l Transition Boiling - Transition boiling means the boiling regime i
l between nucleate and film boiling.
Transition boiling is the regime in which both nucleate and film boiling occur intermittently with neither type being completely stable,.
Trip System - A trip system means an arrangement of instrument i
channel trip signals and auxiliary eauipment required to initiate i
Amendment No. 104 i i
PBAPS 1.0 DEFINITIONS (Cont'd) action to.kccomplish a protective trip function.
A trip system may require one or more instrument channel trip: signals related to one or more plant parameters in order to initiate trip system action.
Initiation or protective action may require the tripping of a single trip system or the coincident tripping of two trip systems.
Unrestricted Area - Any area for which access control is not required for purposes of protection of individuals from exposure to radiation.
Ventilation Exhaust Treatment System - A ventilation exhaust treatment system is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents.
Ventine - The controlled process of discharging air or gas from a confinement to maintain operating conditions, such that replacement air or gas is not provided or required during venting.
Amendment No. 104
-Ba-
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS C.
Control Rod Block Actuation C.
Control Rod Block Actuation l
1.
The limiting conditims of Instrumentation shall be l
operation for the instru-functionally tested, cali-mentation that initiates brated and checked as indi-control rod blocks are given cated in Table 4.2.C.
in Table 3.2.C.
System logic shall be func-2.
The minimum number of oper-tionally tested as indica-able instrument. channels ted in Table 4.2.C.
specified in Table 3.2.C
- for the Rod Block Monitor may be reduced by one in one of the trip systems for maintenance and/or testing, provided that this condi-tion does not last longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any thirty 1
day period.
i i
Amendment No. 104 - - -. -
pyg LIMITING CONDITIONS FOR OPERATION SUFVEILLANCE REOUIRFMFFTS 3.2.D. Radiation Monitoring 4.2.D.
Radiation Monitoring Systems-Isolation and Systems-Isolati on and Initiation Functions Initiation Functions 1.
Reactor Buildina Isolation 1.
React'or Buildina Isolation i
and Standby Gas Treatment and Standby Gas Treatment System System The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali-Table 3.2.D.
brated and checked as indi-cated in Table 4.2.D.
System logic shall be fune-tionally tested as indica-ted in Table 4.2.D.
E.
Drywell Leak Detection E.
Drywell Leak Detection The limiting conditions of Instrumentation shall be operation for the instru-calibrated and checked as mentation that monitors indicated in Table 4.2.E.
~
drywell leak detection are given in Table 3.2.E.
=
i Amendment No. 104 b
TABLE 3.2.D RADIATION NONITORING SYSTEMS' TilAT INITIATE AND/OR ISOLATE SYSTEMS
~ Minicum No. of Operable No. of Instrument Inotrtanent Channels Provided Action Channel s Trip Function Trip Level Setting by Design (2) 2 Refuel Area Exhaust Monitor Upscale, <16 mr/hr 4 Inst. Channels A or B 2
Reactor Building Area Upscale, (16 mr/hr 4 Inst. Channels B -
Exhaust Monitors NOTES FOR TABLE 3.2.D
- 1. Whenever the systems are required to be operable, there shall.be two operable or tripped instrument channels per trip system. If this cannot be met, the indicated action shall be tcken.
- 2. Action A. Cease operation of the refueling equipment.
B. Isolate secondary containment. and start the standby gas treatment system.
O e
TABLE 4.2.D MINIPUM TEST & CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS N
n-Instrument Functional Ins trument h
Instrument Channels Test Calibration Check (2T a
- 1) Refuel Area Exhaust (1)
Once/3 months Once/ day g
Moni tors - Upscale a
- 2) Reactor Building Area (1)
Once/3 months Once/ day Logic System Functional Tcat (4) (6)
Frequency
- 1) Reactor Building Isolation Once/6 months i
- 2) Standby Gas Treatment Once/6 months System Actuation f
e e
(
v e
l l
~
PBAPS 3.2 BASES (Cont'd)
The APRM rod block function is flow biased and prevents a significant reduction in MCPR, especially during operation at reduced flow.
The APRM provides gross core protections i.e., limits the gross core power increase f rom withdrawal of control rods in the normal withdrawal coquence.
The trips are set so that MCPR is maintained greater than the fuel cladding integrity safety limit.
The RBM rod block function provides local protection of the core; i.e., the prevention of boiling transition in the local region of the core, for a single rod withdrawal error from a limiting control rod pattern.
The IRM rod block function provides local as well as gross core 3
i protection.
The scaling arrangement is such that trip setting is less I
than a factor of 10 above the indicated level.
1 1
I The downscale indicaticut on an APRM or IRM is an indication the instrument has failed or the instrument is not sensitive enough.
In oither case the instrument will not respond to changes in the control rod motion and thus, control rod motion is prevented.
The downscale trips are set at 2.5 indicated on scale.
I The flow comparator and scram discharge volume high level components 4
have only one logic channel and are not required for safety.
The flow comparator must be bypassed when operating with one recirculation j
water pump.
i The refueling interlocks also operate one logic channel, and are required for safety gnly when the mode switch is in the refueling i
position.
i For effective emergency core cooling for small pipe breaks, the HPCI system must function since reactor pressure does not decrease rapidly i
enough to allow either core spray or LPCI to operate in time.
The automatic pressure relief function is provided as a backup to the HPCI in the event the HPCI does not provide this function when necessary and minimize spurious operation.
The trip settings given in the cpecification are adequate to assure the above criteria are met.
The specification preserves the effectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes the risk of inadvertent operation; i.e., only one instrument channel out of acrvice.
i Amendment No. O, 79, $$, 104,
4 i
PBAPS 3.2 BASES (Cont ' d )
l Four sets of two radiation monitors are provided which initiate the Reactor ~ Building Isolation function and operation of the standby gas treatment system.
Four instrusent channels monitor the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor.
Each set of the instrument channels is arranged in a 1 out of 2 twice trip logic.
I Trip settings of (16 ar/hr for the monitors in the refueling area ventilation exhaust ducts are based upon initiating normal ventilation isolation and standbp gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by'the standby gas treatment system.
1 Flow integrators are used to record the integrated flow of liquid from i
the drywell sumps.
The alarm unit in each integrator is set to i
annunciate before the values specified in Specification 3.6.C are.
oxceeded.
An air sampling system is also provided to detect leakage j-inside the primary containment.
For each parameter monitored, as listed in Table 3.2.F, there,are two (2) channels of instrumentation.
By comparing readings between the two (2) channels, a near continuous surveillance of instrument performance is available.
Any deviation in readings will initiate an carly recalibration, thereby maintaining the quality of the instrument readings.
The recirculation pump trip has been added at the suggestion of ACRS as a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient.
The response of the plant to this postulated event fall within the envelope of study ovents given in, General Electric Company Topical Report, NEDO-10439, 1
dated March, 1971.
i i
i Amendment No, 104 !
.+
PBAPS LIMITING CDNDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS E
3.8 Radioactive Materials 4.8 Radioactive Materials Appliesbility Applicability Applies - to the r'adioactive Applies to the periodic monit-of fluents from the, plant.
oring and recording of radio-t i t " active affluents.
Ohioctive Objective To assure that radioactive To ascertain that radioactive material is not released to releases are as low as
, the environment in an uncon-reasonably achievable and trolled manner and to assure that any material released ~
~
within allowable values.
10 kapt as low as reasonably cchievable and, in any ev'nt, e
ic within the limits of 10 CFR 20.
Seeci ficati on Speci fication A.
General A.
Gene ral It is expected that releases Operating procedures shall
~
of radioactive material in be developed and used, and offluents will be kept at small eauipment which has been.
f ractions of the limits speci-installed to maintain control fled in Section 20.106 of 10 over radioactive materials CFR Part 20 and as further in gaseous and licuid effluents specified in these Technical produced during normal reactor Specifications. At the same operations, including expected time the licensee is permitted operational occurrences, shall the flexibility of operation, be maintained and used, to keep i
compatible with considerations levels'of radioactive material of health and safety,' to assure in effluents released to areas that the public is provided a at and beyond the SITE BOUNDAFY dspendable source of power as low as reasonably achievable.
even under unusual operating conditions which may tem-porarily result in releases higher than such small fractions, but still within the limits specified in Specifications 3.8.B.1 and 3.8.C.1, and in Scction 20.106 of 10 CFR Part
- 20. It is expected that in using this operational flex-ibility under unusual operating conditions the licensee will 203 Amendment No. 104 J
l
j PBAPS LIMITING CONDITIONS FOR OPERATION SUPVEILLANCE RFOUIREMENTS oxert-his best efforts to keep levels of radioactive l
natorial in effluents as l
low as reasonably achiavable.
I 3.8.B Lieuid Radwaste Effluents 4.8.B Liquid Radwaste Ef fluents 1.
The concentration of radio-la. Facility records shall be active material released to maintained of the radio-areas at and beyond the SITE active concentrations BOUNDARY (See Figure 3.8.1) and volume before dilution shall be limited to the con-of each batch of licuid centration specified in affluent released, and of 10 CFR 20 Appendix B, Table II, the average dilution flow Column 2 for radionuclides and length of time over other than noble gases and which each discharge 2xlO~' uCi/ml total activity occurred.
1 concentration for all dis-lb. Prior to release of each solved or entrained noble batch of licuid effluent, gases. With the concentration a sample shall be taken of radioactive material re-from that batch and analyzed leased to areas at and beyond for the concentration of the SITE BOUNDARY exceeding each significant gamma energy these limits, without delay peak. The release rate.
decrease the release rate shall be based on the of radioactive materials circulating water flow and/or increase the dilution rate at the time
- of flow rate to restore the discharge, concentration to within the Ic. Radioactive liouid waste limi ts.
sampling and activity analysis I
shall be performed in accordance with Table 4.8.1.
2.
The dose or dose commit-2.
Cumulative dose contri-ment to a MEMBER.0F THE butions shall be determined PUBLIC f rom r'adioactive in accordance with the materials in licuid effluent methodology and parameters releases from the two in the O f f si te Dos e reactors at the site to Calculational Manual (ODCM )
areas at and beyond the SITE at least once per month.
BOUNDARY (see Figure 3.8.1) shall be limited to:
- a. During any calendar cuarter to < 3.0 mrem to the totaf body and to
< 10.0 mrem to any organ,
- and,
- h. During any calendar year Amendment No. 104 204
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mm-,
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.4 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE PFCUIRFFFNTS to < 6.0 mrem to the total body and to
< 20.0 mrea to any organ.
When the calculated dose from the release of radioactive materials in liquid effluents exceeds any of the above limits, prepare and subtit to the Commission within 21 working days, pursuant to Specification 6.9.3, a j
Special Report which identifies the causes for exceeding the limits and corrective actions that have been taken to reduce the releases of radioactive materials in liquid effluents and proposed corrective actions to be taken to assure that subsequent releases are within the limits.
This Special Peport sha13 al so include (1) results of radio-logical analyses of the drinking water source and (2) the radiolocical impact on the potentially affected drinking water supplies with regard to 40 CFR 141, Safe, Drinking.
Water Act. Rea* ctor shut-down is not reauired.
30 During release of radioactive 3a. The licuid radwaste ef-wa stes, the following fluents radiation monitor conditions shall be met shall be calibrated
- a. The minimum dilution every 12 months with a water recuired to known radioactive source satisfy 3.8.B.1 shall positioned in a reproducible be met,
geometry with respect to the
- b. The gross n.ctivity sensor and every cuarter monitor and flow monitor by means of a source on the waste ef fluent check. Additi ona3 3 y, an line shall be operable instrument functional test except as specified in shall be performed every l
205 i
Amendment No. 7S,104 l
l
. - -.vm--
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_-r-_..-.e.,w, - - -. - - - - --r
a PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMFNTS 3.8.B.3.d and 3.8.B.3.e, month and an instrument below.
check shall be performed
- c. The af fluent control every day during release, monitor shall be set in Functional test shall accordance with the demonstrate operability methodology and parameters of the radwaste discharge in the ODCM to alarm and automatic isolation valve, automatically close the and control room an-waste discharge valve nunciation if any of the prior to exceeding the following conditions exist:
limits specified in
- 1. Instrument indicates 3.8.B.1 above.
measured levels above
- d. From and af ter the date the alarm / trip set-that the gross activity
~ point.
monitor en the waste
- 2. Instrument indicates effluent line is made
-a downscale failure.
or found to be inoperable for any reason, ef fluent 3b. The liquid effluent flow releases may continue monitor shall be cali-only if best efforts brated every 12 months.
are taken to make such Additionally, an instru-monitor operable, ment check shall be provided that prior performed every day to initiating a during release.
release :
1.
At least two in-dependent samples of the tank's contents are analyzed, and 2.
At least two technically cualified members of the Facility Staff independently verify the release rate cal-culation and discharge line yhlving.
i
- e. From and af ter the date that the flow monite on the waste effluent line is,made or found to be inoperable for any reason, effluent releases via this pathway may continue only if best I
efforts are taken to make j
such monitor operable, provided that the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump performance curves 206 l
Amendment No. M 104 l
PBAPS LIMITING CDNDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS may be used to estimate
~
fl ow,
- f. If the requirements of 3.8.B.3.a, 3.8.B.3.b, 3.8.B.3.c, 3.8.B.3.d, or 3.8.B.3.e cannot be met,
suspend release of radio-
)
active effluents via this pathway.
- g. With less than the minimum number of radioactive licuid radwaste monitors OPERABLE exert best efforts to return the instruments to OPERABLE status within 30 days and if unsuccessful explain in the next Semi-annual Radioactive Eff3 uent Release Report why the in-operability was not cor-rected in a timely manner.
4.
All liauids shall be 4a. Doses due to licuid processed throuch either effluent releases to the waste collector filter areas at and beyond the
.and demineralizer, the SITE BOUNDARY shall be fJ oor drain filter, or the projected once per month fuel pool filter deminer-in accordance with the alizer as appropriate prior methodology and parameters to their discharge when in the ODCM.
the projected dose due to the licuid effluent 4b. The waste collector releases to unrestricted filter and demineralizer areas, when averaged over and the floor drain filter any month, expeeds 0.12 shall be demonstrated mrem to the total body operable once per quarter, or O.4 mrem to any organ unless utilized to process from the two reactors at liquid waste during the the site. With liquid previous 13 weeks, by waste being discharged analyzing the licuid without treatment as processed through the recuired above, prepare appropriate eeuipment to and submit to the Com-determine that it meets mission within 21 working the reauirements of days pursuant to Specifi-Specification 3.8.B.l.
cation 6. 9.3, a Special The fuel pool filter Peport which includes the domineralizer is exempt i
followine information from this reouirement
- a. Explanation of why since it is an a3 ternate licuid radwaste was treatment system which is 207 i
Miendment No.104 e
.p
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g-, -..-
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i l
r PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RFOUIREMENTS l
l being discharged not routinely used to l
without treatment, process licuids for identification of discharge.
any inoperable equipment or sub-systems and the reason for the inoperability,
- b. Action taken to restore the in-operable equipment to operable status,
- c. Action taken to prevent a recurrence.
Reactor shutdown is not required.
3.8.C Gaseous Effluents 4.8.C Gaseous Ef fluents 1.
The dose rate in areas at la. The dose rate due to. noble and beyond the SITE gases in gaseous effluents BOUNDARY (see Figure shall be determined to be 3.8.1) due to radioactive within the limits in materials in gaseous accordance with the methods effluerets released from the and procedures of the
. tan) reactors at the site shall ODCM.
be limit:ed to the following:
- a. The 6,-se rate for Ib. The dose rate due to noble gases shall be iodi ne-131, iodine-133, limited to < 500 tritium, and all radier mrem /yr to the total nuclides in particulate body and < 3000 mrem /yr form with half lives to the skin.
greater than 8 days in gaseous effluents shall
- b. The dose rate for be determined to be iodine-131; iodine-133, within the limits in tritium, and for all accordance with the radionuclides in methods and procedures particulate form with of the ODCM by ottaining half lives greater representative samples than 8 day /yr to and performing analyses s shall be
<1500 mrem in accordance with the any organ.
sampling and analysis program specified in When the dose rates exceed Table 4.8.2.
the above limits, without delay, decrease the release rate to comply with the limit.
208 kiendment No.104 l
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIPIMENTS 2.
The air dose in areas at 2.
Cumulative dose contributions and beyond the SITE for noble gases shall be
~
BOUNDARY (see Figure determined in accordance 3.8.1) due to noble gases with the methodology and in gaseous effluents released parameters in the ODCM from the two reactors at the at least once per month, site shall be limited to the followings
- a. During any calendar quarter for gamma radiation
< 10 mrad.
During any Ealendar quarter for beta radiation: < 20 mrad.
- b. During any calendar year for gamma radiation
< 20 mrad.
~
During any calendar year for beta radiation
< 40 mrad.
When the calculated air dose from radioactive noble gases in gaseous ef fluents exceeds any of the above limits, prepare and submit to the Com-mission within 21 working days, pursuant to Speci-fication 6.9.3, a Special Report which identifies the causes for exceeding the limits and defines the correctiv,e actions, that have been taken to reduce the releases and proposed corrective actions to be taken to assure that sub-sequent releases will be within the above limits.
Reactor shutdown is not recuired.
3.
The dose to a MEMBER OF 3.
Cumulative dose contributions THE PUBLIC f rom iodine-131, for iodine-131, i od ine-133, iodi ne-133, tritium and tri ti um, and radionuclides from all radionuclides in particulate form with half in particulate form with lives greater than 8 days 209 Amendment SE,104
1 PBAPS LIMITING CONDITIONS FOR OP5' RATION SURVFILLANCE RFOUIREMEWF half-lives greater than shall be determined in 8 days in gaseous effluents accordance with the released from the two methodology and parameters reactors at the site to in the ODCM at least once areas at and beyond the per month.
SITE BOUNDARY (see Figure 3.8.1) shall b'e limited to the followings
- a. During any calendar quarter j,15 area.
- b. During any calen6ar year I,30 mrem.
When the calculated dose from 1
the release of iodine-131, iodine-133, triti um a'nd radionuclides in particulate form, with half-lives greater than R days in gaseous effluents exceeds any of the above limits, prepare and submit to the Commission within 21 working days, pursuant to Specification 6.9.3, a Special Report which identifies the causes for exceeding the limits and defines the corrective actions that have been taken and proposed corrective actions to assure that cub-sequent releases will be within the above limits.
Reactor shutdown,is not recui red.
3 i
4.
During release of gaseous 4a. The reactor building wastes the following con-exhaust vent and main ditions shall be met to stack noble cas radiation avoid exceeding the monitors shall be cali-limits specified in brated every 12 months with 3.8.C.12 a known radioactive source
- a. The main off gas stack positioned in a reproducible minimum dilution flow of aeometry with respect to 10,000 cfm shall be the sensor, and every maintained.
quarter by means of a
- b. One reactor building functional test. The exhaust vent monitor channel functi onal test 210 Amenchent No.104
_. ~ - _ _. _ _ _., _. _ _,. _
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMEhTS and one main stack noble gas monitor shall also demonstrate that control room alarm an-shall be operable and set i
to alarm in accordance nunciation occurs if any of with the methodology the following conditions exist:
1.
Instrument indicates and parameters in the measured levels
- ODCM. From and af her the above the alarm 4
date that both reactor setpoint.
building exhaust vent 2.
Instrument indicates monitors or both main a downscale failure.
stack noble gas monitors Additionally, an instrument are made or found to be check shall be performed inoperable for any reason, every day, ef fluent releases via their respective pathway 4b. The reactor building exhaust vent and the may continue provided at main stack flow rate 4
least two independent monitors shall be grab samples are taken calibrated every 12 at least once per 8 hrs.
and these samples are months. Additionally, an i
instrument check shall analyzed for gross activity within 24 be performed every day.
hours, and at least two 4c. The reactor building exhaust vent and the main technically qualified stack fodine and particu1&te members of the facility sampler flow rate monitors staff independently verify the release shall be calibrated,every rate calculations, 12 months. Additionally, an instrument check shall
- c. One reactor building be performed every day.
exhaust vent iodine filter and one main stack iodine filter and one reactor build-ing exhaust vent particulate filter and one main stack particulate filter with their respective flow rate monitors shall be.
}
operable. From and af ter the date that all iodine i
filters or all particulate filters for either the 3
reactor building exhaust i
vent monitor or the main.
stack monitor are made or found to be inoperable for any reason, effluent releases via their respective pathway may 211 Miendment No.104 t
~
~~
j l
PBAPS LIMITING 00NDITIONS FCR OPERATION SURVEILLANCE RFOUIREMEMS continue provided samples are continuously collected with auxiliary sampling equipment for periods on the order of 7 days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period.
- d. One reactor building exhaust vent flow rate monitor and one main stack flow rate monitor shall be operable and set to alarm in accordance with the methodology and parameters in the ODCM.
From and af ter the date that both reactor building exhaust vent flow rate monitors or both main stack flow rate monitors are made or found to be inoperabl e for any reason, effluent releases via their respective pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,
- e. With less than the minimum number of radioactive gas-eous effluent monitoring instrumen,tation channels OPERABIZ exert best efforts to return the instruments to OPERABLE status within 30 days and if unsuccessful explain in the next Semi-annual Radioactive Ef fluent Release Report why the in-operability was not cor-rectedin a timely manner.
5.
Gaseous effluents shall Sa. Doses due to gaseous be processed through effluent releases to the appropriate gaseous areas at and beyond waste treatment system the SITE BOUNDAPY as described below shall be projected prior to discharoe at least once per 212 Miendment No.104
~
k PBAPS
^
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTF
~
\\
- a. Gases from the Steam month in accordance Jet Air Ejector Dis-with the methodology charge shall be and parameters in processed throuch the the ODCM.
recombiner, holdup pipe, off-gas filter, and 5b. The appropriate gaseous off-gas stack.
radioactive waste system equipment as described
- b. Gases from the Mechanical in Specification 3.9.C.5 Vacuum Pump and Gland Steam shall be demonstrated Exhauster discharge operable every quarter, shall be processed unless utilized to through the off-gas process gaseous waste j
stack.
during the previous 13 weeks, by analyzing l
- c. Reactor, turbine, the gaseous waste radwaste, and recombiner processed through the building atmospheres appropriate eouipment l
shall be processed to determine that it l
through permanently meets the requirements of or temporarily installed Specification 3.8.C.1.
equipment in the appropriate j
huilding ventilation system Sc. An air sample sha3 3 be i
and the Reactor Building obtained and analyzed Ventilation Exhaust Stack, from all building areas 4'
with the exception of the with an unmonitored following unmonitored exhaust once per month.
exhausts:
1.
Recirculation M-G i
Set and Reactor Building Coolina Water equipment" ro oms..
2.
Control room utility and toilet rooms.
3.
Cable spread room.
4.
Emergency switchgear rooms.
5.
125/250 VDC Battery rooms and the 250 VDC Battery rooms.
6.
Administration Building maintenance decontam-ination area.
l With gaseous waste being 4
discharged without treatment I
as required above, prepare and submit to the Commission i
within 21 working days i
213 Amendment No.104 1
~
l PBAPS j
-=j LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l
pursuant.to Specification 6.9.3 a Special Report which includes the following information:
- a. Explanation of why gaseous radwaste was being dis-charged without treatment, identification of any J
inoperable equipment or subsystems and the reason for its inoperability.
- b. Action taken to restore the inoperable equipment to operable status,
- c. Summary description of action taken to prevent a recurrence.
Reactor shutdown is not required.
6.
The concentration of hydrogen 6a. An instrument check of the downstream of the recombiners operation of the hydrogen shall be limited to less monitors shall be performed than or equal to 24 by once per day.
- volume,
- a. With the concentration 6b. The hydrogen monitors and of hydrogen downstream associated alarms downstream of the recombiner greater of the recombiner shall than 24 but less than or be calibrated once per equal to 44 by volume, month.
i restore the concentration 1
i to within the limit within 6c. Calibration shall include 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
the use of standard gas
- b. With the concentration of samples containing a hydrogen downstream cf the nominal:
recombiner greater than 44 1.
It hydrogen, balance by volume, an orderly nitrogen by volume, reduction of power shall be 2.
44 hydrogen, balance initiated within one hour nitrogen by volume.
to bring the hydrogen down-stream of the recombiner to less than or equal to 24 by volume.
- c. Except as specified in l
3.8.C.6.d, two hydrogen monitors downstream of the l
recombiners shall be operable during power operation.
[
214 6-l Amendment No. 104 l
l
)
=_
PBAPS l
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- d. With the number of 4-hy'drogen monitors operable one less than required, i
operation may continue for up to 14 days provided grab samples are taken and analyzed daily. With both hydrogen monitors inoperable operation may continue for up to 14 days provided grab samples are taken and i
analyzed every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during power operation.
7a. The radioactivity release 7a. The radioactivity release rate of noble gases from the rate of noble gases from Steam Jet Air Ejector dis-the Steam Jet Air Ejector charge as determined by discharge shall be determined quantitative analysis of to be within limits at the identifiable gamma emitters following frequencies by shall not exceed 320,000 performing an isotopic uCi/see af ter 30 minutes analysis of a representa-decay. With the radio-tive sample of gases taken activity release rate of at the discharge of the noble gases from Steam Steam Jet Air Ejector.
Jet Air Ejector discharge exceeding 320,000 uCi/sec 1.
At least once pqr month af ter 30 minutes decay unless the unit has restore the radioactivity been out of service for release rate to within the entire month.
Its limit within 72 hrs.
2.
Within 4 hrs. following or be in hot standby an increase, if the 1
within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
off-gas monitors indicate an increase of I
greater than 50% in the steady state fission gas release after factoring i
out' increases due to power changes.
3 I
l-7b. One Steam Jet Air Ejector 7b. The Steam Jet Air Ejector i
radiation monitor shall radiation monitors shall be i
be operable during opera-calibrated every quarter tien of a main condenser and an instrument check 1
Steam Jet Air Ejector, shall be performed once d
Upon loss of both Steam per day. Additionally a i
Jet Air Ejector radiation functional test will be monitors, releases may performed every month. The continue via this pathway channel functional test for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided shall also demonstrate that i
215 I
Amendment No.104 i
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS temporary monitors are control room alarm an-used. Otherwise, be in at nunciation occurs if any of least HOT STANDBY within the following conditions 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
exist:
1.
Instrument indicates measured levels above the. alarm setpoint.
2.
Instrument indicates a downscale failure.
Sa. Purging of the primary containment shall be through the Standby Gas Treatment System whenever primary containment integrity is required as specified in 3.7.A.2.
4 I
- b. Primary containment purging I
via the Reactor Building i
Ventilation Exhaust System i
may be performed whenever primary containment integrity is not required as specified in 3.7.A.2.
f 3.8.D 40 CFR 190 4.8.D 40 CFR 190
+
1.
The dose or dose commit-1.
Cumulative dose contribu-I ment to a MEMBER OF THE tions f rom liquid and gaseous PUBLIC f rom all uranium ef fluents shall be determined fuel cycle sources within in accordance with the 8 kilometers is limited methodology and parameters to < 25 arem to the total in the CDCM.
4 i
body or any organ (except 2.
Cumulative dose contribu-the thyroid which* is limited tions from direct radiation to <75 area) over the from the reactor units calendar year. With the and from radwaste storage i
calculated dose from the shall be determined in release of radioactive accordance with the method-materials in liquid or ology and parameters in the gaseous effluents, exceeding ODCM.
i twice the limits of speci-fi cati on s 3. 8.B. 2, 3.8.C.2, I
i or 3.8.C.3 calculations shall be made to determine whether the limits have been exceeded.
2.
The calculations should be 216 Amenchent No.104
-- -.- 0
l i
PBAPS I
LIMITING CDNDITIONS FOR OPERATION SURVEILLANCE RECUIREMENTS l
. \\
made, including direct i
radiation contributions from the reactor units and from outside storage tanks to determine whether the limits have been exceeded. If such is the case, prepara and submit to the Commission, within 21 working days, pursuant to Specification 6.9.3, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent i
recurrence of exceeding the above limits and schedule for achieving conformance with the above limits.
1 This Special Report shall include an analysis that estimates the radiation exposure to a MEMBER OF THE PUBLIC, including all effluent pathways and direct radiation, including i
,the releases covered by this report, for the l
calendar year. It shall i
also describe levels of radiation and concen-
)
trations of radioactive l
material involved and the cause of the exposure levels or concentrations.
If the estimated dose i
exceeds the above limits and if the release condition resulting in violation of 40 CFR 190 i
has not already been corrected, the Special l
Report shall include a request for a variance in accordance with 40 CFR 190. Submittal of l
the report is con-i sidered a timely request and a variance is granted unt.11 staff action on the request is complete.
l 1
Amendment No.104
-216a-I-
PBAPO LIMITING CDNDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.E Radioloolcal Environmental 4.8.E Radiolocical Environmental Monitoring Monitoring 1.
All deviations from the 1.
The radiological environmental sampling schedule for the monitoring samples shall be radiological environmental collected at the locations monitoring program, as and analyzed as specified required by 4. 8.E.1, shall in Table 4.8.3.a and the i
be documented in the annual ODCM. Deviations are permitted re port.
from the required sampling
- a. When the radiological schedule if specimens are environmental monitoring unobtainable due to hazardous program is not conducted conditions, seasonal unavaila-as des'cribed in the ODCM, bility, malfunction of auto-prepare and submit to matic sampling coulpment or the Commission, in the other legitimate reasons. If Annual Radiological equipment malf unction occurs,
Environmental Operating an ef fort shall be made Reports, a description to complete corrective of the reasons for not action prior to the end
^
conducting the program of the next sampling period.
as required and the plans for preventing a.
The concentration of radio-a recurrence.
activity as a result of
~
- b. When the level of plant ef fluents in an.
radioactivity as the environmental sampling result of plant effluents medium shall be evaluated in an environmental on a cuarterly basis sampling mediun at against the ecuation:
one or more of the locations specified concent rati on (1) +
in the ODCM exceeds reporting level (1) the reporting levels of Table 4.8.3.b when concentration (7) +. 1 1.0 averaged over any reporting level (2) calendar quarter, prepare add submit All radionuclides used to the Commission by in this evaluation shall the closing of the be averaged on a month following the calendar quarterly basis, and of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the reporting level of Table 4.8.3.b to be exceeded. The Special Report shall also define the corrective Amendment No. 104
-216a l i
PBAPS LIMITING CDNDITIONS F_0R OPERATION SURVEILLANCE REQUIREMEh"TS actions to be taken to reduce radioactive,
affluents so that the potential annual dose to a MEMBER OF THE.PUBLIC is less than the calendar year reporting level of Table 4.8.3.b. When more than one of the radio.-
nuclides in Table 4.8.3.b sampling medium, this report shall be submitted ift concentration (1)
+
reporting level (1)
_concentraticn (2) +. 11.0 reporting level- ( 2)
When radionuclides other
~
than those in Table 4.8.3.b are detected and are the' result of plant affluents, this. report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or I
greater than the calendar year limits of Specifica-tions. The repcrt is not required if the measured level of radioactivity was not the result of plant ef fluentst however, in such an event, the condition shall be reported a*nd described in the Annual Radiologi.:a1 Environmental Operating Report.
- c. When milk samples become I
permanently unavailable from any of the sample locations listed in the CDCM, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 21 working days. Specific locations from which samples are Amendment No. 104
-216a -
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMEhiS unavailable may then be
~
deleted from the monitoring program. Identify the cause of the unavailability of samples and identify the new locations for ob-taining replacement samples in the next Radioactive Dose
+
Assessment Report and include in the report revised figures and tables for the ODCM reflecting the new locations.
2.
A land use census shall be 2a. The land use census shall conducted and shall identify b, conducted every the location of the nearest 12 months by a door-milk animal in each of the to-door survey by 16 meteorological sectors consulting local within a distance of five agriculture authorities miles.
or by some other appropriate means.
- a. When a land use census identifies a new loca-tien which yields a calculated dose or dose commitment greater than the values currently being calculated in Speci fication 3.8.c.3, identify the new loca-i tion in the next Radioactivy Dose Assessment Report.
- b. When a land use census identifies a location which yields a calculated dose or dose commitment (via the same exposure l
pathway) at least 20%
greater than a location from which samples are currently being obtained j
in accordance with Specification 3.8.E.1, add the new location to the radiological environmental monitoring program within 21 work-ing days. The indicator sampling location having
-216a Amendment No.104
-- -~
- .S LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted i
from this acnitoring program after October 31 of the year in which this land use census was conducted'.
Identify the new location in the next Radio-active Dose Assessment Report and include in the report revised figures and tables for the ODCM reflecting the new locaticms.
3.
Analyses shall be performed 3a. K summary of the results on radioactive materials obtained as part of the supplied as part of the EPA Interlaboratory Comparison Environmental Radioactivity Program shall be included Intercomparison Studies Program, in the Annual Radiological or another Interlaboratory Environmental Operating Comparison Program that has Report pursuant to been approved by the Commission.
Specification 6.9.3.
- a. With analyses not being i
performed as required above report the corrective l
actions taken to prevent i
a recurrence in the Annual Radiological Environmental Operating Repo rt.
3.8.F Solid Radi'oactive Waste 4'8.F Solid Radioactive Waste 1.
The solid radwaste system 1.
.The PCP shall be used to i
shall be used in accordance ensure meeting the burial with a Process Control ground and shipping re-Program (PCP) to process cuirements prior-to shipment wet radioactive wastes to of radioactive wastes from meet shipping and burial the site.
ground reouirements.
- a. With the provisiens of the Process Control Program not satisfied, suspend shipments of defectively packaged solid radio.-
active waste from the i
site. Reactor shutdown is not required.
Amendment No. 104
-216a -
a-I LIMITING CONDITIONS FOR OPERATION SURVIII1ANCE REQUIREMENTS 3.8.G Mechanical vacuum Pump 4.8.0 Mechanical Vacuum Pump l
1.
The mechanical vacuum pump At least once during each shall be capable of being operating cycle verify isolated and secured on a automatic securing and signal of high radio-isolation of the mechanical activity in the steam vacuum pump.
lines whenever the main steam isolation valves are open.
.g 2,
If the limits of 3.8.G.1 -
.s.m,g &.;.rg.-.:a..n.,5;. y..
,5i5.a.r.41 are not met the.veo.uun pump,
. c. e... -.
% t M W #,~; 9 7 - *-
. wr% $7:s;..TSEiPlt fjks4 l
' * ^ ~
= "**M't shall be isolated.M. " * ' ---
. t ; :..
t.
.0-
-^ M '. r -
S.sk$$;if &V.~% i
..... ' ' J r.'.
h..L.c
'Q.'s".'.~',.'.+......
lEn d
... ?. $. *- *
~ 'w%4. *.Q T '. i'.W.tq.n e,.h C:- L* :el'
^
- s4 t-
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g,- m 1
..,. - w
- a...
s
. > tr.m..+. 4. <.._,r._w.
...<q n.,.;i.
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Amendment No.104 216a-6
- e t.. -.... - +.
. r ;<.o;',;,;x. ;y::g.:'
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PBAPS TABLE 4.8.1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS Sample Lower Limit of Detection Sample Precuency Sample Analysis (LLD)(1)(4)(5)
Sample Type
-7 Waste Tank to Each Batch (2)
Quantitative 5 x 10 uCi/ml be released Analysis of Identifiable Gamma Emitters
-6 I-131 1 x 10 uCi/ml
-6 P roportional Monthly (3)
Fe-55 1 x 10 uCi/mi composite of
-5 Batches Tritium 1 x 10 uCi/ml-
-7 Gross Alpha 1 x 10 uCi/ml
-8 Proportional Monthly (3)
Sr-89 5 x 10 uCi/ml Composite of
-8 Batches Sr-90 5 x 10 uci/ml
-5 one Batch Monthly dissolved noble 1 x 10 uCi/ml gases Notes 1.
The Sample Lower Limit of Detection is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
The values for the lower limit of detection are based on a 95% confidence level.
1
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Amendment No,104 216b-1 l
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PBAPS 2.
A batch release is the discharge of liquid wastes of a discrete vol ume.
Prior to sampling for analysis, each batch shall be isolated and thoroughly mixed to assure representative sampling.
3.
A composite sample is one in which the quantity of the sample is proportional to the quantity of liquid waste discharged and in which the method of sampling results in a sample representative of the liquids released.
4.
The principal gamma emitters for which the minimum detectable level specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-68, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, toge'ther with the above nuclides, shall also be identified and reported.
Nuclides which are below the sample detectable licit for the analyses should not be reported as being present at tha sample detectable limit level.
When unusual circumstances result in sample detectable limits higher than required, the reasono shall be documented in the Semi-Annual E f fluent Report.
The values listed are believed to be attainable.
5.
Certain mixtures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher concentrations.
Under these circumstances use of known ratios of radionuclides will be appropriate to calculate the levels of such radionuclides.
3 l
216b 2 l
Amendment No. 104 l
4 e.,
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e PBAPS TABLE 4.8.2 RADIOACTIVE GAFFOUS GSTE SAFPLIFG AFD At% LYSIS FF0F FAIN OFF-GAS STACK AFD RFACTOR BUII DIPG VEM EXFAL'FT STACK Sample Lower Limit of Sample Type Sample Frecuency Sample Analysis Detecti on (LLD ) ( 3 )'(4 )
-4 Grab Sample Monthly (2)
Quantitative 1 x 10 uCi/cc(3)
Analysis of Identifiabl e Gamma Emitters
-6 Grab Sampl e Quarterl y
- Tritium, 1 x 10 uCi/cc
-12 Charcoal Peekly(3) 7-131 1 x 10 uCi/cc(?)
Filters
~
-10 Pa rti cula t e reekly(3)
Cuantitative 1 x 10 uCi/ce(?)
Filters Analyris cf IdentifiabJe Gamma Fmitterr
-12 I-131 1 x 10 uCi/ce(?)
-31 Parti culate Month 3y Gross Alpha 1 x 10 uCi/cc Filters (composite of weekly filters )
-13 Monthly Sr-P9 1 x 10 uCi/cc Particulate Fil ters
-11 (ccmposite of Sr-90 1 x 10 uCi/cc weekly filters)
Noble Gas Continuousl y Noble Gas
-?
Ponitor Grostj6 or}^
1 x 10 uCi/cc (Main Stack)
Noble cas Ccntinuously Foble Cas
-f Poni tor Grossjg or)4 1 x 10 uCi/cc (roof Vents)
Amendment No.104 216c-1
+,-
PBAPS Notes 1.
The Sample Lower Limit of Detection is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
The values for the lower limit of detection are based on a 954 confidence level.
2.
Sampling and analysis shall be performed following shutdown, startup or a thermal power change exceeding 15 percent of rated thermal power within one hour from a steady state condition unless (1) analysis shows that ' he dose equivalent I-131 concentration in t
the primary coolant has not increased more than a factor of 3, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a fact,or of 3.
i L
'j 3.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 3 days l
following each shutdown, startup or thermal power change exceeding l
15 percent of rated thermal power in one hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD may be ' increased by a factor of 10.
This recuirement does not apply if (1) analysis has shown that the dose equivalent I-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
4.
Certain mixt,ures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher i
concentrations.
Under these circumstances use of known ratios of radionuclides will be appropriate to calculate the levels of such radionuelides.
Nuclides which are below the sample detectable limit for the analyses should not be reported as being present at the sample detectable limit level.
Amendment No. 104 216c-2 l
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"rAr1T. 4.8.3.m PNilOt tY'.ICAI.13N 3 lO!183trAI I HI'lORItG l*lOTVM Hunter of Samples Extosure Pattuay ard Samplirvj ard Type ard Frequeswy
__ and/or S.vaple Sample tocation(a)
Collectire Freranency(b,C) of Analvsla e
- 1. DIRECf RADIATIGO At least 40 routire monitorir>]
At least monthly Camma dose at least stations either with two or more
- monthly, dosimeters or with one instrument or for measuring ard recording dme or rate contionnaly to te placed as At least quarterly follon Il an inner rirza of'sta-Cansar. dose at least tions in the general area of time 4sarterly.
SMt: BGMAlff ard an outer rig in the 3 to 6 mile range from tie site. A statica is in esti sector
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of each ring except as dictated by local goojragkry. Ttwe balance of Ue staticms are in special interest creas such as squilatirn centers, reatly residences, sclools ard in areas to serve as control staticns.
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- 2. AIRealese to l
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Itallolo1Ine t.
Sa ples from 5 locations:
Continuous sampler Itadioicdine cannisters 3
Particulates operation with sample Y ML anafysis weekly ~
- s
- a. 3 sanples from close to the collection at.least l
SrtE IKuaWN locations (in weekly or re<pired
- a:
different sectors) of the by dust loading, Particulate Sampler:(f) highest calculated annual whichever is more Cross tota' radio-O average groundlevel DA).
frecpent.
activity analysis l
g follo<ing filter
- b. I sample from tie vicinity clange: Canaa isotopic ia of a community havir>J Lie analysis of congnette highest calculated annual (ty location) (parterly, average grourdlevel DA).
- c. I sample from a control location unlikely to te affected tsf tie plant.
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an4/or samm>1e sample incation(a) collection Frecanency(bd of Analysis
- 3. temmenseae b
- a. Surface
- a. I sample upstream composite sample r* luotopicid) analysis
- b. I sample dunstream over 1 month monthly. cusposite for
- per104, trititan analysis at 1 east spaarterly, b
- b. Drinking a.1 sample of each of 1 to 3*
ccamposite sample m q = lte for gross of the rearest water supplies over monthly teta and gammald) that could be affected by its m - wite isotopic analyses disd.arge.
period.
monthly. twgvwite for trititan analysis at
- b. I sample from a control least osatterly.
location
- c. sediment from I sample freie dtunstream area Se.al-annually Gamma irgicid)
Shoreline with existing or potential analysis semi-
'd recreational value.
annually.
m"
- 4. INrastions
- a. Milk
- a. Samples from milking animals semi-monthly edian Canna isotopic (d) analysis q r*
In 3 locations within 3 elles animals are on or 1N,IN Ce by j :z distance having the highest pasture, monthly chemical separation io ese potential, at other times, quarterly.'l-131 analysis of each sample.
- b. I sample frue milking animals 4
]E at a control location (unlikely to be affected by the plant).
- b. Fish
- a. I sample of each commercially Sample in season, or Casna isotopicid) analysis and secreationally important seat-a...uolly if Lley on edible pxtions.
species in vicinity of dis-are s t seamt charge goint when available, t
- b. I sample of same species in areas not influenced by plant j
discharge s4cn available.
1
-216d.
9 I
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TNttE 4.rd.l.a pmt irwacd1 5tADIOffE13 CAL E3Nisors3rrM. FrNI10RIIG PitTAMS p=ler of Samples 5 - we Pattmaar and S.sapliruj and Type arul Fregsercy F
arut or S. ample Sample treation(a)
Co11ecticm3 Fretaaency(b,c) of Analysis
- c. Fbod Pioacts
- a. Sqles of 3 different kir:1s Ikuthly wisen t'-
isotopleid) and of broad leaf vegetatlas <jrcnas available if milk I-131 analysis.
nearest of fsite garden of s.amellrq is highest aromaal avermy: ground-rot performed.
level DA) if milk sarpling is not performed.
- b. I sample of each of the signitar Stathly when Gunma isotopic (d) and bror_3 leaf vegetation quaan available if allk I-131 analysis.
15-30 km distant in tie least sampitrq is prevalent winul direction if rot performed, milk samplisug la set performed.
W___
al Fixe 5 sa ple locations are stasi in the Offsite Dose calculation Manual, Table VII.A.1 and Figur;-s VII.A.1, VII.A.2, and Vi!.A.3.
At times it snay not te possible or pracCc5Ede to obtain y
samples of tie ets51a of dolce at the sost desired location or time. In these instances e
suitable alternate mo18a and lacations may te closen for the partionlar pathay in gaestion.
Such necessary deviatlans are reported in the Annual Dwitonnental Radiolojical Operating Report.
s et t4 camposite samples shall tus m11ected 1sy mllectirug an alicpot at intervals not exceeding two 2
.o hours.
c3 Sample a211ecticsi fre pencies are defined as follows:
c 13teklyt 7 caleniw days + tw2 days Bi-wekly:
14 calerdar days + three &ys stmthl):
a catermiar month I eight days Oaart ecly:
a tlwee acadh calendar perlos
+ ten &ys Sami-annually: a six smth caterdar perlod +
twenty days
-216d.
9
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snaic 4.e.1 r<=*i_M w.sco siswneosee.zeraL nsationsesG renes _ se 4 Gamma IsaAopic analysts means the identification and maantificatlon of gasme-emdttLeig
-3 rhltdes that, soy be attrit-*me to time effluents tsam time facility.
1 C) radt gamesgesor is cruisidered one tiermontaminescent stasimeter.
t
~ i f) If the gscas heta activity in alt attritmataNe to plant operatica is esseater than ten times time yearly mean of cxmitrol samples, gamma lootopic analysis sinall be perfosand en time ladivleast samples.
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e Amendment tb.104
-216d. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
.a TABLE 4.8.3.c MAXIMUM VALUES FOP. MINIMUM DETECTABLE LEVELS OF ACTIVITY (MDL) a I
r Food Airborne Fish Products Sediment l
Water Particulate (PCi/kg,
Milk (PCi/kg, (pCi/kg,
{
. Analysis (pci/1)
(pci/m3) wet)
(oCi/1) wet) dry) gross 2.5
.006 beta 3H 1200 54Mn 9
80 1
59Fe 18 160 l
58,60Co 9
80 652n 18 160 952r-Nb 9
l 131I
.04 0.6 36 134,137Cs 9,11
.04 90 10 40 100 140Ba-La 9
9 TABLE NOTATION a - Analyses shall be performed in such a manner that the stated MDLs
(
will be* achieved under routine conditions at a 954 confidence level.
Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides or other uncontrollable circumstances make these MDLs unachievable.
f f
Amendment No. 104
-215d-6 e
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ET.LUENT RELEASE POINTS Amendment No.104
"1 PBAPS.
- 3. 8. A & 4. 8. A BASES General It is expected that releases of radioactive material in effluents will be kept at small fractions of the limits specified in Section 20.106 of 10 GR, Part 20.
At the same time, the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is previded a dependable source of power even under unusual operating conditicms which may temporarily result in releases higher than such small fractions, but still within the limits specified in Sectics 20.106 of 10 GR, Part 20.
It is expected that in using this operational flexibility under unusual operating conditions the licensee will exert his best efforts to keep levels of' radioactive material in effluents as low as i
practicable.
1 3.8.B & 4.8.B BASES Concentration This specificaticm is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to areas at and beyond the SITE BOUNDARY will be within the concentration levels specified in 10 GR, Part 20, Appendix B, Table II, Column 2.
This instantaneous limitation provides additional assurance that the levels of radioactive materials in bodies of water in areas at or beyond the SITE BOUNDARY will result in exposures within (1) the Section II.A design objectives of Appendix I,.10 CFR, PartSO, to a MEMBER OF THE PUBLIC and (2) the limits of 10 GR, Part 20.106(e) to the population.
The eencentraticn limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the International Commission on Radiological Protecticn (ICRP) Publication 2.
Dose This specificaticm is provided to implement the recuirements of Sections II.A, III.A and IV.A of Appendix I, 10 GR Part 50.
The Limiting Condition for Operation implements the guidance set forth in Section -II.A of Appendix I and provides the recuired operating flexibility to implesent the guides set forth in Section IV.A of Appendix I to assure that the releases of
~1" Amendment No.104
=_.
--"--~ ~~ - - - -
-..c...__..
PSAPS radioactive material in liauid ef fluents will be kept "as low as reasonably achievable".
The dose calculations in the ODCM implement the requirements in Secticm III.A of Appendix I that conformance with the guides of Appendix I be shown by calculaticmal procedures based en models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is'unlikely to be substantially underestimated.
The equations described in the Off site Dose Calculation Manual for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113,
" Estimating Aquatic Dispersics of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977.
This specificatics applies to the release of liquid ef fluents f rom the site.
Instrumentaticm The radioactive licuid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive-materials in liould ef fluents during actual or potential release of liquid ef fluents.
The operability and use of this instrumentation is consistent with the reouirements of General Design criteria 60, 63 and 64 of Appendix A to 10 CFR, Part 50.
System operation The operability of the liquid radwaste treatment system ensures that this systrem Will be available for use whenever liquid effluents recuire treatment prior to release to the environment, The requirement that the appropriate portions of this system be l
used when specified provides assurance that the releases to radioactive materials in liquid affluents will be kept "as low as reasonably achievable".
This specification implements the requirements of 10 CFR, Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR, Part 50 and design objective Section II.D of Appendix I to 10 CFR, Part 50.
The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR, Part 50, l
for liquid ef fluents.
i
-216f Amendment No.104
~
PBAPS 3.8.C s 4.8.C BASES f
Dos e This specificaticm is provided to ensure that the dose 'from radioactive materials in gaseous of fluents at and beyond the SITE BOUNDARY will be within the annual dose limits of 10 CFR Part 20.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result. in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding' the limits specified in Appendix B, Table II of 10 CFR Part 20.lO6(b)
For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
Examples of calculations for such MEMBERS OF THE PUBLIC with the appropriate occupancy factors are given in the ODO(.
The specified limits restrict, at all times, the gamma and beta dose rates above background to a MEMBER OF THE PUBLIC, at or beyond the SITE BOUNDARY to < 500 mrem / year to the total body or to 13000 mrem / year to the sEin.
These dosre rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to 1 1500 mrem / year.
Dose, Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Conditica for Operaticm implements the guidance set forth in Section II.B of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable".
The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guidances of Appendix I be shown by calculational procedures based cm models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be.substantially underestimated.
The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous ef fluents are consistent with the methodology provided in j
Regulatory. Guide 1.109, " Calculation of Annual Doses to Man f rom Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I", Revision 1,
-216f Amendment No. 104
PBAPS October 1977 and the atmospheric dispersion model submitted on September 30, 1976, in a report titled: "Information Requested in
- to letter from George Lear to E. G. Bauer dated February 17, 1976".
The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
Dose - Iodine-131, Tritium and Radionuclides in Particulate Form This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting condition for Operation implements the guidance set forth in Section II.C of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous ef fluents will be kept "as low as reasonably achievable".
The ODCM calculational methods specified in the surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures bas ed on models > and data such that the actual exposure of a MEMBER OF THE' PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The ODCM calculational methods -
for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provi,ded in Regulatory. Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and the Atmospheric Dispersion Model submitted on September 30, 1976 in a report titled: "Information Requested in to letter f rom George Lear to E. G. Bauer dated February 17, 1976".
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate specifications for iodine-131, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY.
The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetaticm with subsecuent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
l l
Amendment No.104
-216f -
PBAPS Instrumentation The radioactive gasaous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The operability and use of instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 GR, Part 50.
i System Operation The operability of the gaseous radwaste treatment system ensures that this system will be available for use whenever gaseous ef fluents require treatment prior to release to the environment.
The requirement that appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".
This specification implements the requirements of 10 T R, Part 50.36a, General Design criterion 60 of Appendix A to 10 GR, Part 50 and design objective Section II.D of Appendix I to 10 G R, Part 50.
The specified limits governing the use of appropriate portions of the gaseous radwaste treatment system were specified as a suitable fraction of the guidance set forth in Sections II.B and II.C of Appendix I, 10 TR, Part 50, for gaseous ef fluents.
Main Condenser Restricting the gross radioactivity release rate of noble gases from the main condenser provides reasonable assurance that the total body exposure to an individual at the SITE BOUNDARY will not exceed a small fraction of the limits of 10 GR, Part 100 in the event this eff1 bent is inadvertently discharged directly to the environment without treatment.
This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 GR, Part 50.
Hydrocen Gas Mixture This specification is provided to ensure that the concentration of potentially explosive hydrogen gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen.
Maintaining the concentration of hydrogen below its flammability limits provides assurance that the releases of radioactive materials will be controlled in Amendment No. 104
-216f i
.~
.a conformance with the requirements of General Design Criterion 60 of A'ppendix A to 10 CFR Part 50.
Containment Purge Specification 3.8.C.8 requires that the primary containment atmosphere receive treatment for the removal of gaseous iodine and particulates prior to release to provide reasonable assurance that purging operations will not result in exceeding the annual dose limits of 10 CFR Part 20 for areas at or beyond the SITE BOUNDARY.
Total Dose This specification is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorpora'ted into 10 CFR Part 30.
This specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.
It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CPR Part 190 if the individual reactors remain within the reporting requirement level.
The Special Report will describe a course of action that should result in the limitation of the annual d'se to o
a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.
For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose l
contributions from other nuclear fuel cycle f acilities at the same site or within a radius of 8 kilometers (km) must be considered.
If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is considered to be a timely i
reauest and fulfills the requirements of 40 CFR Part 190 until i
NRC staff action is completed.
The variance only relates to the l
limits of 40 CFR Part 190, and does not apply in any way to the other recuirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1 and 3.11.2.
An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
l
-216f Amendment No. 104
- 3. 8.E & 4. 8.E B ASES l
j Monitoring Procram The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the two reactors at the site.
This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.
The recuired detection capabilities for environmental sample analyses are tabulated in terms of the Minimum Detectable Level (MDL).
The MDL's required by Table 4.8.1 and 4.8.2 of the specifications are considered optimum for routine environmental measurements in industrial laboratories.
The monitoring program.
was developed utilizing the experience of the first seven years of commercial operation.
Program changes may be initiated based on the additional operational experience.
Land Use Census This specification is provided to ensure that significant changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census.
This census satisfies the recuirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.
i Interlaboratory Comoarison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure,that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices, are performed as part of the quality assurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
f Amendment No.104
-216f f
1 l
PBAPS 6.5.1.6, Continued h.
Review of the Plant Securitp Pla and implementing procedures and.shall submit recommended changes to the Plan, to the Chairman of the Operation and
^
Saf ety Review Committee.
i.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Plan, to the Chairman of the Operation and Safety Review Committee.
j.
Review of every unplanned release reportable under 6.9.2.b.(5) of radioactive material to the envi rons; evaluate the event; specify remedial action to prevent recurrence; and document the event description, evaluation, and corrective action and the disposition of the corrective action in the plant records.
Authority 6.5.1.7 The Plant Operation Review Committee shall:
i a.
Recommend to the Station Superintendent written approval or disapproval of items considered under 6.5.1.6(a) through (d ) above, b.
Render determinations in writing with regard to whether or not each item considered under
$.5.1.6(a) through (e) above constitutes an i
unreviewed safety question, as defined in 10 CFR 50.59.
c.
Provide immediate written notification to the Superintendent, Generation Division-Nuclear or, in his absence, the Superintendent, Generation Division-Fossil-Hydro, and the Operation and Safety Review Committee of disagreement between the PORC and the Station Superintendent; however, the Station Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
j l
Amendment No. 19, 37, $2,104
-248-
PBAPS 2
Records 6.5.1.8 The Plant Operation Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Superintendent, Generation Division-Nuclear and Chairman of the Operation and Safety Review Committee.
O O
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-248a-Amendment No.104
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6.5.2.8 Continued The Facility Emergency Plan and implementing e.
procedures at least once per two years.
f.
The Facility Security Plan and implementing procedures at least once per two years, g.
The Offsite Dose Calculation Manual and implementing procedures at least once per two years.
l h.
The performance of activities recuired by the Quality Assurance Program regarding the radiological monitoring program to meet the provisions of Regulatory Guide 4.1, Revision 1, April 1975, at least once per calendar year.
i.
Any other area of facility operation considered appropriate by the OSR Committee or the Vice President, Electric Production.
Authority 6.5.2.9 The OSR Committee shall report to and advise the Vice President, Electric Production on those areas of responsibility specified to Section 6.5.2.7 and 6.5.2.8.
Records 6.5.2.10 Records of OSR Committee activities shall be prepared, approved, and distributed as indicated below:
a.
Minutes of each OSR Committee meeting shall be prepared, approved and forwarded to the Vice President, Electric Production within 14 days following each meeting.
b.
Reports of review encompassed by Section 6.5.2.7.e,f,g, and h above, shall be prepared,
approved and forwarded to the Vice President, Electric Production within 14 days following completion of the review.
Amendment No. Jp, 37,104
-252-
PBAPS c.
Audit reports encompassed by section 6.5.2.8 above, shall be forwarded to the Vice President, Electric Productics and to the management positions responsible for the areas audited within 30 days after completion of the audit.
b b
-252a-Amendment No. 104
.1 PRAPS 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Station Superintendent or his designated alternate per Specification 6.1.1 prior to implementation and periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made, providedt a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's' License on the unit
- affected, c.
The change is documented, reviewed by the PORC and 4
approved by the Station Superintendent within 14 days of implementation.
6.8.4 Written procedures shall be established, implemented and maintained covering the activities of the radiological effluent technical specifications as referenced below:
a a.
Offsite Dose Calculation Manual l
b.
Duality Assurance Program for the environmental monitoring using the guidance in Regulatory Guide 4.1, Revision 1, April 1975.
6.9 Reportiner Recuirements In addition to the applicable reporting reauirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Administrator of the appropriate Regional Of fice unless otherwise noted.
Amendment No. J0, N, #7,104
-254-
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PBAPS 6.9.1 Routine Reports a.
Startup Report. A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a diff erent fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.
The report shall address each of the tests identified in the FSAR and shall in general 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 reported in this report.
Startup reports shall be submitted within 90 days following resumption or commencement of commercial full power operation.
b.
Annual Occupational Exposure Tabulation (1)
A tabulation shall be made 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 man-rem exposure according to work and job function, (2) e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special
~
maintenance (describe maintenance), waste processing, and refueling.
This tabulation shall be submitted for the previous calendar year prior to March 1 of each year.
The dose assignment to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposure totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major job functions.
(1)
A single submittal may be made for a multiple unit stati on.
(2)
This tabulation supplements the requirements of 10 CFR 20.407.
Amendment No. J7, SR, 104
-254a-
o PBAPS 6.9.2 Continued (7)
Conditions arising from natural or man-made events that, as a direct result of the event require plant shutdown, operation of safety systems, or other protective measures required by technical specifications.
(8)
Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in
. a manner less conservative than assumed in the analyses.
(9)
Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the saf ety analysis report or technical specifications that reouire remedial action or corrective measures to prevent the existence or development of an unsafe condition.
Note: This item is intended to provide for reporting of l
potentially generic problems.
(10) becurrence of an unusual or important radiological event that has potential environmental impact f rom unit operation, or that has high public interest concerning environmental impact from unit operation.
b.
Thirty Day Written Reports.
The reportable occurrences discussed below shall be the subject of written reports to the Director of the appropriate Regional Office within thirty days of occurrence of the event.
The written report shall include, as a minimum, a completed copy of a licensee event report form.
Information provid ed on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the cireurstances surrounding the event.
Amendment No. 104
-256-
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&za& -
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t PBAPS (1)
Reactor protection system or engineered safety f eature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systess.
(2)
Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or
]
plant shutdown required by a limiting condition for operation.
Notes Routine surveillance testing, instrument calibration, or preventative maintenance which require system configurations as described in items 2.b(1) and 2.b(2) need not be reported except where test results.themselves reveal a degraded acde as described above.
(3)
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
i (4)
Abnormal degradation of systems other than those specified in item 2.a(3) above designed to contain radioactive material resulting from the fission process.
Note: Sealed sources or calibration sources are not included under this item.
Leakage of valve packing or gaskets within the limits for identified leakage set forth in technical specifications need not be reported under this item.
(5)
An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents,
- 2) more than 150 curies of noble gas from a roof vent or 15,000 curies of noble gas f rom the stack in gaseous effluents, or 3) more than 0.05 curies i
of radiciodine f rom a roof vent or 5 curies of radiciodine from the stack in gaseous effluents.
l The report of an unplanned offsite release of l
radioactive material shall include a description l
of the event and equipment involved, the cause(s) l of the unplanned release, the actions taken to Amendment No. 104
-256a-
PBAPS prevent recurrence, and the consequences of the l
unplanned release.
6.9.3 Unioue Reporting Recuirements Special reports shall be submitted.to the Director of the appropriate Regional Office within the tima.. period specified for each report.
These reports shal-1. be submitted covering the activities identified below
'i pursuant to the reeuirements of the applicable reference specifications a.
Loss of shutdown margin, Specification 3.3.A and 4.3.A within 14 days of the event.
b.
Reactor vessel inservice inspection, Specification 3.6.G and 4.6.G within 90 days of the completion of the reviews.
i
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c.
Report seismic monitoring instrumentation inoperable for more than 30 days (Specification 3.15B) within the next 10 working days.
Submit a seismic event analysis (Specification 4.15B) within 10 working days of the event.
d.
Primary containment leak rate testing approximately three months af ter the completion of the periodic integrated leak rate test (Type A) required by Specification 4.7. A. 2.c.2.
For each periodic test, leakage test results from Type A, B
and C tests shall be reported.
B and C tests are local leak rate tests required by Specification 4.7.A.2.f.
The report shall contain an analysis and interpretation of the Type A test results and a summary analysis of periodic Type B and Type C tests that were performed since the last Type A test.
e.
Calculated dose from release of radioactive af fluents, Specification 3.8.B.2, 3.8.B.4, 3.8.C.2, 3.8.C.3, 3.8.C.6, and 3.8.D.
f.
Sealed source leakage in excess of limits, Specification 3.13.2.
Amendment No. 77, 97, R, 79,104
-257-l
PBAPS a
g.
The concentration of radioactivity in excess of the environmental monitoring program reporting levels per Specification 3.8.E.lb.
l h.
Effluent Releases (1)
Annual Radiological Environmental Operating Report Routine radiological environmental operating reports covering the previous calendar shall be submitted prior to May 31 of each year.
The annual radiological environmental operating reports shall include summaries, interpretations, and. evaluations of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies with operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.
The reports shall also include the results of the annual land use census recuired by Specification 3.8.E.2.
j l
i The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental
. samples and of all environmental radiation measurements taken during the period pursuant to the locations specified.in Table 4.8.3, as well as summarized and tabulated results of these analyses and measurements in the format i
of the table in the Radiological Assessment l
Branch Technical Position, Revision 1, i
November 1979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
l The reports shall also include or reference l
f rom previous reports the following: a i
summary description of the radiological l
Amendment No.104
i PBAPS environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, and measuring eauipment used; at least two maps of all sampling locations keyed to a table giving distances and directions from the midpoint between reactor vents; the results of land use censuses reouired by Specification 3.8.E.2; the results of the Interlaboratory Comparison Program and discussion of all analyses in which the LLD required by Tables 4.8.1 and 4.8.2 was not achievable.
(2)
Semiannual Radioactive Ef fluent Release Report Routine radioactive effluent release reports covering the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year.
The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive licuid and gaseous effluents and solid waste released from the site.
The Radioactive Effluent Release Reports shall include the ' following information for each class of solid waste (as defined by 10
, CFR Part 61) shipped offsite during the report period:
a.
Container volume, i
b.
Total curie quantity (specify whether determined by measurement or estimate),
i c.
Principal radionuclides (specify whether determined by measurement or estimate),
l d.
Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms), and
-259-Amendment No. 104 t
., i e.
Type of container. (e.g., LSA, Type A,
~ l Type B, Large Quantity).
The Radioactive Ef fluent Release Reports shall include a list and description of unplanned releases from the site to areas at and beyond the SITE BOUNDARY of radioactive l
materials in gaseous and licuid affluents made during the reporting period.
The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODO4), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.8.E.2.
(3)
Radiation Dose Assessment Report The radiation dose assessment reports shall be submitted within 120 days after January 1 of each year.
I The Radiation Dose Assessment Report shall include an annual summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of an hour-by-hour listing
- on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.** This same report shall include an assessment of the radiation doses due to l
the radioactive liquid and gaseous ef fluents released from the unit or station during the previous calendar year.
This same report shall also include an assessment of the i
radiation doses from radioactive liauid and gaseous ef fluent to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period.
All assumptions l
used in making these assessments (i.e.,
specific activity, exposure time and location) shall be included in these reports.
l' The meteorological conditions concurrent with the time of release of radioactive materials
- ~
Amendment No. 104
_. _ _ -. _.. - _ ~. _ -,.. _,
PBAPS 1
in gaseous affluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.
Approximate methods are acceptable.
The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION P9LNUAL (ODCM).
The Radiation Dose Assessment Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses f rom primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190 Environmental Radiation Protection Standards for Nuclear. Power Operation.
Guidance for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1, October 1977.
If doses from plant effluents do not exceed twice t,he Appendix I limits, a statement to that effect shall constitute a 40 CFR 190 assessment.
~
In lieu of submission with the first half year Radioactive Effluent Release Report, the licensee will retain this summary of required meteorological data on site in a file that shall be provided to the NRC upon reauest.
l l
r
-259b-Amendment No. 104
PBAPS 6.10.2
. Continued d.
Records of radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive material released to the environs.
I f.
Records of transient or operational cycles for-those facility components designed for a limited number of transients or cycles.
g.
Records of training and qualification for current members of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical specifications.
i.
Records of Quality Assurance activities required by the QA Manual, except as described in 6.10.1
~
above.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PORC and the OSR Committee.
1.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.16.
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 ef fective at specified times and QA records showing that these procedures were followed.
i '
Amendment No. M 104 Order dated 10/24/80
-261-E i
.-...w.
PBAPS 6.11 Radiation Protection Procram Procedures for personnel radiation protection shall be prepared consistent with requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 Fire Protection Inspections O.
An independent fire protection and loss prevention program inspection shall be performed at least once per 12 months utilizing either cualified off site licensee personnel or an outside fire protection firm.
b.
An inspection of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.
l l
-26Ia-Amendment No.104
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l
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FBAPS 6.17 Of f site Dose Calculation Manual (ODCM) 6.17.1 The ODCM shall describe the methodology and parameters to be used in the calculation of off site doses due to radioactive gaseous and liquid effluents.
6.17.2 Licensee initiated changes to the ODCM:
1.
Shall be submitted to the Commission in the Semiannual Radioactive Ef fluent Release Report for the period in which the change was made.
This submittal shall contains 4 a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
b.
A determination that the change will no t, reduce the accuracy or reliability of dose calculations.
2.
Shall become effective upon a date specified and agreed to by the PORC following their review and acceptance of the change (s).
6.18 Major Chances to Radioactive Waste Treatment Systems 6.18.1 The radioactive waste treatment systems are those systems described in Specifications 3.8.B.3, 3.8.B.4, 3.8.C.4 and 3.8.C.5, which are used to maintain control over radioactive materials in gaseous and liauid l
effluents.
i 6.18.2 Major changes to the radioactive waste systems shall be I
made by either of the following methods.
For the purpose of this Specification ' major changes' is defined in Specification 6.18.3 below.
-265-l Amenchent No.104
d.
l i
l s
.e F
A.
Licensee initiated changes:
1)
Licensee initiated changes shall be reported to the Commission as part of the Modification Report recuired by 10 CFR 50.59.
The discussion of each change shall contain:
a.
A summary of the evaluation.that led to the determination that the change could f
be made in accordance with 10 CFR Part 50.59; b.
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information:
c.
A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d.
A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; e.
An estimate of the exposure to plant operating personnel as a result of the change; and f.
Documentation of the' fact that the change was reviewed and found acceptable by the PORC.
2)
The change shall become effective upon review and acceptance by both the PORC and OSR Committee.
-266-Amendment No.104
~
n PBAPS B.
Ccamission initiated changes:
1)
The applicability of the change to the facility shall be determined by the PORC af ter consideration of the f acility design.
2)
The licensee shall provide the Commission with written notification of its determinatien of applicability including any necessary revisions to reflect facility design.
3)
The change shall be reviewed by the OSR Committee at its next regularly scheduled meeting.
4 4)
The change shall become effective on a date proposed by the licensee and confirmed by the Commission.
6.18.3
" Major Changes" to radioactive waste systems shall include the following:
A)
Changes in process equipment, components, structures and effluent monitoring instrumentation from those described in the Final Safety Analysis i
Report (FSAR) and evaluated in the staff's Safety Evaluation Report (SER);
B)
Changes in the design of radwaste treatment systems that significantly alter the dnaracteristics-and/or quantities of ef fluents released f rom those previously considered in the FSAR and SER C)
Changes in system design which invalidate the accident analysis as described in the SER; and D)
Changes in system design that result in a signi ficant increase in occupational exposure of operating personnel.
Amendment No. 104
-267-
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I PSAPS TA81.!*0F CONTENTS Page.
No.
1.0 Definitions, Abbreviations and Symbols 1
1.1
~0efinitions 1
1.2 Abbreviations 2
1.3 5.vmbolss 3
2.0 4( b'eletcd)Y 3.0 Menitorino Recuirements 5
2.1 (Thermal) 3.1 5
2.2
'.( Del eted) 3.2 (Deleted) 2.2'.1 'I' Deleted) 3.2.1 (Deleted) 2.2.2 Deleted) 3.2.2 (Deleted) 2.2.3 (Deleted) 3.2.3 (Deleted?
2.2.'4.(Deleted)
~
3.2.4 ( Deleted I
1 2.3
(. Del etad).
3.3-(Del eted).
4.0 secort'Cevels 5.0 Monitorine Recuirements 11
.:.1 (Deleted) 5.1 (Deleted) 4.2 geted -
5.2 eleted}).
eted 5.3 4.3 e ete g
5.0 Envi.enmental Surveillance and See:ial Studv Procrams 14 5.1 (Deleted) s 5,2 (Deleted) 5.3 (Deletsd) 6.4 (Deleted) l 7.0 Administrative contmis 48 l
7.1 Organization, Review and Audit 48 7.1.1 Organization 48 7.1.2 Review and Audit 48 h
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.j_
4 s
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7
/cendment No.104 s
s
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4 1
1 i
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LEFT BLANK INTENTIONALLY
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- l 4
i 13-Amendment No.104
.a.
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1 e
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.I t
WT ELUDC INTENTIONALLY -
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i.
Amendment No.104 g
t t
7.U Adminis tra tive Control s 7.1 Oreanization, Review and Audi t 7.1.1 Oroani za tion
~
A.
The Plan't " Superintendent is responsible' for the operation of the facili ty and to assure that the facili ty operates wi thin the limi ts set forth in the envi ronmenta l technical speci fications.
B.
In all matters pertaining to operation of the' f acility and to the environmental technical specifications, the Plant Superintendent shall report to, and consult wi th the Superintencent, liuclear Section of the Generation Division or, in his absence, the Superintendent, Fossil and Hydro Section of the Generation Division. The management organi zation is shown in Figure 7.1-1.
7.1.2 Review and Audit t
Commi ttees for review and audi t of plant operation are des-cribed in Section 6.5 of Appendix A to the Operating License.
48-A=enesent No.104
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