ML20079M989

Proposed Radiological ETS

ML20079M989
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/23/1984
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20079M975	List: ML20079M972 ML20079M989
References
NUDOCS 8401270497
Download: ML20079M989 (83)

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i VYNPS TABLE OF CONTENTS (continued) t LIMITING CONDITIONS OF OPERATION Page No. Surveillance l 3.8 RADIOACTIVE EFFLUENTS......................................... 147 4.8 A. Liquid Effluents: Concentration.......................... 147 A B. Liquid Effluents: Dose................................... 148 B C. L iqu id Rad wa s te Trea tme nt................................. 149 C D. Liquid Holdup Tanks....................................... 149 D E. Gaseous Effluents: Dose Rate............................. 150 E i F. Gaseous Effluents: Dose From Noble Gases................. 151 F G. Gaseous Effluents: Dose From Iodine-131, Iodine-133, Tritium, and Radioactive Materials in Particulate Fora.... 152 G H. Gaseous Radwaste Treatment................................ 152 H l 1. Ventilation Exhaust Treatment............................. 153 I J. Explosive Gas Mixture..................................... 153 J ] K. Steam Jet Air Ejector (SJAE).............................. 153 K L. Primary Containment....................................... 154 L M. Total Dose................................................ 155 M N. Solid Radioactive Waste................................... 156 N 3.9 RADIOACTIVE EFFLUP.NT MONITORING SYSTEMS....................... 161 4.9 l A. Liquid Effluent Instrumentation........................... 161 A B. Ga seous Ef fluent Inst rumentation.......................... 161a B C. Radiological Environmental Monitoring Program............. 161a C D. La nd U s e Ce n s u s........................................... 162 D E. Inte rcompa ri so n Prog ram................................... 163 E i ( i i, i i l Amendment No. 43, 67, -iv-i I i I

VYNFS TABLE OF CONTENTS (continued) g LIMITING CONDITIONS OF OPERATION Page No. Surveillance I 3.10 AUKILIARY ELECTRICAL POWER SYSTEMS............................ 173 4.10 A. No rmal Ope ra t i o n.......................................... 173 A j B. Operation with Inope rable Components...................... 176 B C. Diesel Fue1............................................... 177 C 3.11 REACTOR FUEL ASSEMBLIES....................................... 180s 4.11 I A. Ave rag e Pla na r LHC R....................................... 180a A B. LHGR...................................................... 180b B C. MCPR...................................................... 180c C 3.12 REFUELING AND SPENT FUEL RANDLING............................. 181 4.12 i ) A. Re f ue li ng Int e r1oc ks...................................... 181 A B. Core Monitoring........................................... 182 B C. Fuel S to rage Pool Wa te r Leve1............................. 183 C D. Cont rol Rod and Control Rod Drive Maintenance............. 184 D E. Ex t e nd ed Co re Maint e na nc e................................. 18% E l F. Fuel Movement............................................. 185 F l G. C ra ne O pe ra b il i t y......................................... 185 G j H. Spent Fuel Pool Water Temperature......................... 185a H u i i 3.13 FIRE PROTECTION SYSTEM........................................ 187b 4.13 5.0 DESIGN FEATURES.................................................... 188 4 6.0 ADMINISTRATIVE 00NTROLS............................................ 190 4 i i ) Amendment No. 43, 67, -v-4 I i f

I. VYNPS 4 j G. Instrument Functional Test - An instrument K. Operable - A system, subsystem, train, component functional test shall be: or device shall be operable or have operability when it is capable of performing its specified 1. Analog channels - the injection of a signal function (s). Implicit in this definition shall be into the channel as close to the sensor as the assumption that all necessary attendant l practicable to verify operability including instrumentation, controls, normal and emergency alarm and/or trip functions. electrical power sources, cooling or saal water. lubrication or other auxiliary equipment that are j 2. Bistable channels - the injection of a signal required for the system, subsystem, train. 1 l into the sensor to verify operability component or device to perform its function (s) are including alarm and/or trip functions. also capable of performing their related support 1 i function (s). i H. Logic System Functional Test - A logic system ) functional test means a test of all relays and L. Operatijgt - Operating means that a system or contacts of a logic circuit from sensor to component is performing its intended functions in ) activated device to insure all components are its required manner. operable per design intent. Where possible, l action will go to completion, i.e., pumps will be M. Operating Cycle - Interval between the end of one started and valves opened. refueling outage and the end of the next 4 subsequent refueling outage. I 1. Minimum Critical Power Ratio - The minimum ) critical power ratio is defined as the ratio of N. Primary Containment Integrity - Primary that power in a fuel assembly which is calculated containment integrity means that the drywell and to cause some point in that assembly to experience pressure suppression chamber are intact and all of boiling transition as calculated by application of the following conditions are satisfied: the GEKL correlation to the actual assembly operating power (Reference NEDO-10958). 1. All manual containment isolation valves on lines connecting to the reactor coolant J. Mode - The reactor mode is that which is system or containment which are not required established by the mode selector switch. to be open during accident conditions are closed. 2 Amendment No. 64, 70, 9 ~

t 5 i VYNPS I a 1 I TABLE OF CONTENTS a (continued) I 1 LIMITING CONDITIONS OF OPERATION Page No. Surveillance F. Automatic Depressurization System......................... 92 F G. Reactor Core Isolation Cooling System (RCIC).............. 93 G H. Minimum Core and Containment Cooling System Availability.. 94 H l 1. Maintenance of Filled Disc harge Pipe...................... 95 I 3.6 REACIOR COOLANT SYSTEM........................................ 105 4.6 1 l A. Pressure and Temperature Limitations...................... 105 A B. Coolant Chemistry......................................... 106 B j C. Coolant Leakage........................................... 1 08 C j D. Safety and Relief Va1ves.................................. 108 D E. Structural Integrity...................................... 109 E F. Jet Pumps................................................. 109 F i G. Single-Loop Operation..................................... 110 'j H. Recirculation System...................................... 110 I. S hoc k S up p r e s so r s......................................... 110a I J. The rmal-Hyd raulic S tability............................... 110b J 3.7 STATION CONTAINMENT SYSTEMS................................... 126 4.7 d i 1 j A. Primary Containment....................................... 126 A j B. S t a nd by Ga s T rea t me n t..................................... 130 B C. S econda ry Containme nt Sy stem.............................. 131 C D. Yrimary Containment Isolation Va1ves...................... 132 D i 1 1 o 1 i i I l Amendment No. 67 -111-1

VYNPS 2. At least one door in each airlock is closed i and sealed. 3. All automatic containment isolation valves are operable or deactivated in the isolated position. 4. All blind flanges and manways are closed. O. Protective Instrumentation Definitions 1. Instrument Channel - An instrument channel means an arrangement of a sensor and auxiliary equipment required to generate and transmit to a trip system a single trip signal related to the plant parameter monitored by that instrument channel. j 2. Trip System - A trip system means an arrangement of instrument channel trip j signals and auxiliary equipment required to initiate 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 action. j Initiation of protective action may require the tripping of a single trip system or the l coincident tripping of two trip systems. l i l l 4 l j Anandment No. 2a I i I

t VYNPS BB. Source Check - The qualitative assessment of GG. Radioactive Material - Any material or combination channel response when the channel sensor is of materials which spontaneously emits ionizing exposed to a radioactive source. radiation and in which the specific activity is greater than 0.002 microcuries/ gram of material or i CC. Dose Equivalent 1-131 - The dose equivalent I-131 any material in which the total estimated activity ) shall be that concentration of 1-131 is greater than 5 microcuries is classified as a (microcurie / gram) which alone would produce the radioactive material. 1 l same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, 1-134 and 1-135 HH. Contamination j j actually present. The thyroid dose conversion l factors used for this calculation shall be those 1. Removable radioactive contamination shall be listed in NRC Regulatory Guide 1.109, Rev. 1, considered significant and unreleasable fron l October 1977. the owner controlled area if the level, when averaged over 300 square centimeters, exceeds DD. Solidification - Solidification ehall be the 220 dpe/ square centimeter for beta gamma, conversion of wet wastes into a form that meets and 22 dps/ square centimeter for alpha j shipping and burial ground requirements. Suitable emitting radionuclides. i forms include dewatered resins and filter sludges. 2. Fixed contamination shall be considered EE. Member (s) of the Public - Members of the public significant and unreleasable from the owner shall include all persons who are not controlled area if the dose rate at any occupationally associated with the plant. This accessible surface exceeds 0.5 aren/ hour. category does not include employees of the utility, its contractors or vendors. Also II. Off-Site Dose Calculation Manual (ODCM) - A manual excluded from this category see casual visitors to containing the current methodology and parameters the plant and persons who enter the site to used in the calculation of off site doses due to service equipment or to make deliveries. radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent FF. Site Boundary - The site boundary is shown in monitoring alarm / trip setpoints, and in the j Figure 2.2-5 in the FSAR. conduction of the environmental radiological j monitoring program. 1 i } Ausndment No. 5 i l

VYNPS JJ. Process Control Program (PCP) - A process control LL. Ventilation Exhaust Treatment System - The program shall contain the sampling, nnalysis, Radwaste Building and A0G Building ventilation tests, and determinations by which wet radioactive HEPA filters are ventilation exhaust treatment waste from liquid systems is assured to be systems which have been designed and installed to converted to a form suitable for of f site disposal. reduce radioactive material in particulate form in gaseous effluents by passing ventilation air KK. Gaseous Radwaste Treatment System - The Augmented through HEPA filters for the purpcse of removing Off-Gas System (A0G) is the gaseous radwaste radioactive particulates from the gaseous exhaust treatment system which has been designed and stream prior to release to the environment. installed to reduce radioactive gaseous effluents Engineered safet) feature atmospheric cleanup by collecting primary coolant system off gases systems, such as the Standby Gas Treatment (SBGT) from the primary system and providing for delay or System, are not considered to be ventilation holdup for the purpose of reducing the total exhaust treatment system components. radioactivity prior to release to the environment. MM. Vent / Purging - Vent / Purging is the controlled process of discharging air or gas f rom the primary containment to control temperature, pressure, humidity, concentration or other operating conditions. 0 Amendment No. 6 2

VYNPS TABLE 3.2.4 0FF-GAS SYSTEM ISOLATION INSTRUMENTATION Minimum Number of Required Action When + Operable Instrument Minimum Condition for Channels per Trip System Trip Function Trip Settina Operation Are Not Mat 1 Time Delay (Stack Off-Gas Valve 1 2 minutes Note 1 Isolation) (15TD & 16TD) 1 30 minutes Note 1 1 Trip System Logic Nete 1 At least one of the radiation monitors between the charcoal bed system and the plant stack shall be operable during operation of the augmented off gas system. If this condition cannot be met, continued operation of the augmented off gas system is permissible for a period of up to 7 days provided that at a I least one of the stack monitoring systems is operable and of f gas system temperature and pressure ate seasured continuously. i i 1 l Amendment No. 25 46 I t 1

VYNPS TABLE 4.2.4 MINIMUM TEST AND CALIBRATION FREQUENCIES OFF-GAS SYSTEM ISOLATION INSTRUMENTATION Trip Function Functional Test (8) Calibration (8) Instrument Check Augmented Off-Gas Trip System Logic (A0G) Every 6 months Every 6 months (Note 2) (Note 3) Amendment No. 20, 58

VYNPS I 3.2 (continued) The APRM rod block trip is flow referenced and prevents a significant reduction in MCPR especially during operation at rtduced flow. The APRM provides gross core protection; i.e., limits the gross core power increase from withdrawal of j eentrol rods in the normal withdrawal sequence. The trips are set so that MCPR is maintained greater than the fuel cladding integrity safety limit. The IRM rod block function provides local as well as gross core protection. The scaling arrangement is such that trip estting is less than a factor of 10 above the indicated level. Analysis of the worst case accident results in rod l block action before MCPR approaches the fuel cladding integrity safety limit. l A downscale indication on an APRM or IRN is an indication the instrument has failed or the instrument is not sensitive snough. In either case the instrument will not respond to changes in control rod motion and thus control rod motion is prevented. To prevent excessive clad temperatures for the small pipe break, the HPCI or Automatic Depressurization System must function since for these breaks, reactor pressure does not decrease rapidly enough to allow either core spray or LPCI to operate in time. The arrangement of the tripping contacts is such as to provide this function when necessary and ninimize spurious operstion. 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 servica. l l a l Amendment No. 25, 65 i

1 l VYNPS 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS 3.8 RADIOACTIVE EFFLUENTS 4.8 RADI0 ACTIVE EFFLUENTS 1 Applicability Applicability Applies to the release of all radioactive Applies to the required surveillance of all l l effluents from the plant. radioactive effluents released from the plant. t l Objective Objective l To assure that radioactive effluents are kept "as To ascertain that all radioactive effluents low as is reasonably achievable" in accordance released from the plant are kept "as low as is l with 10CFR50, Appendix I and, in any event, are reasonably achievable" in accordance with 10CFR50, 1 within the limits specified in 10CFR20. Appendix I and, in any event, are within the t limits specified in 10CFR20. ) Specification Specification I A. Liquid Effluents: Concentration A. Liquid Effluents: Concentration i 1. The concentration of radioactive 1. Radioactive material in liquid waste material in liquid effluents released shall be sampled and analyzed in from the site shall be limited to the accordance with requirements of Table concentrations specified in 10CFR Part 4.8.1. The results of the analyses 9 20, Appendix B. Table II, Column 2 for shall be used in accordance with the j radionuclides other than noble gases and methods in the CDCM to assure that the l 2x10-4 uC1/mi total activity concentrations at the point of release concentration for all dissolved or are limited to the values in i entrained noble gases. Specification 3.8.A.1. Amendment No. 147 l 4

l 1 i VYNPS 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS 2. With the concentration of radioactive material in liquid effluents released f rom the site exceeding the limits of Specification 3.8. A.1, immediately take action to decrease the release rate of I radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits. i B. Liquid Effluents: Dose 8. Liquid Effluents: Dose 1. The dose or dose commitment to a member 1. Cumulative dose 6ontributions shall be of the public from radioactive materials determined in accordance with the in liquid effluents released from the methods in the ODCM at least once per site shall be limited to the following: month if releases during the period have occurred. a. During any calendar quarter: l 1ess than or equal to 1.5 area to the total body, and less than or equal to 5 area to any j organ, and l b. During any calendar year: less than or equal to 3 area to the total body, and j less than or equal to 10 area to j any organ. i l Amendment No. 148 i l 1

4 VYNPS 4 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS C. Liquid Radwaste Treatment C. Liquid Radwaste Treatment 1. The liquid radwaste treatment system 1. See Specification 4.8.B.1. shall be used in its designed modes of operation to reduce the radioactive materials in the liquid waste prior to its discharge when the estimated doses due to the liquid effluent from the site, when averaged with all other liquid release over the last month, would exceed 0.06 area to the total j body, or 0.2 mrem to any organ. 4 l D. Liquid Holdup Tanks D. Liquid Holdup Tanks i j 1. The quantity of radioactive material 1. The quantity of radioactive material j contained in any outside tank

• shall be contained in each of the liqui' holdup l

limited to less than or equal to 10 tanks

• shall be determined to Le within j

curies, excluding tritium and dissolved the limits of Specification 3.8.D.1 by or entrained noble gases. analyzing a representative sample of the tank's content at least once per week or when radioactive materials are being ? added to the tank. I.

• NOTE: Tanks included in this Specification are only those outdoor tanks that are not surrounded by liners, j

dikes, or walls capabic of holding the tank's contents, or that do not have tank overflows and surrounding area j drains connected to the liquid radwaste treatment system. i 1 1 1 i l j Amendment No. 149 1 i i

i i VYNPS l l 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS l 2. With the quantity of radioactive material in any outside tank

• exceeding the limit of Specification 3.8.D.1, j

tamediately take action to suspend all additions of radioactive material tc the l tank. Within 48 hours, reduce the tank contents to within the limit. ) E. Gaseous Effluents: Dose Rate E. Gaseous Effluents: Dose Rate 1. The dose rate due to radioactive 1. The dose rate due to noble gases in l materials released in gaseous effluento gaseous effluents shall be determined to f rom the site to areas at and beyond the be within the limits of Specification site boundary shall be limited to the 3.8.E.1 in accordance with the methods following: in the ODCM. a. For noble gases; less than or equal 2. The dose rate due to Iodine-131, to 500 ares /yr to the total body Iodine-133, tritium and radionuclides in and less than or equal to 3,000 particulate form with half-lives greater area /yr to the skin, and than 8 days la gaseous effluents shall be determined to be within the limits of l b. For Iodine-131, Iodine-133, tritium Specification 3.8.E.1 in accordance with and radionuclides in particulate the methods in the ODCM by obtaining form with half-lives greater than 8 representative samples and performing 3 days; less than or equal to 1,500 analyses in accordance with the sampling area /yr to any organ. and analysis program specified in Table 4.8.2. 2. With the dose rate (s) exceeding the ]j above limits, immediately take action to i decrease the release rate to within the I limits of Specification 3.8.E.1. 1 i Ancndment No. 150 l J

I VYNPS 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS F. Gaseous Effluents: Dose from Noble Gases F. Gaseous Effluents: Dose from Noble Gases 1. The air dose due to noble gases released 1. Cumulative dose contributions for the in gaseous effluents from the site to total time period shall be determined in areas at and beyond the site boundary accordance with the methods in the ODCM shall be limited to the following: at least once every month. a. During any calendar quarter: less than or equal to 5 mrad for gamma radiation, and less than or equal to 10 mrad for beta radiation, and b. During any calendar year: less than or equal to 10 mrad for gamma radiation, and less than or equal to 20 mrad for beta radiation, i l Amendment No. 151

VYNPS 1 4 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS G. Gaseous Effluents: Dose from Iodine-131, G. Gaseous Eff1 tents: Dose from Iodine-131, Iodine-133, Tritium, and Radionuclides in Iodine-133, Tritium, and Radionuclides in Particulate Form Particulate Form j 1. The dose to a member of the public from 1. Cumulative dose contributions for the Iodine-131, Iodine-133, tritium, and total time period shall be determined in radionuclides in particulate form with accordance with the methods in the ODCM half-lives greater than 8 days in at least once every month. gaseous effluents released f rom the site to areas at and beyond the site boundary shall be limited to the following: a. During any calendar quarter: less than or equal to 7.5 mrem to any organ, and b. During any calendar year: less than or equal to 15 mrem to any organ. H. Gaseous Radwaste Treatment H. Gaseous Radwaste Treatment 1. The Augmented Off-Gas System (A0G) shall 1. The readings of the relevant instrument be used in its designed mode of shall be checked every 12 hours when the operation to reduce noble gases in main condenser SJAE is in use to ensure gaseous waste prior to their discharge that the AOC is functioning. I whenever the main condenser steam jet air ejector (SJAE) is in operation. 1 i i Amendment No. 152

4 VYNPS 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS i. ~ I. Ventilation Exhaust Treatment I. Ventilation Exhaust Treatment 1. The A0G and Radwaste Building 1. See Specification 4.8.F.1 for Ventilation Filter (MEPA) Systems shall surveillance related to A0G and Radwaste be used to reduce particulate materiale Building ventilation filter system in gaseous waste prior to their ope rati on. 1 discharge from those buildings when the estimated doses due to gaseous effluent releases from the site to areas at and l beyond the site boundary would exceed 0.3 area to any organ over one month. j J. Explosive Gas Mixture J. Explosive Gas Mixture l L .f the hydrogen concentration in the 1. The concentration of hydrogen in the i cJf gas downstream of the operating off gas system downstream of the 4 *abiner reaches four percent, take recombiners shall be continuously acofenriate action that will restore the monitored by the hydrogen monitor a atration to within the limit within required operable by Table 3.9.2. e I 48 hott es. K. Steam Jet Air Ejector (SJAE) K. Steam Jet Air Ejector (SJAE) l l 1. Gross radioactivity release rate from 1. The gross radioactivity release rate the SJAE shall be limited to less than shall be continuously monitored in or equal to 0.16 Ci/sec (after 30 accordance with Specification 3.9.B. minutes decay). 2. The gross radioactivity release rate of f 2. With the gross radioactivity release noble gases from the SJAE shall be rate at the SJAE exceeding the above determined to be within the limit of limit, restore the gross radioactivity Specification 3.8.K.1 at the following i release rate to within its liett within frequencies by performing an isotopic 72 hours or be in at least Hot Standby analysis (for Xe-138, Xe-135, Xe-133, l within the subsequent 12 hours. Kr-88, Kr-85m, Kr-87) on a representative sample of gases taken at { the discharge. 1 i a. Once per week. Amandment No. 153

w ~ VYNPS 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURiEILLANCE REQUIREMENTS 3. With the gross radioactivity release rate at the SJAE greater than or equal to 1.5 C1/sec (after 30-minute decay), restore the gross radioactivity release rate to less than 1.5 Ci/sec (after 30 minute decay), or be in Hot Standby within 12 hours. b. Within 4 hours following an increase of 25% or 5000 microcuries/sec, whichever is greater, in steady-state activity { 1evels during steady-state reactor operation, as indicated by the SJAE l

monitor, d

L. Primary Containment L. Primary Containment 1. If the primary containment is to be 1. The primar e containment shall be sampled Vented / Purged, it shall be Vented / Purged prior to vesting / purging per Table through the Standby Gas Treatment System 4.8.2, and if the results indicate whenever the airborne radioactivity radioactivity levels in excess of the levels in containment exceed the levels limits of Specification 3.8.L.1, the specified in 10CFR20, Appendix B, Table containment shall be aligned for I, Column 1 and notes 1-5 thereto. venting / purging through the Standby Gas Treatment System. No sampling shall be 2. With the requirements of Specification required if the venting / purging is 3.8.L.1 not satisfied, immediately through the Standby Gas Treatment (SBGT) f suspend all Venting / Purging of the System. containment. i j 3. During normal refueling and maintenance outages when primary containment is no a I longer required, then Specification 3.8.G shall supersede Specifications l 3.8.L.1 and 2. l Amendment No. 154 i

MM 3.8 LIMITING CONDITIONS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS l M. Total Dose M. Total Dose 1 1. The dose or dose commitmunt to a acaber 1. Cumulative dose contributions from of the public* from all station sources liquid and gaseous effluents shall be is limited to less than or equal to 25 determined in accordance with area to the total body or any organ Specifications 4.8.B.1, 4.8.F.1, and (except the thyroid, which is limited to

4. 8.G. I.

less than or equal to 75 arem) over a calendar year. 2. Cumulative dose contributions from direct radiation from plant sources 2. With the calculated dose from the shall be determined in accordance with release of radioactive.aterials in the methods in the ODON. This liquid or gaseous effluents exceeding requirement is applicable only under twice the limits of Specifications conditions set forth in Specification 3.8.B.1.a. 3.8.B.1.b, 3.8.F.1.a. 3.8.M.2. y

3. 8.F.1. b, 3. 8.G. l. a. or 3. 8.G.1. b,

} calculaticas should be made, including direct radiation contributions from the station to determine whether the above limits of Specification 3.8.M.1 have been exceeded. 3 1 l I

• NOTE: For this Specification a member of the public may be taken as a real individual accounting for his actual i

activities. Amendment No. 155

VYNPS 3.8 LIMITING CONDITIOWS FOR OPERATION 4.8 SURVEILLANCE REQUIREMENTS N. Solid Radioactive Waste N. Solid Radioactive haste 1. The solid radwaste system shall be used 1. Verification of solidification of wet in accordance with a Process Control waste shall be performed as required and Program as described in Section 6.12 to in accordance with the Process Control process wet radioactive waste (spent Program. resins / filter sludges) to meet shipping and burial ground requirements. 2. With the provisions of Specification 3.8.N.1 not satisfied, suspend shipments nf defectively processed or defectively packaged solidified wet radioactive wastes from the site. 4 l ] l .l i 1 Amendment No. 156

A I VYNPS TABLE 4.8.1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i l Lower Limit i Minimum of Detection l. Sampling Analysis Type of Activity (LLD) Liquid Release Type Frequency Frequency. Analysis (uCi/al)a I Batch Waste Release Tanksb Prior to Prior to Principal Gamma 5 x 10-7 each release each release Emittersd Each Batch Each Batch 1-131 1 x 10-6 1 l One Batch Once per Dissolved and 1 x 10-5 per month month Entrained Gases sampled (Gamma Emitters) prior to a relea se Prior to once pe r H-3 1 x 10-5 each release month c Each Batch Composite Gross Alpha 1 x 10-7 i Prior to once per Sr-89, Sr-90 5 x 10-8 i each release quarter ] Each Batch Compositec 1 l Fe-55 1 x 10 ] i l Amendment No. 157 I l

I VYNPS i TABLE 4.8.1 l (continued) TABLE NOTATION 1 I c. The LLD is the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding i that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): i 4.66

• S b LLD =

E*V*K*Y*e i j where: i LLD = the lower limit of detection as defined above (microcuries or picocuries/ unit mass or volume) ) Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as I appropriate (counts / minute) ( = the counting efficiency (counts /dicintegration) E i V = the sample size (units of mass or volume) K = 2.22 x 106 disintegrations / minute / microcurie or 2.22 disintegrations / minute /picoeurie as applicable Y = the f ractional radiochemical yield (when applicable) A = the radioactive decay constant for the particular radionuclide (/ minute) l At = the elapsed time between sample collection and analysis (ainutes) i 4 Amendment No. 158

VYNPS TABLE 4.8.1 (continued) TABLE NOTATION Typical values of E, V, Y and d$t can be used in the calculation. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of othar l radionuclides normally present in the samples. Analysis shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unavailable. It should be recognized that the LLD is defined as a "before the fact" limit representing the capability of a measurement system and not as an "af ter the fact" limit for a partic.ular measurement. This does not preclude j the calculation of an "af ter the fact" LLD for a particular measurement based upon the actual parameters for the l 1 sample in question and appropriate decay correction parameters such as decay while sampling and during analysis. I 'o. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each j batch shall be isolated and then thoroughly mixed to assure representative sampling. I 1 c. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative af the liquids released. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order j for the composite sample to be representative of the effluent release. } d. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-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 i identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level, but as "not detected". When unusual circumstances result in LLDs higher than required, the reasons shall be docunented in the Semiannual l Effluent Release Report. i l Amendment No. 159 j I l l 1

1 i VYNPS TABLE 4.8.2 RADIDACTIVE GASEOUS 'dASTE SAMPLING AND ANALYSIS PROGRAM I Lower Limit Minimum of Detection 1 Sampling Analysis Type of Activity (LLD) r i j Goreous Release Type Frequency Frequency Analysis (uCi/ml)a__ l A. Steam Jet Air Once per once per Xe-138, Xe-135, 1 x 10-4 Ejector week week Ke-133, Kr-88, .l s Grab Sample Kr-87, Kr-85M i B. Containment Purge Prior to Prior to Principal Gamma 1 x 10-4 each release each release Emitterad Each Purge Each Purge j Grab Sample C. Main Plant Stack Once per Once per Principal Gamma 1 x 10-4 monthe monthe Emittered jr Grab Sample H-3 1 x 10-6 Once per I-131f 1 x 10-12 1 Continuouse weekb Charcoal Sample 8 Continuous Once per e i weekb Principal Gamma 1 x 10-11 Particulate Emittersd j Sample (1-131) i Continuous Once per Gross Alpha 1 x 10-11 8 month Composite i Particulate Sample Amendment No. 160 I

4 VYNPS t TABLE 4.8.2 (continued) i RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM i Lower Limit Minimum of Detection Sampling Analysis Type of Activity (LLD) Gaseous Release Type Frequency Frequency, Analysis (uCi/ml)a__, C. (continued) Continuouse Once per Sr-89, Sr-90 1 x 10-11 quarter Composite 4 Particulata i Sample 1 Continuous Noble Gas Noble Cases. 1 x 10-5 i Monitor Gross Beta I or Gamma j ] i } l i 9 l 1 Amendment No. 160a 3 4

1 1 4 VYNPS i j TABLE 4.8.2 ) (continued) TABLE NOTATION i n. See footnote a. of Table 4.8.1. b. Samples shall be changed at least once per 7 days and analysee shall be completed within 48 hours af ter removal j from samplers. Sampling shall also be performed at least once per 24 hours for to least 7 days following each shutdown, startup or thermal power change exceeding 25% of rated thermal power in one hour, and analyses shall i i be completed within 48 hours of changing the samples. When samples collected for 24 hours are analyzed, the { corresponding LLDs may be increased by a factor of 10. This requirement to sample at least once per 24 hours I for 7 days applies or.ly if: (1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has increased more than a factor of 3 and the resultant concentration is at least 1 x 10-1 uCi/al; and 1 l (2) the noble gas monitor shows that effluent activity has increased more than a factor of 3. c. Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding j 25% of rated thermal power per hour 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 the resultant concentration is at least 1 x i 10-1 uCi/al; and (2) the noble gas monitor shows that ef fluent activity has not increased more than a factor j of 3. i d. The principal gatama emitters for which the LLD specification will apply are exclusively the following I radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions, and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable. l together with the above nuclides, shall also be identified and reported. Nuclides which are below LLD for the 1 analyses should not be reported as being present at the LLD level for that nuclide, but as "not detected". When i unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Semiannual i Ef fluent Release Report. e. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by l each dose or dose rate calculation made in accordance with Specifications 3.8.E.1, 3.8.F.1 and 3.8.G.I. Amendment No. 160b i 4

VYNPS TABLE 4.8.2 (continued) TABLE NOTATION The gaseous waste sampling and analysis program does not explicitly require sampling and analysis at a specified f. LLD to determine the 1-133 release. Estimates of I-133 releases shall be determined by counting the weekly charcoal sample for I-133 (as well as 1-131) and assume a constant release rate for the release period. 1 t t .I 6 160c Amendment No.

VYNPS BASES: 3.8 RADIOACTIVE EFFLUENTS A. Liquid Effluents: Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site above background (at the point of discharge from the plant discharge into Connecticut River) will be less than the concentration levels specified in 10CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix 1,10CFR Part 50, to a member of the public, and (2) the limits of 10CFR Part 20.106 (e) to the population. The concentration limit for noble gases is basel upon the assumption that Xe-135 is the controlling radionuclide and its MPC in air (submersion) was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2. i B. Liquid Effluents: Dose l l I This specification is provided to implement the requirements of Sections II. A, III. A and IV. A of Appendix I, 10CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix 1. The requirements provide operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid ef fluents will be kept "as low as is reasonably achievable". The Surveillance Requirements implement the requirements in Section III. A of Appendix I, i.e., that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. In addition, 160d Amendment No.

1 i VYNPS 1 3.8 (Continued) i there is reasonable assurance that the operation of the facility will not result in 'radionuclide concentrations in potable drinking water that are in excess of the requirements of 40CFR 141. No drinking l water supplies drawn f rom the Connecticut River below the plant have been identified. The appropriate dose q equations for implementation through requirements of the Specification are described in the Vermont Yankee j Off-Site Dose Calculation Manual. The equations specified in the ODCM for calculating the doses due to the f actual release rates of radioactive materials in liquid effluents were developed from the methodology j provided in Regulatory Cuide 1.109, " Calculation of Annual Doses to !!an f rom Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix 1", Revision 1, October { 1977 and Regulatory Guide 1.113 " Estimating Aquatic Dispersion of Effluents f rom Accidental and Routine ] Reactor Releases for the Purpose of Implementing Appendix I", Revision 1, April 1977. C. Liquid Radvaste Treatment l The requirement that the appropriate portions of this system as indicated in the ODCM be used, when i specified, provides arsurance that the releases of radioactive materials in liquid effluents will be kept ) "as low as is reasonably achievable". This specification implements the requirements of 10CFR Part 50.36a and the design objective given in Section II.D of Appendix I to 10CFR Part 50. The specified limits j governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable f raction of the dose design objectives set forth in Section II.A of Appendix I,10CFR Part 50, for liquid effluents. l D. Liquid Holdup Tanks l l The tanks listed in this Specification include all outdoor tanks that contain radioactivity that are not i surrounded by liners, dikes, or walls capable of holding the tank contents, or that do not have tank l overflows and surrounding area drains connected to the liquid radwaste treatment system. Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less j than the limits of 10CFR Part 20, Appendix B, Table II, Column 2, at the nearest portable water, supply and j the nearest surface water supply in an unrestricted area. I I ( i Amendment No. 160e

VYNPS 3.8 (Continued) E. Gaseous Effluents: Dose Rate This specification is provided to ensure that the dose at any time at and beyond the site boundary from j gaseous ef fluents will be within the annual dose limits of 10CFR Part 20. The annual dose limits are l the doses associated with the concentrations of 10CFR Part 20, Appendix B, Table II, Column 1. These j limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of member (s) of the public either within or outside the site boundary, to annual i average concentrations exceeding the limits specified in Appendix B, Table II of 10CFR Part 20 [10CFR Part 20.106(b)]. For member (s) of the public who may at times be within the site boundary, the occupancy j of the individual w111 be sufficiently low to coepensate for any increase in the atmospheric diffusion j factor above that for the site boundary. The specified limits as determined by the methodology in the ODCM, restrict, at all times, the corresponding gamma and beta dose rates above background to a member of the public at or beyond the site boundary to (500) ares / year to the total body or to (3,000) area / year to the skin. 4 Specification 3.8.E.b also restricts, at all times, comparable with the length of the sampling periods of i i Table 4.8.2 the corresponding thyroid dose rate above background to an infant via the cow-milk-infant i pathway to 1500 mres/ year for the nearest cow to the plant. i F. Gaseous Effluents: Dose from Noble Gases d This specification is provided to iaplement the requirements of Sections II.B. III.A, and IV.A of 1 Appendix 1, 10CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section l II.B of Appendix 1. The requirements provide operating flexibility and at the same time implement the i guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in j gaseous ef fluents will be kept "as low as is reasonably achievable". The Surveillance Requirements i implement the requirements in Section III.A of Appendix I, i.e., that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of any member of the public through appropriate pathways is unlikely to be substantially underestimated. The { appropriate dose equations are specified in the ODCH for calculating the doses due to the actual, releases ~ of radioactive noble gases in gaseous effluents. The ODCN also provides for determining the air doses at j the site boundary based upon the historical average atmospheric conditions. i 1 Amandment No. 160f l

1 VYNPS 3.8 (Continued) The equations specified in the ODChi for calculating the doses due to the actual release rates of radioactive noble gases in gaseous ef fluents were developed from the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man f rom Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. G. Gaseous Effluents: Dose f rom Iodine-131. Iodine-133, Tritium, and Radionuclides in Particulate Form This specification is provided to implement the requirements of Sections II.C, III.A. and IV. A of 1 f Appendix I, 10CFR Part 50. The Limiting Condition for Operation are the guides set forth in Section II.C of Appendix 1. The requirements provide operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous i effluents will be kept "as low as is reasonably achievable". The Surveillance Requirements implement the l requiresents 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 equations specified in the ODCM for calculating the doses due to the actual release rates of the subject materials were also developed using 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 10CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric i Transport and Dispersion of Gaseous Effluents in Routine Releases f rom Light-Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for Iodine 131, i Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are { dependent on the existing radionuclide pathways to man, in areas at and beyond its site boundary. The pathways which were examined in the development of these specifications were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy arean where milk animals and meat producing animals graze 1 with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent, exposure of I man. l l 1 l Amendnent No. 160g t

i l VYNPS 3.8 (Continued) l H. Gaseous Radwaste Treatment The requirement that the appropriate portions of the Augmented Off-Gas (A0G) System be used whenever the i SJAE is in operation 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 10CFR Part 50.36a and the design objectives of Appendix 1 to 10CFR Part 50. 4 1 Ventilation Exhaust Treatment i The requirement that the A0G Building and Radwaste Building HEPA filtere be used when specified provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as i is reasonably achievable". This specification implements the requirements of 10CFR Part 50.36a and the i design objective of Appendix I to 10CFR Part 50. The requirements governing the use of the appropriate portions of the gaseous radwaste filter systems were specified by the NRC in NUREG-0473, Revision 2 ] (July 1970) as a suitable f raction of the guide set forth in Sections II.B and II.C of Appendix I,10CFR Part 50, for gaseous effluents. 1 l J. Explosive Gas Mixture 1

• ne hydrogen monitors are used to detect possible hydrogen buildups which could result in a possible I

hydrogen explosion. Automatic isolation of the off gas flow would prevent the hydrogen explosion and ] possible damage to the augmented off gas system. Maintaining the concentration of hydrogen below its flammability limit provides assurance that the releases of radioactive materials will be controlled. i j K. Steam Jet air Ejector (SJAE) ) Restricting the gross radioactivity release rate of gases f rom the main condenser SJAE provides reasonable I assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10CFR 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 10CFR Part 50. I I a i Amendment No. 160h 1 1 j

VYNPS 3.8 (Continued) L. Primary Containment (MARK I) This specification provides reasonable assurance that releases from containment purging / venting operations will be filtered through the Standby Gas Treatment System so that the annual dose limits of 10CFR Part 20 at the site boundary will not be exceeded. The dose objectives of Specification 3.8.G restrict i purge / venting operations when the Standby Gas Treatment System is not in use and gives reasonable assurance that all releases f rom the plant will be kept "as low as is reasonably achievable". M. Total Dose I This specification is provided to meet the dose limitations of 40CFR Part 190 that have been incorporated into 10CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Specific t Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix 1. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40CFR 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 dose to a member of the public to within the 40CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public is estimated to exceed the requirements of 40CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR Part 190 have not already been corrected), in accordance with the provisions of 40CFR Part 190.11 and 10CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10CFR Part 20, as addressed in Specification 3.8.A and 3.8.E. 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. N. Solid Radioactive Waste This specification implements the requirements of 10CFR Part 50.36a with respect to the handli,ng of solid radioactive waste (spent resin and filter sludges only). The establishment and implementation of a Process Control Program (PCP), provides the operational guidelines by which proper dewatering of filter medis and spent resins in preparation for off-site disposal is assured. Amendment No. 1601

l 1 ~ VYNPS 3.9 LIMITING CONDITIONS FOR OPERATION 4.9 SURVEILLANCE REQUIREMENTS 3.9 RADIOACTIVE EFFLUENT MONITORING SYSTEMS 4.9 RADIOACTIVE EFFLUElff MONITORING SYSTEMS Applicability Applicability Applies to the monitoring systems or programs Applies to the required surveillance of the which perform a surveillance, protective or monitoring systems or programs which perform a controlling function on the release of radioactive surveillance, protective or controlling function effluents f rom the plant and their identification on the release of radioactive ef fluents from the I in the environment. plant and their identification in the environment. Objective Objective l To assure the operability of the radioactive To specify the type and f requency of surveillance effluent monitoring systems and environmental to be applied to the radioactive effluent programs. monitoring system and environmental programs. j Specifications Specifications 1 A. Liquid Ef fluent Instrumentation A. Liquid Effluent Instrumentation 1. During periods of release through the 1. Each radioactive liquid effluent i monitored pathway, the radioactive monitoring instrumentation channel shall liquid effluent monitoring be tested and calibrated as indicated in instrumentation channel shall be Table 4.9.1. l operable in accordance with Table 3.9.1 with their alarm setpoints set to ensure that the limits of Specification 3.8. A.1 are not exceeded. J ? Amsndment No. 161 4 4 4

VYNPS 3.9 LIMITING CONDITIONS FOR OPERATION 4.9 SURVEILLANCE REQUIREMENTS a B. Caseous Effluent Instrumentation B. Gaseous Effluent Inctrumentation j 1. The gaseous process and effluent 1. Each gaseous process or effluent monitoring instrumentation channels monitoring instrumentation channel shall shall be operable in accordance with be tested and calibrated as indicated in Table 3.9.2 with their alare/ trip Table 4.9.2. I setpoints set to ensure that the limits i of Specifications 3.8.E.1.a. 3.8.J.1, and 3.8.K.1 are not exceeded. C. Radiological Environmental Monitoring Program C. Radiological Environmental Monitoring Program l 1. The radiological environmental 1. The radiological environmental monitoring program shall be conducted as monitoring samples shall be collected specified in Table 3.9.3. pursuant to Table 3.9.3 from the locations given in the ODCM and shall be i analyzed pursuant to the requirements of j Table 3.9.3 and the detection capabilities required by Table 4.9.3. } l 1 l ) Assadment No. 161a i i } i

VYNPS ~ 3.9 LIMITING CONDITIONS FOR OPERATION 4.9 SURVEILLANCE REQUIREMENTS D. Land Use Census D. Land Use Census 1. A land use census shall be conducted to 1. The land use census shall be conducted identify the location of the nearest at least once per year between the dates milk animal and the nearest residence in of June 1 and October 1 by either a each of the 16 meteorological sectors door-to-door survey, serial survey, or within a distance of five miles. The by consulting local agricultural survey shall also identify the nearest authorities. The results of the land milk animal (within 3 miles of the use census shall be included in the plant) to the point of predicted highest annual Radiological Environmental annual average D/Q value in each of the Surveillance Report pursuant to three major meteorological sectors due Specification 6.7.C.3. to elevated releases from the plant stack. 2. With a land use census identifying one I or more locations which yield a calculated dose or dose commitment (via the same exposure pathway) at least 20 percent greater than at a location f rom which samples are currently being obtained in accordance with Specification 3.9.C.1, add the new location (s) to the radiological I l Amendment No. 162 i l i i

VYNPS ~ 3.9 LIMITING CONDITIONS FOR OPERATION 4.9 SURVEILLANCE REQUIREMENTS environmental monitoring program within 30 days if permission f rom the owner to collect samples can be obtained, and sufficient sample volume is available, i The sampling location (s), excluding the control station location, having the lowest calculated dose or dose I commitment (vin the same exposure pathway) may be deleted from.this monitoring program af ter October 31 of the year in which this land use census was conducted. E. Intercomparison Program E. Intercomparison Program 4 1. Analyses shall be performed on 1. A summary of the results of analyses i referenced radioactive materials performed as part of the above required supplied as part of an Intercomparison Intercomparison Program shall be Program which has been approved by NRC. . included in the Annual Radiological Environmental Surveillance Report. The identification of the NRC approved Intercomparison Program which is being participated in shall be stated in the ODCM. l l r i i j l Arendment No. 163 i

I l l VYNPS d TABLE 3.9.1 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 1 Minimum i Channels Operable Notes 1. Gross Radioactivity Monitors not Providing Automatic Termination of Release l a. Liquid Radwaste Discharge 1* 1,4,5 <] Monitor j j b. Service Water Discharge 1 2,4,5 Monitor j 2. Flow Rate Measurement Devices 1 I a. Liquid Radwaste Discharge 1* 3,4 I Flow Rate Monitor i I l

• During releases via this pathway.

I l 1 l Amendment No. 164 t l }

i VYNPS TABLE 3.9.1 I (continued) TABLE NOTATION With the number of channels operable less than required by the minimum channels operable requirement, NOTE 1 effluent releases may continue provided that prior to initiating a celease: i-At least two independent samples are analyzed in accordance with Specification 4.8.A.1, and a. b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving, i Otherwise, suspend release of radioactive effluents via this pathway. NOTE 2 - With the number of channels operable less than required by the minimum channels operable requirement, ef fluent releases via this pathway may continue provided that, at least once per 24 hours, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 microcurie /al. NOTE 3 - With the number of channels operable less than required by the minimum channels operable requirement, l ef fluent releasea via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves may be used to estimate flow. I NOTE 4 - With the number of channels operable less than required by the minimum channels operable requirement, exert I reasonable efforts to return the instrument (s) to operable status prior to the next release. i The alarm setpoints of these channels shall be determined and adjusted in accordance with the methodology NOTE 5 and

rameters in the Off-Site Dose Calculation Manual (ODCM). With a radioactive liquid effluent monitoring instrumentation channel alarm setpoint less conservative than a value which will ensure that the limits of e.8. A.1 are met during periods of release, immediately take action to suspend the release of i

I radioactive liquid ef fluents monitored by the af fected channel or declare the channel inoperable; or change l the setpoint so it is acceptably conservative. l Amendment No. 165

I i VYNPS TABLE 3.9.2 l CASEOUS EFFLUENT MONITORING INSTRUMENTATION + } i Inst rument Minteum Channels Operable Notes i 1. Steam Jet Air Ejector (SJAE) 1 7,8,9 j I a. Noble Gas Activity Monitor t 2. Augmented Of f-Gas System a. Noble Gas Activity Monitor Between the Charcoal Bed 1 2,5,6,7 System and the Plant Stack (Providing Alara and Automatic Termination of Release) 1 i b. Flow Rate Monitor 1 1, 5, 6 ) I c. Hydrogen Monitor 1 3,5,6 3. Plant Stack I a. Noble Gas Activity Monitor 1 2,5,7 i j b. Iodine Sampler Cartridge 1 4,5 c. Particulate Sampler Filter 1 4,5 I i d. Sampler Flow Integrator 1 1,5 i e. Stack Flow Rate Monitor 1 1,5 i Arendment No. 166 j i

W VYNPS TABLE 3.9.2 l (continued) I TABLE NOTATION l l j NOTE 1 - With the number of channels operable less than required by the minimum channels operable requirement, j effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 l hours. NOTE 2 With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via this pathway may continue for a period of up to 7 days provided that at least one of the stack monitoring systems is operable and of f gas system temperature and pressure are measured continuously. NOTE 3 - With the number of channels operable less than required by the minimum channels operable requirement, operation of the A0G System may continue provided gas samples are collected at least once per 24 hours and analyzed within the following 4 hours, or an orderly transfer of the off gas effluents f rom the operating recombiner to the standby recombiner shall be made. NOTE 4 - With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment. NOTE 5 - With the number of channels operable less than required by the minimum channels operable requirement, exert reasonable efforts to return the instrument (s) to operable status within 30 days. NOTE 6 - During releases via this pathway. NOTE 7 - The alare/ trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Off-Site Dose Calculation Manual (ODCM). With a gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of 3.8.E.1.a and 3.8.K.1 are met, immediately take actions to suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative. I I Amendment No. 167 I 1 1

i l VYNPS I TABLE 3.9.2 (continued) TABLE NOTATION Nsta 8 - Minimum channels operable required only during operation of the Steam Jet Air Ejector. With the number of channels operable less than required by the minimum channels operable requirement, gases Nste 9 f rom the SJAE may be released to the environment for up to 72 hours provided: i 1. The A0G system is not bypassed; and 2. The A0G system noble gas activity monitor is operable. i 4 i i I I i Amendment No. 168 1 E

e O dp+ VYNPS O TABLE 3.9.3 RADIOLOGICAL ENVIRONNENTAL NONITORING PROCRAN O Exposure Fathway and/or Sample Number of Sample Locations

• Sampling and Collection Frequency Type and Frequency of Analysis 1.

AIR 50RMc e a. Radiciodine and Samples from 5 locations: Antinuous operation of sampler Radiotodine canister: Analyse Particulates with saaple collection semisonthly each sample for 1-131. e 3 samples f rom close to the 3 or more f requently as required by 3 site boundary locations in dust loading or plant effluent Particulate sampler Cross beta h l different sectors, of the highest releases. radioactivity analysis on each emple e 1 calculated annual average ground following filter change.c level D/Q. Composite (by location) for games o isotopic at least once per quarter. I sample fros the vicinity of a community having the highest calculated annual average ground level D/Q. I sample from a control location, e as for example 15-30 km distant and in the least prevalent wind j direction. i i j ~ 4 4 4 1 I Amendment No. 169 \\ o e 4 Y 1 S l i l

1 A } VYNFS S u e TABLE 3.9.3 S (continued) RADIOLOGICAL ENVIRONNENTAL NONITORING PROGRAN S i i Esposure Pathway e and/or Sample Number of Sample Locations, Sampling and Collection Frequency Type and Frequency of Analysis 2. DIREC* RADIAT10Nb 40 routine monitoring stations Quarterly. Camma dose, at least once per quarter. e as follows: Incident response TLDs in the outer sonitoring locations, de-dose only e quarterly unless gaieous release LCO was exceeded in period. i 16 incident response stations (one in each meteorlogical sector) within a range of 0 to 4 kmR; g i 16 incident response stations (one in each meteorlegical sector) g within a range of 2 to 8 kmE; the balance of the stations to be 9 placed in special interest areas ] and control station areas. i I e e i ) 9 Amendment No. 9 I a .i I

VYMPS TABLE 3.9.3 (continued) RADIOLOCICAL ENVIROINENTAL MONITORING pt0 CRAM Esposure Fathway and/or Sample Number of Sample locatione, Samplina and Collection Frequency Type and Freemency of Aestyeis 3. WATERSORNE d of a. Surface

• 1 eampia upstream.

Monthly grab sample. Causa footopic seslyste each sample. Tritten analysis of 1 esople downetreme. Composite saeple coil ted over composite sample at least once per a period of one month quarter. b. Ground 1 sample f rom within S km Quarterly. Canna lectopfed ad tritium distance. analyses of each sample. I sample from a control location. Quarterly. c. Sediment free 1 eample from downstraea area Santennually. Cosma footopic ana! -ted of Shoreline with existing or potential each eemple. recreational value. j 1 semple f rom north store dra*n As specified in outfall. the OPOt. 4 ) 4 Amendment No. / 171 I 4

m. 4 e A VYNFS e TAB 1E 3.9.3 [ continued) e RADIOLOGICAL ENVIRONENTAL MON 17051NC PROGRAN e Esposure Pathway and/or Sample Number of Sample Locatione, Sampling and Collection Frequency Type and Frequency of Analysis a g 4. INGESTION e a. Milk Samples f rom n'.1 king antaale in Seeleonthly if allking animale Canna isotopicd and 1-131 analysis 3 locations within 5 km distance are identified on pasture; at of each sampls. a having the highest dose potential. least once per month at other g 1 If there are less than 3 primary times. f locatione available then 1 or more secondary sample from allking i antaals in each of 3 areas between 5 to 8 km distance where doses are calculated to be greater than 1 aree per year. 1 sample f roe allking antaals in O a control location. b. Floh 1 sample of two recreationally Seelannually. Cases isotopic analysisd on etable O leportant species in vicinity of portions. plant discharge area. 9 1 sample (preferably of same species) in areas not influenced by plant discharge. O c. Vegetation 1 grase sample at each air Quarterly when available. Cassa isotopic analysted of each sampling station. esepte. 1 silage aseple at each allk At time of harvest. Comma isotopic analysted I of each sampling station (as ave 11able). sample. Amendment No. 172 e WP w a'

1 vrNpS I i TABLE 3.9.3 (continued) TABLE NOTATION j ) o Specific parameters of distance and direction sector from the centerline of the reactor and additional descriptions where pertinent, shall be provided for each and every sample location in Table 3.9.3 in a table and figure (s) in the ODCN. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous l conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every reasonable effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the annus1 Radiological Enviromental Surveillance Report pursuant to Specification 6.7.C.3. It is j recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of j i choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological j cavironmental monitoring program. In lieu of a Licensee Event Report and pursuant to Specification 6.7.C.1, i identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining j replacement samples in the next Sesiannual Radioactive Effluent Release Report and also include in the report a l { revised figure (s) and table for the ODCM reflecting the new location (s). I l One or more instruments, such as a pressurized ion chsaber, for measuring and recording dose rate continuously b j may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a Thermoluminescent Dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered l ss two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 stations is not an absolute number. The frequency of analysis or readout for TLD systems will depend upon the i characteristics of the specific system used and should be selected to obtain optinua dose information with minimal fading. 3 l c Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling j to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual pamples. i Amendment No. 172a f

. =. VYNPS TABLE 3.9.3 l (continued) TABLE NOTATION i, j d Camma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be j attributable to the effluents f rom the facility. l e The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream" j cample shall be taken in an area beyond but near the mixing zone. f Composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample. 4 8 Each meteorological sector shall have an established " inner" and an " outer" monitoring location based on ease of j recovery (i.e., response time) and year-round accessibility. j h Sample collection will be performed weekly whenever the main plant stack effluent release rate of 1-131, as j dstermined by the sampling and analysis program of Table 4.8.2, is equal to or greater than 1 x 10-1 uC1/sec. Sample collection will revert back to semimonthly no sooner than at least two weeks af ter the plant stack effluent release rate of 1-131 falls and remains below 1 x 10-1 uCi/sec. i j 1 l i j l J Amendment No. 172b I e i i

l 1 1 1 1 VYNFS i i TABLE 3.9.4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONNENTAL SAMPLES (a) Reporting Levels i i Water Airborne Particulate Fish Milk Vegetation l Analysis (pC1/1) or Gases (pC1/m3) (pCi/Kg, wet) (pC1/1) (pci/Kg, wet) Mb) H-3 2 x 10 3 4 Mn-54 1 x 10 3 x 10 2 4 Fe-59 4 x 10 1 x 10 3 4 Co-58 1 x 10 3 x 10 Co-60 3 x 10 1 x 10' 2 Zn-65 3 x 10 2 x 10 1 2 Zr-Nb-95 4 x 10 2 I-131 0.9 3 1 x 10 3 3 Co-134 30 10 1 x 10 60 1 x 10 3 3 Cs-137 50 20 2 x 10 70 2 x 10 2 2 ) Ba-La-140 2 x 10 3 x 10 (a) Reporting levels may be averaged over a calendar quarter. When more than one of the radionuclides in Table 3.9.4 4 are detected in the sampling medium, the unique reporting requirements are not exercised if the following condition holds: concentration (1) concentration (2) .0. { reporting level (1) reporting level (2) +... I i When radionuclides other than those in Table 3.9.4 are detected and are the result of plant effluents, the i potential annual dose to a member of the public must be less than or equal to the calendar year limits of j Specifications 3.8.B. 3.8.E and 3.8.F. 4 pCi/1 may be l (b) Reporting level for drinking water },athways. For nondrinking water pathways, a value of 3 x 10 used. l Amendment No. 172c i

i d VYNPS i ) ~ TABLE 4.9.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l Inst rument Instrument Source Instrument Functionni i Instrument Check Check Calibration Test 1 I 1. Gross Radioactivity Monitors not Providing Automatic Termination of Release a. Liquid Radwaste Discharge Monitor (3) Once each Prior to Once each Once each j day

• each release, 18 months quarter (2)

I but no more (1) i than once each month l b. Service Water Discharge Monitor (3) One each once each once each once each I day month 18 months quarter (2) (1) 2. Flow Rate Measurement Devices i a. Liquid Radwaste Discharge Flow Rate Monitor Once each Not Not Once each day

• Applicable Applicable quarter *
• During releases via this pathway.

i ) 1 l Amendment No. 172d i i v

VYNPS TABLE 4.9.1 (continued) TABLE _ NOTATION (1) The Instrument Calibration for radioactivity measurement instrumentation shall include the use of a known (traceable to National Bureau of Standards) liquid radioactive source positioned in a reproducible geometry with respect to the sensor. These standards shall permit calibrating the system over its normal operating range of a energy and rate.

l (2)

The Instrument Functional Test shall also demonstrate the Control Room alarm annunciation occurs if any of the following conditions exists,: i i i (a) Instrument f.ndicate measured levels above the alarm setpoint. (b) Circuit failure. l j (c) Instrument indicates a downscale failure. i (d) Instrument controls not set in operate mode. 1 4 (3) The alarm setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Off-Site Dose Calculation Manual (ODCM). 1 i l j l l Amendment No. 172e 9

2 VYNPS i l TABLE 4.9.2 CASEOUS EFFLUENT MONITORING INSTRUMENTATION SUR*MILLANCE REQUIREMElffS 1 i Inst rument j Instrument Source Inst rument Functional Instrument Check Check Calibration Test i 1. Steam Jet Air Ejector (SJAE) i a. Noble Gas Activity Monitor Once each Once each Once each Once each I day ** month 18 months quarter (2) l (3) 2. Augmented Off gas System l a. Noble Gas Activity Monitor Once each Once each Once each Once each day

• month 18 months quarter (1)

[ (3) l b. Flow Rate Monitor Once each Not Once each Not day

• Applicable 18 months Applicable l

c. Hydrogen Monitor Once each Not Once each once each ] day

• Applicable quarter (4) month t

i i 3. Plant Stack i a. Noble Gas Activity Monitor Once each Once each Once each Once each ) day month 18 months quarter (2) (3) i l b. Sampler Flow Integrator once each Not Once each Not l l week Applicable 18 months Applicable l c. System Flow Rate Monitor Once each Not Not Not day Applicable Applicable Applicable During releases via this pathway. During operation of main condenser SJAE. l Amendment No. 172f 4

r VYNPS TABLE 4.9.2 (continued) TABLE NOTATION (1) The Instrument Functional Test shall also demonstrate that automatic isolation of this pathway and the Control Room alarm annunciation occurs if any of the following conditions exists: (a) Instrument indicate measured levels above the alara setpoint. 4 (b) Circuit failure. (c) Instrument indicates a downscale failure. (d) Instrument controls not set in operate mode. l J (2) The Instrument Functional Test shall also demonstrate that Control Room alarm annunciation occurs when any of the following conditions exist: l (a) Instrument indicates measured levels above the alara setpoint. (b) Circuit failure. (c) Instrument indicates a downscale failure. l (d) Instrument controls are not set in operate mode. (3) The Instrument Calibration for radioactivity measurement instrumentation shall include the use of a known (traceable to Nation.a1 Bureau of Standards) radioactive source positioned in a reproducible geometry with respect to the sensor. These standards should permit calibrating the system over its normal operating range cf j rate capabilities. (4) The Instrument Calibration shall include the use of standard gas samples (high range and low range) containing I suitable concentrations, hydrogen balance nitrogen, for the detection range of interest per Specification i 3.8.J.1. l Amendment No. 172g ll I

VYNPS 2 TABLE 4.9.3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (a)(c)(f) Analysis (d) Water Airborne Particulate Fish Milk Vegetation Sediment 3 (pci/1) or Gas (pCi/m ) ',pci/Kg, we t) (pC1/1) (pC1/Kg, wet) (pCi/Kg, dry) Grass beta 4 0.01 H-3 3000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15(b) 1-131 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15(b)(e) 15(b)(e) i 4 Amendment No. 172h i

i VYNPS 4 TABLE 4.9.3 (continued) TABLE NOTATION i See Footnote (a) of Table 4.8.1. j (c) (b) Parent only. i If the meas 2 red concentration minus the 5 sigma counting statistics is found to exceed the specified LLD, (c) the sample does not have to be analyzed to meet the specified LLD. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, (d) together with those of the listed nuclides, shall also be analyzed and reported in the Annual Radiological i Environmental Surveillance Report pursuant to Specification 6.7.C.3. (e) The Ba-140 LLD and concentration can be determined by the analysis of its short-lived daughter product La-140 subsequent to an 8 day period following collection. The calculation shall be predicted on the i normal ingrowth equations for a parent-daughter situation and the assumption that any unsupported La-140 in the sample would have decayed to an insignificant amount (at least 3.6 percent of its original value). The ingrowth equations will assume that the supported La-140 activity at the time of collection is zero. 1 (f) Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD, but I as "not detected". For purposes of averaging, the LLD will be assumed to be zero. l l i J I Amendment No. 1721 1

i i VYNPS f BASES: 1 3.9 RADIOACTIVE EFFLUENT MONITORING SYSTEMS l A. Liquid Effluent Instrumentation 1 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alara setpoints for these instruments are to ensure that the alarm will occur prior to j exceeding the limits of 10CFR Part 20. Automatic isolation function is not provided on the liquid radwaste discharge line due to the infrequent nature of batch, discrete volume, liquid discharges (on the order of once per year or less), and the administrative controls provided to ensure that conservative discharge flow rates / dilution flows are set 1 such that the probability of exceeding the 10CFR Part 20 concentration limits are low, and the potential off site dose consequences are also low. i B. Gaseous Effluent Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous ef fluents during actual or potential releases of gaseous effluents. The alare/ trip setpoints for these instruments are provided to ensure that the alare/ trip will 1 occur prior to exceeding the limits. of 10CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas ] hoidup system. i i i I i I l Amendment No. 172J i i I

VYNPS 3.9 (Continued) C. Radiological gnvironmental Monitoring Program The radiological 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 member (s) of the public resulting f rom the station operation. This monitoring program implements Section IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby 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 modeling of the environmental exposure pathways. Ten years of plant operation, including the years prior to the implementation of the Augmented Off-Gas Systen, have amply demonstrated via routine effluent and environmental reports that plant effluent measurements and modeling of environmental pathways are adequately conservative. In all cases, environmental sample results have been two to three orders of magnitude less than expected by the model employed, thereby representing small percentages of the ALARA and environmental reporting levels. This radiological environmental monitoring program has therefore been significantly modified as provided for by Regulatory Guides 4.3 (C.2.a) and 4.1 (C.2.b), Revision 1, April 1975. Specifically..the air particulate and radioiodine air sampling periods have been increased to semimonthly, based on plant effluent and environmental ai sampling data for the previous ten years of operation. An I-131 release rate trigger valueof1x10-{uCi/secfromtheplantstackwillrequirethatairsamplecollectionbeincreagedto The 1 x 10~1 uCi/sec I-131 value corresponds to the LLD air concentration of 0.07 pCi/m at weekly. theagximumpredictedairmonitoringstation,whichexhibitsamaximumquarterlyX/Qvalueof2x10-7 sec/m. A factor of 3.5 below the LLD value has also been included in the stack release rate value to account for meteorological fluctuations in X/Q. Due to the large local population of cows and the ready availability of milk samples, food product sampling has been eliminated f rom the program in lieu of milk sampling. Since milking cows in the area spend very little time on pasture, silage and grass sampling have been instituted as an indicator of radionuclide deposition. The detection capabilities required by Table 4.9.3 are considered optimum for routins environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as,a before-the-f act limit representing the capability of a measurement system and not as an af ter-the-fact limit for a particular measurement. This does not preclude the calculation of an af ter-the-fact LLD for a particular measurement based upon the actual parameters for the sample in question. Amendment No. 172k

a i' VYNPS 3.9 (Continued) D. Land Use Census i i This specification is provided to ensure that changes in the use of areas at and beyond the site boundaries are identified and that modifications to the monitoring program are made if reqaired by the results of this census. This census natisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. The requirement of a garden census has been eliminated along with the food product monitoring requirement due to the substantial and widespread occurrence of dairy farming in the surrounding area which dominates the food uptake pathway. The addition of new sampling locations to Specification 3.9.C, based on the land use census, is limited to 3 those locations which yield a calculated dose or dose commitment greater than 20 percent of the cciculated dose or dose commitment at any location currently being sampled. This eliminates the unnecessary changing of the environmental radiation monitoring program for new locations which, within the accuracy of the calculation, contributes essentially the same to the dose or dose commitment as the location already sampled. The substitution of a new sampling point for one already sampled when the calculated difference } in dose is less than 20 percent, would not be expected to result in a significant increase in the ability to detect plant effluent related nuclides. E. Intercomparison Prograa j The requirement for participation in an intercomparison program is provided to ensure that independent I checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a 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. 1 t l i i i I Amendment No. 1721 i i ] i l E

i l 1 VYNPS 3.11 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS C. Minimum Critical Power Ratio (MCPR) 1. During steady-state power operation, the MCPR Operating Limit shall be equal or greater than the values shown on Table 3.11-2. For core flows other than rated MCPR, the Operating MCPR Limit shall be the above.value multiplied by Kf where Kf is given by Figure 3.11-2. If at any time during steady-state operation it is determined by normal surveillance that the limiting value for MCPR is being exceeded, action shall be initiated within 15 minutes to restore operation to within i the prescribed limits. If the steady state MCPR is not returned to within the prescribed limits within two (2) hours, the reactor power shall be brought to shutdown condition within 36 hours. Surveillance and corresponding action shall continue until reacter operation is within the prescribed limits. l 1 1

l 1

I i a ] Amendment No. 47 180c

VYNPS B sent 3.11C Minimum Critical Power Ratio (MCPR) Operating Limit MCPR 1. The MCPR Operating Limit is a cycle-dependent parameter which can be determined for a number of different combinations of operating modes, initial conditions, and cycle exposures in order to provide reasonable assurance against exceeding the Fuel Cladding Integrity Safety Limit (FCISL) { for potential abnormal occurrences. The MCPR operating limits are presented in Appendix A of the l current cycle's Core Performance Analysis report. l l 4 i i 1 e J i J ) Amendment No. 41, 70 180h 1 i

VYNPS 5.0 DESIGN FEATURES 5.1 Site The station is located on the property on the went bank of the Connecticut River in the Town of Vernon, Vermont, which the Vermont Yankee Nuclear Power Corporation either owns or to which it has perpetual rights and easements. The site plan showiag the exclusion area boundary, boundary for gaseous ef fluents and boundary for liquid effluents is on Figure 2.2-5 in the FSAR. The minimum distance to the boundary of the excluaion area as defined in 10CFR100.3 is 910 feet. No part of the site shall be sold or leased end no structure shall be located on the site except stractures owned by the Vermont Yankee Nuclear Power Corporation or related utility companies and used in conjunction d with normal utility operations. 5.2 Reactor j A. The core shall consist of not more than 368 fuel assemblies. B. The reactor core shall contain 89 cruciform-shaped control rods. The control material shall be boron carbide powder (B C). 4 5.3 Reactor Vessel The reactor vessel shall be as described in Table 4.2-3 of the FSAR. The applicable design codes shall be as described in subsection 4.2 of the FSAR. 5.4 Containment A. The principal design parameters and applicable design codes for the primary containment shall be as j given in Table 5.2.1 of the FSAR. B. The secondary containment shall be as described in subsection 5.3 of the FSAR and the applicable codes shall be as described in Section 12.0 of the FSAR. l C. Penetrations to the primary containment and piping passing through such penetrations shall be designed 1 in accordance with standards set forth in subsection 5.2 of the FSAR. Amendment No. 21 188 I i 1 1

VYNPS d. Power Plant Design i e. Reactor Engineering l f. Radiation Safety 1 l g. Safety Analysis 1 J h. Instrumentation and Control 1. Metallurgy 3. Meeting Frequency: Semi-annually and as required on call of the Chairman. 4. Quo rum: Chairman or Vice Chairman plus four members or designated alternates. 5. Responsibilities: a. Review proposed changes to the operating license including Technical Specifications. b. Review minutes of meetings of the Plant Operation Review Committee to determine if matters j considered by that committee involve unreviewed or unresolved safety questions. ) Review the safety evaluations for changes to equipment or systems completed under the c. ] provisions of Section 50.59 10 CFR to verify that such actions did not com titute an unreviewed safety question. d. Periodic audits of implementing procedures, shall be performed under cognizance of the j Committee. Included in these audits, but not limited to, are the following specific activities: 1 1. plant operations; 4 2 11. facility fire protection program; i Amendment No. 66, 70, 197

i P VYNPS l iii. the radiological environmental monitoring program and the results thereof at least once per 12 months; s iv. the Off-Site Dose Calculation Manual and implementing procedures at least once per 24 months; v. the Process Control Program and implementing procedures for processing and packaging of radioactive waste at least once per 24 months; vi. the performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974, and Regulatory Guide 4.1, i Revision 1, April 1975, at least once per 12 months. Investigate all reported instances of violations of Technical Specifications, reporting e. l findings and recommendations to prevent recurrence to the Manager of Operations. I f. Perform special reviews and investigations and render reports thereon as requested by the Manager of Operations. g. Review proposed tests and experiments and results thereof when applicable. h. Review abnormal performance of plant equipment and anomalies. I j 1. Review unusual occurrences and incidents which are reportable under the provisions of 10 l CFR Part 20 and 10 CFR Part 50. j. Review of occurrences if safety limits are exceeded. l 6. Authority i Review proposed changes to the operating license including Technical Specifications and j a. revised bases for submittal to the NRC. i b. Review proposed changes or modifications to plant systems or equipment, provided that such l changes or modifications do not involve unreviewed safety questions. i i Amendment No. 66, 70, 198 I

I VYNPS c. Recommend to the Manager of Operations appropriate action to prevent recurrence of any violations of Technical Specifications. d. Evaluate actions taken by the Plant Operation Review Committee. 7. Records Minutes of all meetings of this committee shall be recorded. Copies of the minutes shall be forwarded to the Manager of Operations, the Vice President - Operations, the Plant Manager and i any others that the Chairman may designate, i l i ) j 1 t ~ l 1 i j Amendment No. 198a l l l l

b VYNPS 4 6.5 Plant Operating Procedures A. Detailed written procedures, involving both nuclear and non nuclear safety, including applicable 3 check off lists and instructions, covering areas listed below shall be prepared and approved, t All procedures shall be adhered to. 1. Normal startup, operation and shutdown of systems and components of the facility. 2. Refueling operations. 3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, suspected Primary System leaks and abnormal reactivity changes. 4. Emergency conditions involving potential or actual release of radioactivity. 5. Preventive and corrective maintenance operations which could have an effect on the safety of the reactor. j 6. Surveillance and testing requirements. i 7. Fire protection program implementation including minimum fire brigade requirements and training. The training program shall meet or exceed the requirements of Section 27 of the NFPA Code 1976. l Training sessions will be scheduled as plant operations permit but will be completed in specified i subjects annually. Initial fire brigade training shall be completed by March 13, 1978. 8. Process Control Program in plant implementation. j l 9. Off-Site Dose Calculation Manual in plant implementation. 3 l l i i Amendment No. 36, 41, 43, 200 l l 4

e 1 VYNPS B. Radiation control standards and procedures shall be prepared, approved and maintained and made i available to all station personnel. These procedures shall show permissible radiation exposure, and shall be consistent with the requirements of 10 CFR Part 20. This radiation protection program shall be organized to meet the requirements of 10 CFR Part 20.' I 1. Paragraph 20.203, " Caution signs, labels, signals and controls". In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2), each high radiation area in which the intensity of radiation is 1000 mres/hr or less shall be barricaded and conspicuously posted as a i high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation i Work Permit.* Any individual or group of individuals permitted to enter such areas shall be provided with one or more of the following: ) a. A radiation monitoring device which continuously indicates the radiation dose rate in the area. b. A radiation monitoring device which continuously integrates the radiation dose rate in the l area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made af ter the dose rate levels in the area have been established j and personnel have been made knowledgeable of them. u l c. A Health Physics qualified individual (i.e., qualified in radiation protection procedures) i l with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and who will perform periodic radiation surveillance at the f requency specified in the RWP. The surveillance f requency will be established by the Plant Health Physicist. l The above procedure shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 ares /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shif t Supervisor on duty and/or the Plant Health Physicist. i l

• Hralth Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, providing they are following plant radiation protection procedures for entry into high rediation areas.

j Amendment No. 36, 42, 201 1 i

~ VYNPS 7. Records of transient or operational cycling for those plant components that have been designed to l operate safely for a limited number of transients or operational cycles. 8. Records of inservice inspections of the reactor coolant system. 9. Minutes of meetings of the Plant Operation Review Committee and the Nuclear Safety Audit and Review Board. i 10. Records for Environsental Qualification which are covered under the provisions of paragraph 6.9. 11. Records of analysis required by the Radiological Environmental Monitoring Program. 4 i l 1 l 1 1 1 Amendment No. M. Order dated October 24, 1980 207a

VYNPS 6.7 Reportina Requirements In addition to the applicable reporting requirements of Title 10 Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of l Inspection and Enforcement unless otherwise noted. I A. Routine Reports i t 1. Startup Report A summary report of plant startup and power escalation testing shall be submitted following i (1) receipt of an operating license, (2) amendment to the license involving a planned increase in l power level, (3) installation of fuel that has a different design or has been manufactured by a i 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 conditions or characteristics obtained during the test program and a comparison of i these values with design predictions and specifications. Any corrective actions that were i required to obtain satisfactory operation shs11 also be described. Any additional specific i details required in license conditions based on other commitments shall be included in this report. Startup reports shall be submitted within (1) 90 days following completion of the startup test i program, (2) 90 days following resumption of commencement of commercisi power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e., initial criticality, completion of startup test program, and I resumption or commencement of commercia.1 power operation), supplementary reports shall be submitted at least every three months until all three events have been completed. 4 l l Amendment No. 42 208 i 4 i l l 1 1

VYNPS ~ 2. Annual Report An annual report covering the previous calendar year shall be submitted prior to March 1 of each. year.. The annual report shall include a tabulation on an annemi basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 area /yr and their associated man-rem exposure according to work and job functions,1/ e.g., reactor j operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty I functions may he estimates based on pocket dosimeter, TLD or film badge measurement. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body done received f rom external sources shall be assigned to specific major work functions. 3. Monthly operatina Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Management Information and Program Control, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the appropriate Regional Of fice, to arrive no later than the fif teenth of each month following the calendar month covered by the report. These reports shall include a narrative summary of operating experience during the report period which describes the operation of the facility and any major safety-related maintenance. t B. Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of In case of corrected or supplemental reports, a licensee event report shall be completed, occurrence. and reference shall be made to the original report date. Events involving systems or components described in Sections 3/4.8.B, 3/4.8.C, 3/4.8.F. 3/4.8.C, 3/4.8.H, 3/4.8.1, 3/4.8.M, 3/4.9.C, 3/4.9.D. 3/4.9.E, Table 3.9.1-note 5. Table 3.9.2-note 7 and 3/4.13 do not require reportire under the provision of this section. Such events will be reported as required in Section 6.7.C.2 or 6.7.C.3 as indicated below. The reporting provisions of this section are not applicable to Sections 3/4.8.A. 3/4.8.D, 3/4.8.E, 3/4.8.N, 3/4.9. A, and 3/4.9.B. 1/ This tabulation supplements the requirements of 20.407 of 10CFR Part 20. 209 l Amendment No. 42,

1 VYNPS i 1. Prompt Notification With Written Follow-Up j The types of events listed below shall be reported as expeditiously as possible, but within 24 l. hours by telephone and confirmed by telegraph, sailgram, or facsimile transmission to the Director of the appropriate Regional Of fice, or his designate, no later than the first working i day following the event, with a written follow up report within two weeks. The written follow-up report shall include, as a minimus, a completed copy of a licensee event report form. 4 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. a. Failure of the Reactor Protection System or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter I reaches the setpoint specified as the limiting safety system setting in the Technical specifications or failure to complete the required protective function. 4 1 i Note: Instrument drif t discovered as a result of testin6 need not be reported under this j iten but may be reportable under Items 1.e, 1.f or 2.a below. b. Operation of the unit or affected systems when any perameter or operation subject to a limiting cordition is less conservative than the least conservative aspect of the limiting condition for operation established in the Technical Specifications. I j Note: If specified action is taken when a system is found to be operating between the most j conservative and the least conservative aspects of a limiting ' condition for 1 operation listed in the Technical Specifications, the limiting condition for operation is not considered to have been violated and need not be reported under this ites, but it may be reportable under Item 2.b below. ) c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary or primary containment. Note: Leakage of valve packing or gaskets within the limits for identified leakage set 3 forth in Technical Specifications need not be reported under this ites. i i I l Amendment No. 28, 210 l l i

i VYNPS i l d. Reactivity anomalies, involving disagreement with the predicted value cf reactivity balance under steady-state conditions during power operation, greater than or equal to 11 k/k; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the Technical Specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, of suberitical, an unplanned reactivity insertion of more than 0.5% ak/k or occurrence of any unplanned criticality. e. Failure or malfunction of one or more components which prevents or could prevent, by } itself, the fulfillment of the functional requirements of system (s) used to cope with j sccidents analyzed in the SAR. I f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents l analyzed in the SAR. ] Note: For items i.e and 1.f, reduced redundancy that does not result in a loss of system function need not be reported under this section but may be reportable under Items 2.b and 2.c below. g. Conditions arising f rom 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. j h. 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 l Specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses. i 1. Performance of structures, systems or components that requires remedial action or i corrective measures to prevent operation in a manner less conservative than assumed in the j accident analyses in the safety analysis report or Technical Specifications bases; or discovery during plant life of conditions not specifically considered in the safety l analysis report or Technical Specifications that require remedisl action or corrective l measures to prevent the existence of development of an unsafe condition. f Note: This item is intended to provide for reporting of potentially generic problems. I j Aoendment No. 28, 211 l l l W T rv k

VYNPS 2. 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 30 days of occurrence of the event. The 1 written report shall include, as a minimum, a completed copy of a licensee event report form. 3 Information provided on the licensee event report form shall be supplemented, as needed, by 4 additional narrative material to provide complete explanation of the circumstances surrounding the event. i { a. Reactor Protection System or engineered safety feature 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 af fected systems. b. 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.a and 2.b need not he i reported except where test results themselves reveal a degraded mode as described above. c. Observed inadequacies in the implementation of administrr.tive or procedural controls which i threaten to cause reduction of degree of redundancy provided in Reactor Protection Systems or Engineered Safety Feature Systems. d. Abnormal degradation of systems other than those specified in Item 2.c above designed to contain radioactive material resulting f rom the fission process. j Note: Scaled sources or calibration sources are not included under this ites. Leakage of valve packing or gaskets within the limits for identified leakage set forth in Technical Specifications need not be reported under this item. ls 2 Amendment No. 28, 212 l i i

d 1 VYNPS 1 C. Unique Reporting Requirements 1. Semiannual Effluent Release Report a. Within 60 days.af ter January 1 and July 1 of each year, a report shall be submitted - i covering the radioactive content of effluents released to unrestricted areas during the previous six months of operation. b. The radioactive ef fluent release reports shall include a summary of the quantities of J radioactive liquid and gaseous effluents and solid waste released f rom the unit as outlined j in Regulatory Guide 1.21, Revision 1, June 1974, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous { Effluents from Light-Water-Cooled Nuclear Power Plants", with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes the format for Table 3 in Appendix B of Regulatory Guide 1.21 shall be supplemented with three additional categories: class of solid wastes (as defined by 10CFP. Part 61), type of i container (e.g., LSA, Type A, Type B, Large Quantity), and solidification agent or j absorbent, if any. In addition, the radioactive effluent release report to be submitted 60 days after January i l 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the fo.a of an hour-by-hour j listing on magnetic tape of wind speed, wind direction, atmospheric stability, and t precipitation (if measured), or in the form of joint frequency distributions of wind speed, j wind direction, and atmospheric stability.* This same report (or a supplement to it to be i submitted within 180 days of January 1 each year) shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released f rom the unit during the previous calendar year. (The semiannual effluent release report submitted I within 60 days of July 1 each year need not contain any dose estimates f rom the previous 6 months' effluent releases.) The effluent reported submitted after January I each year shall also include an assessment of the radiation doses f rom radioactive effluents to i

• In lieu of submission with the first half year radioactive effluent release report, the licensee has the options of retaining this summary of required meteorological data in a file that shall be provided to the NRC upon request.

Amendment No. 213 l l l

l l j VYNPS' I 4 member (s) of the public due to any allowed recreational activities inside the site boundary li during the previous calendar year. All assumptions used in making these assessments (e.g., j specific activity, exposure time and location) shall be included in these reports. For any j batch or discrete gas volume releases, the meteorological conditions concurrent with the time of release of radioactive materials in gaseous ef fluents (as determined by sampling j f requency and measurement) shall be used for determining the gaseous pathway doses. For radioactive materials released in continuous effluent streams, quarterly average i meteorological conditions concurrent with the quarterly release period shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be i performed in accordance with the Off-Site Dose Calculation Manual (ODCM). i With the limits of Specification 3.8.M.1 being exceeded during the calendar year, the radioactive effluent release report to be submitted 60 days af ter January 1 of each year shall also include an assessment of radiation doses to the likely most exposed real I member (s) of the public from reactor releases (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with j 40CFR190, Environmental Radiation Protection Standards for Nuclear Power Operation. i The radioactive effluent release reports shall include a list and description of unplanned i releases from the site to site boundary of radioactive materials in gaseous and liquid 1 effluents made during the reporting period. { With the quantity of radioactive material in any outside tank exceeding the limit of Specification 3.8.D.1, describe the events leading to this condition in the next Radioactive Effluent Release Report. If inoperable radioactive liquid effluent monitoring instrumentation is not returned to operable status prior to the next release pursuant to Note 4 of Table 3.9.1, explain in the next Radioactive Effluent Release Report the reason (s) for delay in correcting the Inoperability. If inoperable gaseous effluent monitoring instrumentation is not returned to, operable status within 30 days pursuant to Note 5 of Table 3.9.2, explain in the next Radioactive l Effluent Release Report the reason (s) for delay in correcting the inoperability. I 214 Amendment No. i

4 ~ j VYNPS With milk samples no longer available f rom one or more of the sample locations required by Table 3.9.3, identify the cause(s) of the sample (s) no longer being available, identify the new location (s) for obtaining available replacement samples, and include revised ODCM i figure (s) and table (s) reflecting the new location (s) in the next Radioactive Effluent Release Report. With a land use census identifying one or more locations which yield at least a 20 percent greater dose or dose commitment than the values currently being calculated in Specification 4.8.G.1, identify the new location (s) in the next Radioactive Effluent Release Report. g Changes made during the reporting period to the Process Control Program (PCP) and to the j Off-Site Dose Calculation Manual (ODCM), shall be identified in the next Radioactive ~ Effluent Release Report. 2. Special Reports l Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. i 1 Liquid Effluents, Specifications 3.8.B and 3.8.C. a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the limits of Specification 3.8.B.1, prepare and submit to the Commission within 30 days a special report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to assure that subsequent releases will be in compliance with the limits of Specification 3.8.B.1. i l With liquid radwaste being discharged without processing through appropriate treatment systems and estimated doses in excess of Specification 3.8.C.1, prepare and submit to the Commission within 30 days a special report which includes the following information: (1) explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the rea' sons for the j inoperability; i 215 Amendment No. a v

i 4 VYNPS (2) action (s) taken to restore the inoperable equipment to operable status; and (3) Summary description of action (s) taken to prevent a recurrence. i b. Gaseous Effluents, Specifications 3.8.F, 3.8.G, 3.8.H. and 3.8.I. l i With the calculated air dose f rom radioactive noble gases in gaseous effluents exceeding j any of the limits of Specification 3.8.F.1, prepare and submit to the Commission within 30 j days a special report which identifies the cause(s) for exceeding the limit (s) and the corrective action (s) taken to assure that subsequent releases will be in compliance with the limits of Specification 3.8.F.1. With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and/or radionuclides in particulate form exceeding any of the limits of Specification 3.8.G.1, prepare and submit to the Commission within 30 days a special report which identifies the cause(s) for exceeding the limit (s) and the corrective action (s) taken to assure that subsequent releases will be in compliance with the limits of 1 Specification 3.8.G.I. 1 ] With gaseous radwaste being discharged without processing through appropriate treatment j systems as defined in Specification 3.8.H.1 for more than seven (7) consecutive days, or in ) excess of the limits of Specification 3.8.I.1, prepare and submit to the Commission within j 30 days a special report which includes the following information: 1 (1) explanation of why gaseous radwaste was being discharged without treatment (Specification 3.8.H.1), or with resultant doses in excess of Specification 3.8.1.1, identification of any inoperable equipment or subsystems, and the reasons for the inoperability; (2) action (s) taken to restore the inoperable equipment to operable status; and (3) summary description of action (s) taken to prevent a recurrence. Amendment No. 216

1 ~ VYNPS c. Total Dose, Specification 3.8.M. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding the limits of Specification 3.8.M. prepare and submit to the Commission within 30 days a special report which defines the corrective action (s) to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.8.11 and includes the schedule for achieving conformance with these limits. This special 1 report, required by 10CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to.a member of the public from station sources, including all effluent pathways and direct radiation, for the calcndar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If l the estimated doses exceed any of the limits of Specification 3.8.M, and if the release condition resulting in violation of 40CFR Part 190 has not already been corrected, the } special report shall include a request for a variance in accordance with the provisions of j 40CFR Part 190. Submittal of the report is considered a timely request, and a variance is j granted until staff action on the request is complete. j d. Radiological Environmental Monitoring, Specification 3.9.C. i With the level of radioactivity as the result of plant effluents in an environmental sampling media at one or more of the locations specified in Table 3.9.3 exceeding the i reporting levels of Table 3.9.4, prepare and submit to the Commission within 30 days fron the receipt of the Laboratory Analyses a special report which includes an evaluation of any l release conditions, environmental factors or other factors which caused the limits of Table 3.9.4 to be exceeded. This report is not required if the measured level of radioactivity was not the result of plant effluents, however, in such an event, the condition chall be j reported and described in the annual Radiological Environmental Surveillance Report. e. Land Use Census, Specification 3.9.D. With a land use census not being conducted as required by Specification 3.9.D, prepare and submit to the Commission within 30 days a special report which identifies the reasons why I the survey was not conducted, and what steps are being taken to correct the situatioa. I i Amendment No. 217 i I i e i

i ' 1 1 VYNPS l 3. Environmental Radiological Monitoring Radiological Environmental Surveillance Reports covering the operation of the unit during previous calendar year shall be submitted prior to May 1 of each year. The annual Radiological Environmental Surveillance Report shall include summaries, interpretations, cad an analysis of trends of -the results of the radiological environmental l surveillance activities for the report period, including a comparison 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 annual Radiological Environmental Surveillance Report shall include summarized and tabulated results of all radiological environmental samples taken during the report period pursuant to the table and figures in the ODCM. In the event that some 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. With the level of radioactivity in an environmental sampling media at one or more of the locations specified in Table 3,9.3 exceeding the reporting levels of Table 3.9.4, the condition shall be described in the next annual Radiological Environmental Surveillance Report only if the l measured level of radioactivity was not the result of plant effluents. With the radiological i environmental monitoring program not being conducted as specified in Table 3.9.3, a description of the reasons for not conducting the program as required and the plans for preventing a 4 recurrence shall be included in the next annual Radiological Environmental Surveillance Report. j The annual Radiological Environmental Surveillance Report shall also include the results of the i land use census required by Specification 3.9.D. A summary description of the radiological environmental monitoring program including a map of 411 sampling locations keyed to a table j giving distances and directions from the reactor shall be in the reports. If new environmental I sampling locations are identified in accordance with Specification 3.9.D. the new locations shall i be identified in the next annual Radiological Environmental Surveillance Report. The reports shall also include a discussion of all analyses in which the LLD required by Table { 4.9.3 was not achievable. J i l Amendment No. 43 218 i l

l l l mn The results of licensee participation in the intercomparison program required by Specification 3.9.E shall be included in the reports. With analyses not being performed as j required by Specification 3.9.E the corrective actions taken to prevent a recurrence shall be report to the Commission in the next annual Radiological Environmental Surveillance Report. l 6.8 Fire Protection Inspection l A. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified off site licensee personnel or an outside fire protectiva firm. i i B. An inspection and audit by an outside fire consultant shall be performed at intervals no greater than 3 years. 6.9 Environmental Qualification 1 ) A. By no later than June 30, 1982, all safety-related electrical equipment in the facility shall be I qualified in accordance with the provisions of Division of Operating Reactors, " Guidelines for Evaluating Envirotunental Qualification of Class 1E Electrical Equipment in Operating Reactors" (DOR Guidelines); or NUREG-0588, "Interia S.:aff Fosition on Environmental Qualification of Safety-Related Electrical Equipment", December 1979. Copies of these documents are attached to Order for i Modification of License DPR-28, dated October 24, 1980. B. By no later than Deceabar 1,1980, complete and auditable rece-ds must be available and maintained at a central location which describe the envirorumental qualification method used for all safety related electrical equipment in suf ficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereaf ter, such records should be updated and maintained current as equipment is I repleced, further tested, or otherwise qualified. i 6.10 Integrity of Systems Outside Contairunent l A program to reduce leakage from systems outside containment that would or could contain highly radicactive fluids during a serious transient or accident to as low as practical levels will be implemented. This program shall include the following: Amendment No. 63 219

VYNPS a A. Provisions establishing preventive maintenance and periodic visual inspection requirements. B. System leakage inspections, to the extent permitted by system design and radiological conditions, for l each system at a f requency not to exceed refueling cycle intervals. The systems subject to this i testing are: (1) Residual Heat Removal, (2) Core Spray, (3) Reactor Water Clernup, (4) EPCI, (5) RCIC, and (6) Sampling Systems. 6.11 Iodine Monitorina l A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

• under accident conditions will be implemented. This program shall include the following:

A. Training of personnel. B. Procedures for monitoring. C. Provisions for maintenance of sampling and analysis equipment. 6.12 Process Control Program (PCP) A process control program shall contain the sampling, analysis, tests, and determinations by which wet radioactive vaste f rom liquid systris is assured to be converted to a form suitable for off site disposal. j A. Licensee initiated changes to the PCP: i i 1. Shall be submitted to the Commission in the semiannual Effluent Release Report for the period in I which the change (s) was made. This submittal shall contain: l j a. Suf ficiently detailed information to support the rationale for the change without benefit of additional or supplemental information. 4 l I k

• Areas requiring personnel access for establishing hot shutdown condition.

Amendment No. 63 220 I i i

I VYNPS 4 b, A determination that the change did not reduce the overall conformance of the dewatered spent resins / filter media waste product to existing criteria for solid waste shipments and' l disposal. c. Documentation of the fact that the change has been reviewed by PORC and approved by the i Manager of Operations (M00). i 2. Shall become effective upon review by PORC and approval by the Manager of Operations (M00). l 6.13 Off-Site Dose Calculation Manual (ODCM) An Off-Site Doea Calculation Manual shall contain the current methodology and parameters used in the l calculation of off site doses due to radioactive gaseous and liquid effluents, in the calculation of i gaseous and liquid ef fluent monitot'ing alarm / trip setpoints, and in the conduct of the environmental ] radiological monitoring program. l A. Licensee initiated changes to the ODCM: 1. Shall be submitted to the Commission in the sentannual Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain: 1 a. Suf ficiently detailed information to 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 l change ( s). { b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations. j c. Documentation of the fact that the change has been reviewed by PORC and approved by the Manager of Operations (MOO). I 2. Shall become effective upon review by PORC and approved by the Manager of Operations (M00). i l Amendment No. 221 l l

I VYNPS 1, 6.14 Major Channes to Radioactive Liquid, Caseous, and Solid Waste Treatment Systeme* Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid): i i Shall be reported to the Commission in the semiannual Radioactive gffluent Release Report for the A. The discussion of each change shall contain: period in which the evaluation was reviewed by the PORC. I A summary of the evaluation that led to the determination that the change could be made in 1. accordance with 10CFR Part 50.59; Suf ficient detailed information to support the reason for the change without benefit of 4 2. additional or supplemental information; components, and processes involved and the interfaces i 3. A detailed description of the equipment, j with other plant systems; An evaluation of the change, which shows the predicted releases of radioactive materials in 4. liquid and gaseous effluents and/or quantity of solid vaste that differ from those previously predicted in the license application and amendments thereto; j An evaluation of the change, which shows the expected anximum exposures to member (s) of the 5. public at the site boundary and to the general population that differ from those previously I estimated in the license application and amendments thereto; A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents 6. and in solid waste, to the actual releases for the period prior to when the changes are to be made; An estimate of the exposure to plant operating personnel as a result of the change; and 7. e Documentation of the f act that the change was reviewed and found acceptable by PORC. 8. Shall become ef fective upon review and acceptance by PORC and apprc al by the Plant Manager. B. I )

• Licensee may choose to submit the information called for in this Specification as part of the annual FSAR update.

I 222 l Amendment No. l}}