Text

Proposed Tech Spec Change Request NPF-38-112 Re Generic Ltr 89-01 Implementation
	ML20065N596
Person / Time
Site:	Waterford
Issue date:	12/07/1990
From:	; ENTERGY OPERATIONS, INC.
To:	;
Shared Package
ML20065N588	List: ML20065N596; ML20065N748; ML20065N756; W3P90-1176, Application for Amend to License NPF-38,consisting of TS Change Request NPF-38-112 Re Generic Ltr 89-01 Implementation;
References
	GL-89-01, GL-89-1, NUDOCS 9012120208
	Download: ML20065N596 (161)
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Attachment A

- NPF-38-112 D$$ { g2 hNa P-

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i INDEX DEFINITIONS (Continued)

. ECTION PAGE 1.29 SITE BOUNDARY... ........................................... 1-7 1.30. SOFTWARE.................................................... 1-7 1.31 SOLIDIFICATION...... ....................................... 1-7 1.32 SOURCE CHECK................................................ 1-7 1.33. STAGGERED TEST BASIS...,..................... .............. 1-7 1.34 THERMAL:P0WER............................................... 1-7 1.35 U N I D E NT I F I E D '.C.A GG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 1.36.'UNRES7RICTED AREA........................................... 1-8 1.37 VENT 7LATION EXHAUST. TREATMENT SYSTEM......................... 1-8 1.38 VENTING......................................... ..... ..... 1-8 1.39 WASTE GAS' HOLDUP SYSTEM..................................... 1-8

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WATERFORD - UNIT 3 II l

4 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS-3/4.2.1 LI N EA R H EAT RAT E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 2-1 3/4.2.2 P LANAR RADI AL PEAKING FACT 0RS. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 2-3 3/4.2.3 AZIMUTHAL POWER TILT.................................... 3/4 2-4 3/4.2.4 DNBR MARGIN............................................. 3/4 2-6 3/4.2.5 RCS FLOW RATE........................................... 3/4 2-10 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE. . . . . . . . . . . . . . . . . . . . 3/4 2-11 3/4.2.7 AXIAL SHAPE INDEX....................................... 3/4 2-12 3/4.2.8 PRESSURIZER PRESSURE.................................... 3/4 2-13 3/4.3 INSTRUMEHTATION a

3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION...................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION...................................... 3/4 3-13 3/4.3.3 MONITORING INSTRUMENTATION RADIATION HONITORING INSTRUMENTATION................. 3/4 3-28 INCORE DETECTORS..................................... 3/4 3-34 SEISMIC INSTRUMENTATION.............................. 3/4 3-35 METEOROLOGICAL INSTRUMENTATION....................... 3/4 3-38

,c. ,, REMOTE SHUTDOWN INSTRUMENTATION...................... 3/4 3-41 ACCIDENT HONITORING INSTRUMENTATION.................. 3/4 3-44

' CHEMICAL DETECTION SYSTEMS........................... 3/4 3-47 l

LOOSE-PART D ETECTION INSTRUMENTATION. . . . . . . . . . . . . . . . . 3/4 3-54 RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION.................................... 3/4 3-55 '

RADI0 ACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION.................................... 3/4 3-60 3/4.3.4 TURBINE OVERSPEED PROTECTION............................ 3/4 3-68 WATERFORD - UNIT 3 V Amencment No. 50

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1 INDEX LIM'ITING CONDITIONS FOR' OPERATIONS AND SURVEILLANCE REQUIREMENTS SECTION PAGE 1

l 3/4.10- SPECIAL' TEST EXCEPTIONS (Continued) 3/4.10.2 MTC, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS............................ 3/4 10-2

~3/4.10.3 REACTOR-COOLANT L00PS................................... 3/4 10-3. I l

3/4.10.4 CENTER CEA MISALIGNMENT................................. 3/4'10-4 -

3/4.10.S NATURAL' CIRCULATION TESTING......................,...... 3/4 10-5' 3/4.11 RADI0 ACTIVE EFFLUENTS j.

3/4.11.1 LIQUID EFFLUENTS.

CONCENTRATION........................................... 3/4 11-1 00SE.................................................... 3/4 11-6 LIQUID RA0 WASTE-TREATMENT SYSTEM........................ 3/4 11-7 LIQUID HOLOUP TANKS..................................... 3/4 11-8 ,

3/4.11.2 GASEOUS EFFLUENT!

DOSE RATE............................................... 3/4 11-9

'00SE - NOBLE' GASES,..................................... 3/4-11-13 00SE --IODINE-131,100INE-133,. TRITIUM, AND RADIONUCLIDES IN PARTICULATE F0RM..................... 3/4 11-14 GASEOUS RA0 WASTE TREATMENT............................. 3/4 11-15' f

EXPLOSIVE GAS MIXTURE............'..........,........... 3/4 11-16 GAS STORAGE TANKS...................................... '3/4 11-17 3/4.11.3 SOLIO RADIOACTIVE WASTE............................... 3/4 11-18 3/4.11.4 TOTAL 00SE.............................................- 3/4 11-1S 3/4.12 RADIOLOGICAL ENVIRONMENTAL-MONITORING 3/4.12.1 MONITORING PR0 GRAM..................................... 3/4 1 --

_3/4.12.2- LAND USE' CENSUS......................................... 3/4 12-13 3/4.12.3 INTERLABORATORY. COMPARISON -

PROGRAM..................... 3/4 12-14 WATERFORD UNIT 3 X l

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INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.9 CONTAINMENT PURGE VALVE ISCLATION SYSTEM.............. B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and SPENT FUEL P00L....................................... B 3/4 9-3 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM. . . . . . . . . . . . . B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN....................................... B 3/4 10-1 3/4 10.2 MTC, GROUP HEIGHT, INSERTION, AND c POWER DISTRIBUTION LIMITS....... ..................... B 3/4 10-1

) ;3/4.10.3 REACTOR COOLANT L00PS................................. B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT...............................- B 3/4 10-1 3/4.10.5 NATURAL CIRCULATION TESTING........................... B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS....................................... B 3/4 11-1 3/4.11.2 GASECUS EFFLUENTS...................................... B 3/4 11-3

. 3/4.11.3 SOLID RADI0 ACTIVE WASTE................................ B.3/4 11-6

~3/4.11.4 TOTAL 00SE............................................. B 3/4 11-6 3/4.12 RADIOACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM..................................... B 3/4 12-1 3/4.12.2 LAND USE CENSUS........................................ B 3/4 12-2 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM..................... B 3/4 12-2 4

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i WATERFORD - UNIT 3 XIV

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 S AF ETY R EV I EW COMMI TT E E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-it FUNCTION............................................... 6-10 COMPOSIT10N............................................. 6-10 ALTERNATES........................ .................... 6-10 CONSULTANTS............................................ 6-10 MEETING FREQUENCY...................................... 6-11 QU0 RUM................................................. 6-11 REVIEW................................................. 6-11 AUDITS........................... ..................... 6-12 AUTN0RITY.............................................. 6-13 RECOR05................................................ 6-13 6.6 REPORTABLE EVENT ACTI0N..................................... 6-13 6.7 SAFETY LIMIT VIOLATION...................................... 6-13 6.8 PROCEDURES AND PR0 GRAMS............................... ..... 6-14 6.9 REPORTING REQUIREMENTS...................................... 6-16 6.9.1 ROUTINE REP 0RTS........................................... 6-16 STARTUP REP 0RT......................................... 6-17 ANNUAL REP 0RTS......................................... 6-17 MONTH LY OPE RATING REP 0 RT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-18 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATINO REPORT..... 6-18 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT......... 6-19

' INDUSTRIAL SURVEY OF T0XIC CHEMICALS REPORT............ 6-20 6.9.2 SPECIAL REP 0RTS........................................... 6-20 6.10 RECORD RETENTION........................................... 6-20 WATERFORD - UNIT 3 XVII

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+ . INDEX ADMINISTRATIVE CONTROLS-SECTION PAGE o

6.11' RADIATION PROTECTION PR0 GRAM...............................

6-22 ,

,6.12. HIGH RADIATION AREA........................................ 6-22 .;

6.13 PROCESS CONTROL PR0 GRAM.................................... 6-23 t

6.14- 0FFSITE DOSE CALCULATION MANUAL............................ 6-24 6.15' MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS. AND SOLID

. WASTE TREATMENT SYSTEMS...... ............................ 6-24

)

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WATERFORD - UNIT 3 XVIII

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4 INDEX LIST OF TABLES (Continued)

TABLE PAGE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEI LLANCE REQUIR EMENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-40 3.3 9 REMOTE SHUTDOWN INSTRUMENTATION....................... 3/4 3-42 4.3 6 REMOTE SNUTDOWN INSTxiNENTATION SURVEILLANCE REQUIREMENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-43 3.3-10 ACCIDENT MONITORING INSTRUMENTATION................... 3/4 3-45

, 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-46 '

l 3.3- 12 RADIOACTIVE LIQUID EFFLUENT MONITORING

. INSTRUMENTATION....................................... 3/4 3-56 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING' INSTRUMENTATION SURVEI LLANCE REQUIREMENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-58 3.3-13 RADICACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION....................................... 3/4 3-61 4.3-9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............. 3/4 3-65 4.4-1 HINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION........................... 3/4 4-15 4.4-2 STEAM GENERATOR TUBE INSPECTION. . . . . . . . . . . . . . . . . . . . . . . 3/4 4-16 3.4-1 REACTOR COOLANT SYSTEM' PRESSURE ISOLATION VALVES...... 3/4 4-20

. 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY...................... 3/4 4-22:

,- 7 4.4-3. -REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-23

- 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4 '26 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE

, PROGRAM - WITH0RAWAL SCHEDULE. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-32 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS. . . . . . . . . . . . 3/4 6-5 3.6-2 CONTAIMMENT ISO LATION VALVES. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-21 WATERFORD - UNIT 3 XXI Amendment No. 3, 50

INDEX

,O LIST OF TABLES (Continued)

TABLE PAGE 3.7-1 STEAM LINE SAFETY VALVG .7 L00P. . . . . . . . . . . . . . . . . . . . . 3/4 7-2 3.7-2 MAXIMUM ALLOWABLE LINEAR POWER LEVEL - HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS.......... 3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.......................... 3/4 7-8 3.7-3 ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS.......... 3/4 7-14 1

4.8-1 DIESEL GENERATOR TEST SCHEDULE. . . . . . . . . . . . . . . . . . . . . . . 3/4 8-7 4.8-la ADDITIONAL RELIABILITY ACTI0FS....................... 3/4 8-7a 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS..................... 3/4 3-11 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES................................... 3/4 8-18 3.8 MOTOR-OPERATED VALVES THINAL OVERLOAD

-) PROTECTION AND/0R BYPASS DEVICES..................... 3/4 8-53 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PR0 GRAM.............................................. 3/4 11-2 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PR0 GRAM.............................................. 3/4 11-10 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.... .. .. 3/412-3 3.12-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES............................. 3/4 12-9 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS............................................. 3/4 12-10 k

VATERFORD - UNIT 3 XXII Amendment No. ), 23, 50

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'f, DEFINITIONS:

-10ENTIFIED LEAKAGE (Continued) b; Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to-be PRESSURE BOUNDARY LEAKAGE , . or

c. Reactor Coolant System leakage through a steam generator to the secondary. system.'

' MEMBER (S) 0F THE PUBLIC_ ,

)

1.15 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa- il tionally associated with the plant. This category does not include employees

-of the -licensee, its contractors, or vendors. Also excluded from this category

-are persons who< enter the site _ to service equipment or 'make deliveries.

~

This category does include persons who use portions of the site for recreational,

-occupational, or other purposes not associated with'the plant.

OFFSITE DOSE CALCULATION MANUAL (00CM) 1.16 The OFFSITE DOSE CALCULATION MANUAL shall contain the current. methodology and parametersfused in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent-

-monitoring alarm / trip setpoints, and in the conduct of the environmental radio-logical monitoring program.

OPERABLE-' OPE 3 ABILITY 1.17 A system, subsystem, train,-component',-or device shall be- OPERABLE or -

have.0PERABILITY.when-it is. capable'of performing its specified function (s),.

(and when all necessary attendant instrumentation. controls, electrical power,.

cooling or seal water, ilubrication.or other. auxiliary equipment that'are

. required;for the system, subsystem, train, component, or~ device to perform its -i

. function (s) are'also capable of' performing their related support ~ function (s).- ]

OPERATIONAL MODE - MODE 1.18 : An OPERATIONAL 1M00E (i.e. MODE) shall correspond to any one inclusive

, icombination of; core ' reactivity' condition - power level and average reactor

-coolant temperature specified in Table 1.2..

WATERFORD:-' UNIT 3 1-4

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! DEFINITIONS PHYSICS TESTS

! 1.19 PHYSICS TESTS shall be those tests performed to measure the fundamental j nuclear characteristics of the reactor core and related instrumentation and j (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions g of 10 CFR 50.59, or (3) otherwise approved by the Commission.

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, PLANAR RADIAL PEAKING FACTOR l F,y t .

2- 1.E0 Tha PLANAR RADIAL PEAKING FACTOR is the ratio of the peak to plane average power density of the . individual fuel rods in a given horizontal plane, 4

excluding the effects of azimuthal tilt.

PRESSURE BOUNDARY LEAKAGE 1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube h akage) through a non isolable fault in a Reactor Coolant System component body, pipe wall i or vessel wall.

PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM thall contain the provisions to assure that the SOLIDIFICATION of wet radioactive wastes results in a waste form with prop-erties that meet the requirements of 10 CFR Part 61 and of low-level rreioactive !

waste disposal sites. .The PCP shall identify process parameters influ<encing SOLIDIFICATION such as pH, oil content,2 H O content, solids content, 'atio of solidification agent to waste and/or necessary additives for each ty;e of antic-ipated waste, and the acceptable boundary conditions for the process parameters-

%. shall be identified for each waste type, based on laboratory scale and full scale testing or experience. The PCP shall also include an identification of conditions that must be satisfied, based on full scale testing, to assure that dewatering of bead resins, powdered resins, and. filter sludges will result in volumes of free water, at the time of disposal, within the limits of 10 CFR Part 61 and of. low-level radioactive waste disposal sites.

PURCE - PURGING 1;23 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentra-tion or other operating condition, in such a mannrr that replacement air or gas is required to purify the confinement.

WATERFORD - UNIT 3 1-5 l

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L DEFINITICNS 4

SITE BOUNCARY 1.29 The $1TE BOUNDARY shall be that li'ne beyond which the land is neither ownuJ, nor leased, nor otherwise controlled by the licensee.

SOFTWARE 1.30 The digital computer SOFTWARE for the reactor protection system shall be the program codes including their associated data, documentation, and procedures.

SOLIDIFICATION 1.31 SOLIDIFICATION shall be the immobilization of wet radioactive wastes such as evaporator bottoms, spent resins, sludges, and reverse osmosis concentrates as a result of a process of thoroughly mixing the waste type with a solidifica-tion agent (s) to form a free standing monolith with chemical and physical charac-teristics specified in the PROCESS CONTROL PROGRAM.

SOURCE CHECK 1.32 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel senscr is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.33 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and

b. The testing of er,e system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER 1.34 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNIDENTIFIED LEAKAGE 1.35 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

WATERFORD - UNIT 3 1-7

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l INSTRUMENTATIGN RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

! LIMITING CONDITION FOR OPERATION 4

3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 Shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm /

trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (0DCM).

APPLICABILITY: At all times.

ACTION:

_ a. With radioactive liquid effluent monitoring instrumentation channel i

alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive liquid j effluents monitored by the affected channel, or declare the channel

, inoperable.

b. With less than the minimum number of radioactive liquid effluent i monitoring instrumentation channels OPERABLE, take the ACTION s:,own in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE 1 status within 30 days or, if unsuccessful, explain in the next l Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9,1.8, why this inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the specified ACTIONS are continued.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE '

CHECK, CHANNEL- CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

4 WATERFORD - UNIT 3 3/4 3-55 AMENDMENT NO.17

g TABLE 3.3-12 4 5 g RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTf. TION o'

g MINIMUM

, CHANNELS INSTRUMENT OPERABLE ACTION O 1. RADI0 ACTIVITY MONITORS PROVIDING ALARM AND

w AUTOMATIC TERMINATION OF RELEASE

a. Boric Acid Condensate Discharge 1 28

b. Waste Waste Condensate and Laundry Discharge 1 28

c. Dry Cooling Tower Sumps 1/ sump 29

d. - Turbine Building Industrial Waste Sump 1 29 i

e. Circulating Water Discharge (Blowdown Heat Exchanger and Auxiliary Component Cooling Wa*.er Pumps)# 1 29

2. CONTINUOUS COMPOSITE SAMPLERS I

a. Steam Generator Blowdown Effluent Line 1 29

3. Ft(M RATE MEASUREMENT DEVICES

a. Boric Acid Condensate Discharge 1 30 t

b. Waste, Waste Condensate and Laundry Discharge 1 30 i c. Turbine Building Industrial Waste Sump

N.A. N.A.

Eo d. Dry Cooling Tower Sumps

N.A. N.A.

ka e. Circulating Water Discharge * (Blowdown and Blowdown Heat r

l j

, Exchanger and Auxiliary Component Coo'ing Water Pumps) M.A. N.A. i W

Automatic termination of blowdown discharge c.ily l P

r y * -

m w. . - _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ . . _ _ _ _ _ . _ . _ . _ _ _ _ . . _ _ . . _ _ -

._..m.--.___

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1 TABLE 3.3-12 (Continued)

TABLE NOTATIONS

Pump performance curves generated in place shall be used to l estimate flow.

ACTION STATEMENTS l' ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to

, repair the instrument and that prior to initiating a release: !

a. At least two independent samples are analyzed in accordance.

with Specification 4.11.1.1.1, and

b. At least two technically qualified members of the Facility ;

Staff indept: dently verify the release rate calculations ;

and discharge line valving; ACTION 29 - With the number of channels CPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via ,

this pathway may continue provided best efforts are made to

repair the instrument and that grab samples are analyzed for radioactivity at a lower limit of detection of at least 10-7 microcurie /mL.

a. of.

At theleast secondary once per coolant 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when is greater the than specific 0.01 activity / gram microcurie DOSE EQUIVALENT l-131, or ;

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curie / gram DOSE EQUIVALENT I-131.

ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,-effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place may be used to estimate flow.

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WATERFORD - UNIT 3 3/4 3-57 AMENDMENT NO.17

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i TABLE 4.3-8 N

M RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4 CHANNEL

@ FUNCTIONAL CHANNEL SOURCE CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST l

l E l O 1. RADI0 ACTIVITY MONITORS PROVIDING

( w ALARMS AND AUTOMATIC TERMINATION l OF RELEASE 1

a. Boric Acid Condensate Discharge P P R(3) Q(1) l

b. Waste, Waste Condensate and Laundry P P R(3) Q(1)

Discharge _

c. Dry Cooling Tower Sumps D M R(3) Q(5)

d. Turbine Building Industrial Waste Sump D M R(3) Q(5)

e. Circulating Water Discharge w (Blowdown Heat Exchanger ar,d 1 Auxiligry Component Cooling Water w Pumps) D M R(3) Q(5)

" 2. CONTINUOUS COMPOSITE SAMPLERS

a. Steam Generator Blowdown Eff bent Line D(6) N.A. R Q

3. FLOW RATF, MEASUREMENT nEytCES l a. Boric Acid Condensate 11ischarge D(4) N.A. R Q

b. Vaste Vaste Condensat and Laundry D(4) N.A. R Q Discharge

c. Turbine Building Industrial Vaste Surp N.A. N.A. N.A. N.A.

a., d. Dry Cooling Tower Sumps N.A. N.A. N.A. N.A.

$ e. Circulating Water Discharge l

y, (810wdown and Blowdown Heat 2 Exchangers and Auxiliary

? Component Cooling Water Pumps) N.A. N.A. N.A. N.A.

~

Automatic termination of Blowdown discharge only I

i t

TABLE 4.3 8 (Continued) l TABLE NOTATION 1 (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the j following conditions exists:

1. Instrument indicates measured levels above the alarm / trip setpoint, i

2. Circuit failure.

. 3. Instrument indicates a downscale failure.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: .

1. Instrument. indicates measured levels above the alarm setpoint.

2. Circuit failure. ;

.(3) .The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NB5. These standards shall !

l permit calibrating the system for over its intended range of energy and

'.. measurement range. For subsequent CHANNEL CALIBRATION, sources that have I been related to the initial calibration shall be used.

(4) . CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on .

l- days on which continuous, periodic, or batch releases are made.

($) -The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolaticn !

of this pathway occurs if the instrument indicates measured levels above !

the alarm / trip setpoint and that control room alarm annunciation occurs if any of the following conditions exists:

i 1.. Instrument indicates measured levels above the alars set.

2. Circuit failure.

3. Instrument controls not set in operate mode.

(6) CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which I continuous releases are made to the Circulating Water System or Waterford 3 -

waste pond.

4

-(

WATERFORD - UNIT 3 3/4 3-59 Amendment No. I 1

_ _,u.,..-.0,-. ........_a , ,_,,.a.-.. , _ . . _ . . _ . - . _ _ . . _ . . . . _ . - . .

o i

I INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFI'JENT MONITORING INSTRUMENTATION 4

i i l!MDING CONDITION FOR OPERATION I.

3. 3. 3. h The radioactive gaseous effluent monitoring instrumentation channels

shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to l ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm /

i t.ip setpoints of these channels shall be determined and adjusted in accordance l with the methodology and parameters in the ODCM.

APPLICABillTY: As shown in Table 3.3-13.

ACTION:

4 l a. With'a radioactive gaseous efflue nt monitorhg instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare .'ie channel inoperable, or change the setpoint so it is acceptably conservative. l

b. With less than the minimum number of radioactive gaseous effluent

- monitoring instrumentation channels OPERABLE,-take the ACTION shown

in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Semi- l annual Radioactive Effluent Release Report, pursuant to Specification F 6.9.1'.8, why this inoperability was not corrected within the time specified. Releases need not be terminated after 30 dcys provided 4

the specified ACTIONS are continued.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel i

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

i WATERFORD - UNIT 3 3/4 3-60 AMEN 0 MENT NO.17

TABLE 3.3-13

~

c h RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUNENTATION o

MINIMUM CHAhNELS E INSTRUMENT OPERABLE APPLICABILITY ACTION g 1. WASTE GAS HOLDUP SYSTEM G -

, a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Temination of Release 1 35

b. Effluent System Flow Rate Measuring Device 1

36

2. WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM i

a. Hydrogen Monitor 1 ** 38

{ ,

4 b. Oxygen Monitors 2 40 C8 .

3. MAIN CONDENSER EVACUATION AND TURBINE GLAND SEALING SYSTEM

a. Noble Gas Activity Monitor 1 ' 37

b. Ioaine Sampler # 1

39 Particulate Sampler # *

c. 1 39

d.

Sampler Ficw Rate Monitor 1 36

If a primary to secondary leak exists or if the noble gas monitors in the main condenser evacuation am[

turbine gland sealing system or if the steam generator blowdown monitor indicates the presence or radioactivity in the secondary system, the flow from this release point shall be diverted immediately to the plant stack.

These instruments are in the plant stack and sampling for radiciodines and particulates shall occur at the plant vent when this occurs.

TABLE 3.3-13 (Continued)

M RADIDACTIVE GASEOUS EFFLUENT NOMITORING INSTRIMENTATION 4

S O

MININUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION E 4. REACTOR AUXILIARY BUILDING J

% VENTILATION SYSTEM '

w (PLANT STACK) L

, a. Noble Gas Activity Monitor -

i Providing Alarm and Automatic !

Termination of Release # 1

37

h. Iodine Sampler 1

39 i

c.

~

Particulate Sampler 1

39 w

) d. Flow Rate Monitor 1

36 l

)

i e. Sampler Flow Rate Monitor 1

36 i

m t

! 5. FUEL HANDLING BUILDING I '

VENTILATION SYSTEM (NORMAL)

a. Noble Gas Activity Monitor 1 *** 37 4

b. Iodine Sampler 1 ***

39 1 t

, c. Particulate Sampler 1 ***

39

d. Flow Rate Mo*iitor 1 **"

36 I

e. Sampler Flow Rate Monitor 1 ***

36

Automatic termination of containment purge only.

l l

TABLE 3.3-13 (Continued)

TABLE NOTATIONS

At all times.

- During WASTE GAS HOLOUP SYSTEM operation.

- - With irradiat'd fuel in the storage pool.

ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided best efforts are made to repair the instrument and that prior to initiating .

the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; j ACTION 36 - With the number of channels OPERABLE less than required by the -

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to re-pair the instrument and that the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . For the waste gas holdup tank this action item is applicable only during periods of release. For the main condenser evacuation and turbine gland sealing systems, this action item applies only during release via the discharge silencer and only during turbine gland sealing operations and/or vacuum pump operation.

ACTION 37 - With the number o' channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to re-pair the instrument and that grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . However, containment purging of radioactive effluents must be immediately suspended during this condition for the plant stack only.

ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the WASTE GAS HOLOUP SYSTEM may continue provided best efforts are made to repair the instrument and that grab samples are collected at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for the onservice gas decay tank.

f WATERFORD - UNIT 3 3/4 3-63 AMENDMENT NO.17

. .. -- . . - - - - -- __-~.-- _-.-.----_

TABLE 3.3-13 (Continued)

ACTION STATEMENTS ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.

U ACTION 40 - With the number of channels OPERABLE one less than required by

the Minimum Channels OPERABLE requirement, operation of the WASTE GAS HOLDUP SYSTEM may continue provided best efforts are made to repair the instrument and that the system is sampled l by.either the remaining monitor or by a grab sample at least ,

once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and the oxygen concentration remains less than 2%. If there are no monitors OPERABLE, WASTE GAS HOLDUP SYSTEM operation may continue provided best efforts are made to return at least one channel.to OPERABLE status and that a grab sample is taken and analyzed from the onservice gas decay tank at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and the oxygen concentration remains less than 1%.. With oxygen concentration exceeding 1%, reduce the oxygen concentration to less than 1% within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1 g.

+

L i

WATERFORD - UNIT-3 3/4 3-64 AMENDMENT NO. 17

TABLE 4.3-9 1

r. g l 3 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 9 CHANNEL MODES IN WHICH 3 CHANNEL. SOURCE' CHANNEL FUNCTIONAL SURVEILLANCE E CHECK CHECK CALIBRATION TEST IS REQUIRED

, INSTRUMENT C

j'i 1. WASTE GAS HOLDUP SYSTEM

-4

'd a. Noble Gas Activity Monitor -

Providing Alarm and Automatic

Tennination of Release - P P R(3) Q(1)

I b. Effluent System Flow Rate

Measuring Device P N.A. R Q

2. WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM R 0 N.A. Q(4) M

a. Hydrogen Monitor D N.A. Q(5) M h b. Oxygen Monitors

3. MAIN CONDENSER EVACUATION AND -

TUFaINE GLAND SEALING SYSTEM .

a. Noble Gas Activity Monitor D M R(3) Q(2)

Iodine Sampler W N.A. N.A. M.A.

b.

W N.A. N.A. N.A.

c. Particulate Sampler

d. Sampler Flow Rate Monitor D N.A. R Q i

i i

) 6

TABLE 4.3-9 (Continued) g RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4

o CHANNEL MODES IN WHICH E CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED C

h, 4. REACTOR AUFILIARY BUILDING i

" VENTILATIO?) SYSTEM (PLANT STACK) -

a. Noble Gas Activity Monitor - ;

Providing Alarm and Automatic Termination of Release # D M R(3) Q(6) *

. . b. Iodine Sampler W M.A. N.A. N.A. *

, c. Particulate Sampler W N.A. N.A. N.A. * '

) d.

, Flow Rate Monitor D N.A. R Q j

e. Sampler Flow Rate Monitor D N.A. R Q r

5. FUEL HANDLING BUILDING VENTILATION SYSTEM (NORMAL)

a. Noble Gas Activity Monitor D M R(3) Q(2) ***

L

b. Iodine Sampler W N.A. N. A. M.A. ***

j

c. Particulate Sampler W N.A. N.A. N.A. ***

d. Flow Rate Monitor D N.A. R ***

Q I t

e. Sampler Flow Rate Monitor D N.A. R Q *** ,

i

Automatic termination of containment purge only.

i f

i

, _ _ _ _ _ _ _ _ - - _ _ . . - - - _ _ - - _ - - - - - _ _ - - - _ - - - - d

l TABLE 4.3-9 (Continued)

TABLE NOTATIONS )

At all times.

- 0uring WASTE GAS HOLDUP SYSTEM operation.,

- - Vhen irradiated fuel is in the spent fuel pool.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isola of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm / trip setpoint.

2. Circuit failure. I

3. Instrument indicates a downscale f ailure. :

1 (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

(3) The initial CHANNE. CALIBRATION shall be performed using one or more of the reference sta,tdards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

The CHANNEL CALIBRATION shall include the use of standard gas samples (4) containing a nominal:

1. Zero volume per$nt hydrogen, balance nitrogen, and

2. > Four volume percent hydrogen, balance nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. Zero volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance nitrogen. '

(6) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automa of this pathway occurs if the instrument indicates measured levels above the alarm / trip setpoint and that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm set.

2. Ciicult failure.

3. Instrument controls not set in operate mode.

WATERFORD - UNIT 3 3/4 3-67

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcurie /ml total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accor-dance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

WATERFORD - UNIT 3 3/4 11-1 AMENDMENT NO. I7

s i

k TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 1

LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL)

A. Batch Waste P P Release Each Batch Each Batch Principal Gamma 5x10 7 7anks .f,g,h,i b

Emitters C

1. Boric Acid 1-131 1x10 5 Condensate P H Dissolved and 1x10 6 Entrained Gases

2. Waste One Batch /M (Gamma Emitters)

Condensate P M H3 1x10 5 Each Batch Composite d

. Laundry Gross Alpha 1x10 7 Waste (

4. Turbine P Q d Sr-89, Sr40 5x10.s Building Each Batch Composite Industrial Waste Fe-55 1x10 6 Sumps *

5. Dry Cooling Tower Sumps

1 and #2*

6. ' Regenerative Waste

7. Filter Flush

8. Waste 7 1 release from this source is batch in nature.

WATERFORD - UNIT 3 3/4 11-2

i

PAGE.OG MAY 16 '05 10:IB CATEL SERVICES CCRP.

r '

TAB.LE 4.11-1 (Contirwed)

.~.

LCVER LlHIF HINIMM 0F OETECTICH LIQUID RELEASE SMPL1HG ANALYSI5 TYPE Oc ACTIVITV (LLD)a TYPE FREQUCMCY FREQUCHCT AN 4YS15 (pci/rtL)

8. Continuous W W Principal Gtana 5x10 7 I' I ' "3 " * . Grab Sample Emitters" 1 Turbine 1-131 1x10 8 8uilding Industrial h Waste Sumps **. -

M M Dissolved and 1x10 5

2. Dry Cooling Grab Sample Entrained Cases -

Tower i (Gamsa Emitters)

Susp #1**

3. Dry Coolin0 'W - M d H-S M05 Tower i Grab Sample composite

- 84'P 82** '

Grost Alpha 1x10 7

4. Circulating W Q Sr.H $W kW d

. Water , Grab Sawle Composita ot scharge- . Fe-2 1x10 8

. .. Steam Gene-rater blow-

. down HX

5. Auxiliary Component cooling i Vater Pumps e

0 0 .

- vhen reiease from this source is continuous in nature.

3/4 11-3 #N ** I VATERf0RD - UNIT 3

- --- --.~.-- = = = ~ ~ ~ - ~ ~ ~ ~ ~

, m m_m. ...

.. MAY 16 '85 18:21 QafEL SERVICES CORP. PAGE.06 TA415 4.!!-! (Continued)

' ~

i LOWat LIMIT' KINIMUN LIQUID RELEASE SANFLINGn-OF DettcTION ANALYSIS TYPE OF ACTIVITY TT?t FREQUENCY (Lt.b)a T1tEQtJENCY ANALYSIS (uC1/mL)

5. Continuous V V Principal Canaa h10*I telaases e,f Contfor~:sk Coeposite Emitters *

6. Steau Cenerator I-131 1 10-6 810wdows Disch1rge $1 H M Dissolved and lx10-5 Crab Sample Entrained C4ses (Gamma Emitters)

W M M-3 lx10-5 Continoons Composite d Cross Alpha 1x10' W Q Sr-89. Sr-90 $x10-8 Continuou d Composited

, , , Fe-55 .

lx10-6 S

e W

uATEtroan - UNIT 3 3/4 11-3a AMENDMENT NO. 1

~~~~~~~?--

9 l

TABLE 4.11-1 (Continued)

~

TABLE NOTATION l l

a ine LLD is defined, for purposes of these specifications, as 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 that a blank observation represents a "real" signal.

~For a particular measurement system, which may include radiochemical i separation:

.66 s b gg 3 ,

E V 2.22 x 10' Y exp (-Aot)

Where:

LLO is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, ss is the standard deviation of the background counting rate or of the c5uriting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, t

V is the sample size in units of mass or volume, 2.22 x 108 is the number of afsintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an

.a posteriori (after the fact) limit for a particular measurement.

b A batch release is the discharge of' liquid wastes of 'a-discrete volume.

Price to sampling for analyses, each batch shall be isolated, and then thoroughly mixect.by a method described in the 00CM to: assure representative sampling.

WATERFORD - UNIT 3 3/4 11-4

, . ,e_,. , , - - , . . - - . - , - , . , . . . - . - _ _ , . . . , . - . , . - .

4 i

TABLE 4.11-1 (Continued)

TABLE NOTATIONS The principal gamma emitters for which the LLO specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134. Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are ident;fiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to

Specification 6.9.1.8.

d A composite rample is one in which the quantity of liquid sampler' ;. proportional to the quant',ty of liquid waste discharged and in which the method of s,ampling ,

employed resalts in a specimen that is representative of the liquids released.

'A continuous release is the discharge of liquid wastes if a nondiscrete volume, e.g. from a volume of a system that has an inptt ficw during the continuous rtlease.

I Prior to analyses, all samples taken for the composite ihall be thoroughly mixed in order for che composite sample to be representative if the effluent t

release.

9 If the contents of the filter flush tank or the regenerative waste tank

. contain detectable radioactivity, no discharges from these tanks shall be made to the UNRESTRICTED AREA and the contents of these tanks shall be directed to 6~ the liquid radwaste treatment system.

h Turbine Building Industrial Waste Sump (TBIWS)

,,- The TBIWS shall be required to be sampled and analyzed in accordance with this table if any of the following conditions exist:

(1) Primary to secondary leakage is occurring; or, (2) Activity is present in the- secondary system as indicated by either the SGB monitors or secondary sampling and analysis; or, (3) . Activity was nresent in the TBIWS during the previous 4 weeks.

If none of the above situations exists, then the sampling and analysis of this stream need not be performed.

Sampling and analysis of the dry cooling tower sumps and the auxiliary component cooling water pump discharge will be required only when detectable activity exists in the CCW.

Sampling and analysis of the circulating water discharge-steam generator blowdown heat exchanger discharge-(CWD-5GB) will be required only when detectable activity exists in the secondary system.

(

WATERFORD - UNIT 3 3/4 11-5

,,** MAY 16 '05 18:25 QATEL SERVICES CO2P. PAGE.07 Table 4.11-1 (Continued)

TABl,E NOTATIORS

' 1.

j 3 Sampling and analysis of the steam generator blovdown vill be required only when the blevdovo is directed to the circulating water syntes or' Vaterford 3 veste pond.

, steam generator blevdown to the Vaterford 3 veste poed vill be limited to attuations requiring secondary cheedstry control where the Circulating Vater System is not available or the secondary chemistry is outside the requireeents for. Circulating Veter System discharge. Slowdown to the vaste pond will be terminated apoo , detection of sample 'setivity greater than the 11D liirels of table 4.11-1 Section B.

k

.. To be repres'entative of the quantities and concentration of radioactive materials in liquid effluents, samples shall be collected continuously-in proportion to the rate of flow of the affluent stream.

I Steam generator blowdown discharge to the wasta pond shall be limited to a period of six months with the circulating water system discha' roe'

,, path not available unless radiation sonitoring and automatic isolatlon capabilities are added to the waste pond discharge path, w

+,

VArzarotD - tntIT 3 3/4 11-5. AMrwrwrxT uo. 1

, , , _ _ _ , - - - - - - - - --- - -------- " - * * " " " " ~ ~ * ~

! Y

j. ,

j' RADIOACTIVE EFFLUENTS

! DOSE l' LIMITING CONDITION FOR OPERATION k 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive i materials in liquid effluents released to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited: .

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, i and

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

., ACTION:

1 a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifica-

! tion 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective getions that

have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include (1) the results of radiological analyses of the crinking water source and (2) the radiological-impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

[ SURVEILLANCE REQUIREMENTS 4.11.1'.2 Cumulative dose contributions from liquid effluents for the current i

calendar. quarter cnd the current calendar year shall be determined in accordance with-the methodology and parameters-in the ODCM at least once per 31 days, i

i l'

s WATERFORD - UNIT 3 3/4 11-6 l ,

l l

t

i l

RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITICN FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid. effluent to UNRESTRICTED AREAS (see Figure S.1-3),would exceed 0.06 mrem tc the total body or 0.2 mrem to any organ in a 31 day period.

APPLICABillTY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation, prepare and submit to the Commis-sion within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason 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,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid re' leases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be demonstrated OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

WATERFORD - UNIT 3 3/4 11-7

R RADIOACTIVE EFFLUENTS 3/4.11,2 GASEOUS EFFLUENTS DOSE RATE LIMITI.NG CONDITION FOR OPERATION

, 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and

b. .For iodine-131, iodine-133, for tritium, an.d for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to:1500 mrems/yr to any organ.

APPLICABILITY: At all times..

ACTION:

With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s), and describe the events leading to this condition in the next Semiannual' Radioactive Effluent Release Report.

i, SURVEILLANCE REQUIREMENTS 4.11.2.1.1- The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the 00CM.

4.11.2.1.2 Representative samples and analysis of gaseous effluents shall be obtained in accordance with the sampling and analyses program specified in Table 4.11-2.

4.11.2.1.3 Based upon the sampling and analysis performed in Table 4.11-2 the dose rate due to I-131. I-133 H-3, and all other radionuclides in particulate '

l form with half-lives greater than 8 days shall be determined to be within the above limits in accordance with the methodology.and parameters in the 00CM. ,

1 WATERFORD - UNIT 3- 3/4 11-9

. i h

t TABLE 4.11-2' j d RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

, E o MINIMUM LOWER LIMIT Of~

$ SAMPLING ANALYSIS TYPE OF DETECTION (LLD)*

I . GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS 64i/st)

?- c P P 5

A. Waste Gas Holdup Each Tank Each Tank Principal Gamma EmittersD 1x10

Tanks Grab Sample P P C

l B. Containment PURGE Each PURGE Each PURGE C

Principal Gamma Emitters D 1x10 *

] (Plant Stack) -

Grab Sample M 11- 3 1x10 8 C

C.1 Plant Stack M 'd'i Principal Noble Gas Gamma b

1x10

Grab Sample M Emitt ers H-3 1x10 6 R

C 2 Fuel Handling M) Principal Noble Gas Gamma b 1x10

Building Ven- Grab Sample M Emitters j U' tilation H-3 1x10 6

,. (Normal)

Exhaust I D.1 All Release Types ' ContinuousI 'D'd W9 I-131 1x102 }

l as listed in / Charcoal i B., C.1, and 5ssple I-133 1x10 88

! C.2 above !

a . {,

D.2 Main Condenser Continuousf , .J g3 PrincipagParticulateGamma 1x10 88 Evacuation and [

Particulate . Emitters i Turbine Gland Sample -

Scaling System

! Continuous #'D'l M Gross Alpha 1x10 88 l

Composite [

j 3 Particulate ;

} Sample j l Continuous #' *) Q Sr-89, Sr-90 1x10 88 i Composite j Particulate ;

j Sample j

Continuous * *) Noble Gas Noble Gases 1x10 8 Monitor GrNs Beta or Gamma .!

2

d i

2 TABLE 4.11-2 (Continued)

. TABLE NOTATION

'The LLD is defined for purposes of these specifications, as the smallest ,

concentration of f dioactive material in a sample that will yield a net count,

l. above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a

, " teal" signal.

For a particular measurement system, which may include radiochemical separation:

1' 4.66s b

LLD =

E V 2.22 x 106 Y exp (-Aat)

Where:

LLO is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sg is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, I

V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and ,

at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.

1 Typical values of E, V, Y, and a should be used in the calculation.

It should be recognized that the-LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter the fact) limit for a particular measurement.

WATERFORD - UNIT 3 3/4 11-11

l TABLE 4.11-2 (Continued)

TABLE NOTATIONS b

The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xc-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131,1-133, Cs-134, Cs-137, Ce-141, and Ce -144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

C Sampling shall also be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. . Analysis for prin.!ple gamma emitters as defined in (b) above shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of sampling, d

iritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the :

refueling canal is flooded.

' Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

I The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made i

in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

9 Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months af ter changing, or af ter removal from sampler.

Sampling shall also be performed at least once per 24 h";urs for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may b.s increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 '

concentration in the primary coolant has not increased more than a f actor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

h If no primary to secondary leakage exists, then only the gross beta or gamma noble gases analysis need be performed for the main condenser evacuation and turbine gland sealing system. If a primary to secondary leak exists and the release from the main condenser evacuation and turbine gland sealing system has not been released via the plant stack, then the sampling and analysis must be performed.

Note (c) above is not applicable for the plant stack unless the noble gas monitor shows that effluent activity has increased by a factor of 3.

buel Handling Building sampling is required whenever irradiated fuel is in the storage pool.

WATERFORD - UNIT 3 3/4 11-12 i

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3,11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

a. During any. calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and,

b. During any calendar year: Less than or equal to 10 mrads for gamma rsdiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION

a. With the calculated air dose from radioactive noble gases in gaseous ef fluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.?, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed correctiva actions to be

[ taken to assure that subsequent releases will be in compliance with the above limits,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

CURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 aays.

(

WATERFORD - UNIT 3 3/4 11-13

RADI0 ACTIVE EFFLUENTS DOSE - 10 DINE-131, 100lNE-133, TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION

' 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous ef fluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s)

{' for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulativa dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form'with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.

WATERFORD - UNIT 3 3/4 11-14

1 a ,

t. ,

RADIOACTIVE EFFLUENTS JGASEOUS RA0 WASTE TREATMENT LIMITING = CONDITION FOR OPERATION-3.11.2.4 The-VENTILATION EXHAUST TREATMENT SYSTFM and_ the WASTE GAS HOLDUP ,

SYSTEM shall be _0PERABLE and appropriate portions of these systems shall be' '

.used to reduceLreleases of radioactivity when the projected doses in 31 days

-due to gaseous effluent' releases to areas at and beyond the SITE 80VNDfiRY (see

, Figure 5.1-3) would exceed either:

'a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or_ l

c. 0.3. mrem to any organ of a MEMBER OF.THE-PUBLIC.

APPLICABILITY: At all times.

ACTION:-

a. With radioactive gasbous waste being discharged without treatment-and -in excess of the above limits, prepare and submit .to the Commis-sion within130 days, pursuant to Specification.6.9.2, a Special' Report,that includes the following information:

L

1. {

1. Identification of any inoperable equipment or subsystems, and the reason'for the inoperability, 2, Action (s) taken to restore the inoperable equipment to OPERABLE status, and

.3. .bummary description of action (s) taken to prevent a recurrence.

b. .The provisions of Specifications 3.0.3.and 3.0.4 are not applicable.

SURVEILLANCE' REQUIREMENTS 4.11.2.4.1 Doses.due to gaseous releases to areas at and beyond the_ SITE BOUNDARY shall be projected at least once per' 31 days in accordance with the methodology and parameters in.the ODCM.

4.11.2.4.2 The installed Gaseous Radwaste Treatment System, shall be demonstrated 0PERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or_ ,

3!11.2.3.

o p

'I WATErJ ORD - UNIT 3 3/4 11-15

1 0' ~RADI0ACTIVEEFFLUENTS' 3/4.'11.3 SOLIO RADI0 ACTIVE WASTE i LIMITING' CONDITION FOR OPERATION 3.11.3' Radioactive wastes shall be SOLIDIFIED or dewatered in accordance with-the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

APPLICABILITY: At all times.

ACTION: ,

a. With SOLIDIFICATION or dewatering not meeting disposal site and.

shipping- and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL '

PROGRAM,.the procedures, and/or the solid waste system as necessary to prevent recurrence. .

b. With SOLIDI'FICATION or dewatering not performed in accordance with the PROCESS CONTROL-PROGRAti, . (1) test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and (2) take appropriate administrative action to prevent-recurrence,

c. With the installed equipment incapable of meeting Specification 3.11.3

.( or declared inoperable, restore the equipment to OPERA 8LE' status or provide for contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements,

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.11.3 SOLIDIFICATION-of at least one representative test specimen.f t om at least every tenth batch- of each' type of wet radioactive wastes (e.g. , filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM.'

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION -i of the batch.under test shall be suspended until such time as additional-test specimens can be obtained, alternative. SOLIDIFICATION parameters

. can be-determined in accordance with ;he PROCESS CONTROL PROGRAM,.

and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the t.iternative' SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.

b. 'If the initial test specimen from a batch of waste- f ails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent lq batches of waste.

WATERFORD - UNIT 3 3/4 11-18 l

' RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE .

LIMITING CONDITION FOR OPERATION 3.11.4 The' annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to relases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

, ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifi-c a tion 3.11.1. 2. a , ' 3.11.1. 2. b 3.11. 2. 2. a . 3.11. 2. 2. b . 3.11. 2. 3. a .

or 3.11.2.3.b, calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks

-to determine whether the above limits of Specification 3.11.4 have

~

been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases ~to prevent recurrence of exceeding'the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to.a MEMBER OF THE PUBLIC from uranium fuel, cycle sources, including all effluent pathways and direct radiation, for the calendar 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 the estimated dose (s) exceeds the above limits, and if tne -release condition resulting in violation of 40 CFR Part 190 has not already _ been corrected, the Special Report shall include a request for a variance in accordance with the

, provisions of 40 CFR Part-190. Submittal of the report is con-sidered a timely request, and a variance is granted until staff action on the request is complete.

L b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS - 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and L 4.11.2.3, and.in.accordance with the methodology and parameters in the 00CM.

4.11.4.2 Cumulative dose contributions from direct radiation from the reactor L

units and from radwaste storage tanks shall be determined in accordance with L the-methodology and parameters in the ODCM. This requirement is applicable l .only under conditions set forth-in Specification 3.11.<4.a.

WATERFORD - UNIT 3 3/4 11-19 w T r w ,w e ~ " > % % v

3/4'.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM

~

LIMITING CONDITION FOR CPERATION

.[

3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table.3.12-1.

o . APPLICABILITY: At all times.

ACTION:

a. With-the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the o

^

Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.7, a. description of the .

reasons for not conducting the program as required and the plans '

for preventing a recurrence, a

b. With-the level of radioactivity as the result of plant effluents;in an environmental sampling medium at a specified location exceeding ^

the reporting, levels of Table 3.12-2 when averaged over any calendar quarter,~ prepare and submit to the Commission within.30 days, pursuant to Specificaton 6 9.2,- a Special Report that identifies.the cause(s) '

for exceeding the. limit (s) and defines the corrective actions-to be

, taken to reduce radioactive effluents so that the potential annual ;

dose

to.A MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12-2-are detected in the sampling medium, this report shall be submitted if:

concentration (1) , concentration (2) . ...) 1.0 reporting level (1) reporting-level (2)

When adionuclides other than those in Table 3.12-2 are detected.atd are.the result of plant effluents, this' report shall be submitted ir the potential annual dose

to A: MEMBER OF' THE PUBLIC is equal to or greater than the' calendar year limits of _ Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. This report is not required if the measured. 3 level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described-in the Annual Radiological Environmental Operating Report,

c. With milk or fresh leafy vegetable samples unavailable from one or. _

more of the sample locations required by Table 3.12-1, identify W locations for obtaining replacement samples'and add them'to the -

radiological environmental monitoring program within 30~ days. The

The methodology and. parameters used to estimate the potential annual. dose to-a_ MEMBER OF THE PUBLIC shall be indicated in this report.

t WATERFORD - UNIT 3 3/4 12-1

-m .. . _. _. _ . . _ . _ _ - .- ___ _.

a

!- RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued) specific locations irem which samples were unavailable may then be ,

deleted from the monitoring program. Pursuant to Specification !

6.9.1.8, identify the cause of the unavailability of samples and I identify the new location (s) for obtaining replacement samples in i the next Semiannual Radioactive Effluent Release Report and also includo in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS l

4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from' the specific locations n ,eno in the table and figure (s) in the ODCM, and shall be analyzed puriuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

I

-t WATERFORD - UNIT 3 3/4 12-2

~

. a

~ "

,--i

.a.

jE TABLE-3.12 ;;;

4' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

o -

o-NUMBER OF-REPRESENTATIVE E EXPOSURE PATHWAY SAMPLES AND. SAMPLING AND TYPE AND FREQUENCY 1 AND/OR SAMPLE SAMPLE LOCATIONS

COLLECTION FREQUENCY OF-ANALYSIS b

1. DIRECT RADIATION 31/ routine monitoring stations Quarterly Gamma dose quarterly.

either with 2 or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

an inner ring of. stations, one in

~,

u, each meteorological sector in the 30 gent.a1 area of the SITE BOUNDARY,.

kh an outer ring of stations, 1 in-10 of the' meteorological sectors '

in the 6- to 8-km range from the site; ,

the balance of the stations to be plar.ed in special' interest areas such'as population centers, nearby-residences, schools, and in 1 or 2 a.eas to serve as control stations.

The number, media,' frequency, and location of samples may vary from site to site. This table-presents an acceptable minimum ' program' for a site at which each entry is applicable. Local site-characteristics must be examired to determine if pathways not covered by this table may significantly contribute to an -

individual's dose and should be included in the sampling program.

- ~ . .. -- - -, - , _

~

f w

TABLE 3.12-1 (Continued)'

A q RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

C) ,

w '

C' NUMBER OF-REPRESENTATIVE E EXPOSURE PATHWAY. ; SAMPLES AND' SAMPLING AND TYPE AND FREQUENCY tj AND/0R SAMPLE SAMPLE LOCATIONS, COLLECTION FREQUENCY OF ANALYSIS w - -

2. AIRBORNE Radioiodine and Samples from 5 locations Continuous sampler- Radiciodine Cannister:

Particulates operation with sample I-131 analysis weekly.

3 samples from close to the collection weekly, or 3 SITE BOUNDARY locations, in more frequently if different sectors, of the required by dust Porticulate Sampler:

highest calculated annual' average loading. Gross beta radioactivity ground-level 0/Q. analysis folleging-filter. change;

I sample from the vicinity of a Gamma isotopic analysis

,, community having the highest of composite (by <

y calculated annual average location) quarterly.

= ground-level D/Q. !

I sample from a control location, as for example 15-30 km distant and in winddirection.gheleastprevalent

3. WATERBORNE

-1

a. Surface # 1 sample upstream Compositesampfeover Gamma isotopic analysis

I sample downstream 1 month period monthly.- Composite for

-tritium analysis quarterly.

.b. Ground Samples from 1 or 2 sources Quarterly Gamma isotopic

and tritium h

only if likely to be affected analysis quarterly. ,

_ _ _ = . _ ._ ._

jE TABLE 3.12-1-(Continued) ig RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

O c3 N'JMBER OF REPRESENTATIVE gj. EXPOSURE PATilWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY -

AND/0R SAMPLE a.

q SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS

~

us c .' Drinking 1 sample of each of 1 to 3 of Composite sample I-131 analysis on each compositeL i the nearest water supplies that over 2-week period9 when the dose calculated for the could be affected by its. when 1-131 analysis consumption of the water is discharge. ,

. is performed, monthly greater than 1 arem per. year.g composite otherwise Composite.for gross betg and gamma isotopic analyses monthly.

Composite for tritium analysis quarterly.

{' ; d. Sediment 1 sample from downstream area Semiannually Gamma isotopic analysis"

,, from with existing or potential semiannually.

q> shoreline recreational value.

u.

4. INGESTION

a. Milk Samples from milking animals Semimonthly when Gamma isotopic

and I-131 in 3 locations within 5 km animals are on analysis semimonthly'when i distance having the highest pasture; monthly at animals are on pasture; dose potential. If there are other times monthly at other times.

none, then, I sample from milking animals'in each of 3 areas between 5 to 8 km distant where doses arecalculategtobegreaterthan 1 mrem per yr .

1 sample from milking animals at a control location 15-30 km distant and in the least prevalent wind direction.C m ,,

a - - - .- - - -

g TABLE 3.12-1 (Continued) k -

. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *'

O o NUMBER OF-REPRESENTATIVE g EXPOSURE PATHWAY SAMPLES AND-3 SAMPLING.AND

. TYPE AND FREQUENCY-Q AND/0R SAMPLE SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS

b. ' Fish and 1 sample of each commercially - Sample .in season, ' or Gamma isotopic analysis' Inverte- and recreationally important semiannually if they on edible portions.

brates ~ species in vicinity of plant are not seasonal discharge area.

I sample of same species in areas not influenced by plant

, discharge.

$ c. Food 1 sample of each principal class At time of harvest i Gamma isotopic analysis' g Products of food products from any area on edible portion.

rf that is irrigated by water.in

<n which' liquid plant wastes have discharged.

Samples of 1-to 3 different kinds Monthly when Gamma' isotopic' and I-131 of broad leaf vegetation grown available analysis.

nearest each of two different offsite locations of highest i

predicted ~ annual average ground-level D/Q if milk sampling.is not-performed.

I sample of each of the similar Monthly when Gamma isotopic

and.I-131 broad leaf vegetation grown available analysis.

15-30 km distant in the least prevalent wind direction if milk sampling ~is not performed.

% 7.__ . , . , ... -

-. ,.i, , 4 , w -. t 4 ..y,. .. ,<- ,

TABLE 3.12-1 (Continued)

TABLE NOTATIONS a

specific parameters of distance and direction sector frcm the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure (s) in the 00CM. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtain-able due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, corrective action shall be completed prior to the end of-the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environ-mental Operating Report pursuant to Specification 6.9.1.7. It is recognized that, at times it may not be possible or practicable to continue to cbtain samples of the media of 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 environmental monitoring program. Pursuant to Specification 6.9.1.8, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Semianuual Radioactive Effluent Release Report and also include in the report a revised. figure (s) and table for the 00CM reflecting the new location (s).

( b 0ne or more instruments, such as a' pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in adaition 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 as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the spe-cific system used and should be selected to obtain optimum dose information with minimal fading.

c The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

d Airborne particulate sample filters shall be analyzed for gross beta radio-activity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be:

performed on the individual samples.

l

' Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the eff..ents from the facility.

(

WATERFORD - UNIT 3 3/4 12-7

. , _ . _ ~.-m__.. _ . _ . _ _ _ . _ _ _ . _ _ _ _ _._ _ _ ._ _. . . .

I TABLE 3.12-1-(Continued)

TABLE NOTATIONS (Continued)

I The_" upstream sample" shall.be taken at a distance beyond significant influence of the discharge. The " downstream" sample-shall be taken in an area-beyond but near the mixing zone. . " Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall Lbe sampled only when the receiving water is utilized for recreational activities, e 9A composite sample 'is one in which the quantity _ (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in,a specimen that is representative of the liquid-flow. In this program composite sample aliquots shall be collected at time intervals that are ver period-(e.g,, monthly)y short-(e.g.,

in order to assure hourly) obtaining relative to the compositing a representative sample.

_hGroundwater samples shall be taken when this source is tapped for drinking or:

Irrigation purposes in areas where the hydraulic gradient or recharge' proper-ties are suitable for contamination.

I The_ dose shall be calculated for the' maximum organ and age group, using the methodology and parameters in the 00CM.

IIf harvest occurs more'than once a year, sampling shall be performed during

' t' each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention'shall be paid to including samples of tuberous and root food products.

A WATERFORD - UNIT 3 3/4 12-8 amMT---'TmM -

P s f e

g TABLE 3.12-2 w

REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels g WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS p ANALYSIS (pCi/1) OR GASES (pci/m3 ) (pCi/kg, wet)- (pCi/t) (pCi/kg, wet) 11- 3 20,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 m Co-60 300 10,000 D In-65 300 20,000 S Zr-Nb-95 400 I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 4 2,000 70 2,000 Ba-La-140 200 300

i

. ...~

~

g TABLE 4.12-1 ,

a a k DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSI5

C LOWER LIMIT OF DETECTION (LLD) 3 F ISil - MILK FOOD PRODUCTS SEDIMENT g WATER AIRBORNE PARTICULATE (pCi/kg, wet) (pC1/t) (pCi/kg, wet) (pCf/kg. dry)'

q ANALYSIS (pC1/2) .OR GAS (pCi/m3 )

w gross beta 4 0.01 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 l

l A Zn-65 30 260 w

i 7 y

Zr-Nb-95 15 d 60 I-131 I 0.07 1 0.05 130 15 60 150 Cs-134 15 0.06 150 18 80 180 Cs-137 18 Ba-La-140 15 15 1

TABLE 4.12-1 (Continued)

TABLE NOTATIONS a

This! list does not mean that only these nuclides are to be considered. Other peaks.that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report' pursuant to Specification 6.9.1.7.

'b Required detection capabilities for thermoluminescent dosimeters used for

~

'i environmental measurements shall.be in accordance with the recommendations of

< Regulatory Guide 4.13.

C The LLO is defined, for purposes of these specifications, as 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 that a blank observation represents a ;

"real signal .

For'a particular measurement system, which may include radiochemical- ,

separation:

4.66 s b -

.E V 2.22 x 105 Y exp(-AATT .

F Where:

LLO is' the "a_ priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sfisthestandarddeviationofthebackgroundcountingrateorofthe-

.cDunting rate of a blank sample as appropriate, as counts per minute, ;5 E is the counting efficiency,-as counts per disintegration, V is the sample size in units _of mass or_ volume, 2.22 x 108 is' the' number of disintegrations per minute per microcurie, ;

Y is the. fractional radiochemical yield, whenl applicable, A is the radioactive' decay constant for the particular radionuclide, and 6t- for environmental samples is the elapsed time between sample collection, 4

or end of'the sample collection period, and time of counting Typical values of E, V, Y, and at should be used in the calculation.

l l WATERFORD - UNIT 3 3/4 12-11 L

7ABLE 4.12-1 (Continued) 1 TABLE NOTATIONS It should be recogaized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a mannar that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrol-lable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

I WATERFORD - UNIT 3 3/4 12-12

l l

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden

of greater than 50 m 2 (500 ft 2) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location (s) that yields a cal-culated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8,

b. With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location f rom which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control

( station location, having the lowest calculated dose or dose commitment (s),

via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Specification 6.9.1.8 identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised Tigure(s) and table for the ODCM reflecting the new location (s),

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the bat results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

Broad leaf vegetation sampling of different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12-1 Part 4.c. shall be followed, including analysis of control samples.

WATERFORD - UNIT 3 3/4 12-13 o . - .

._. - _ .,_ . _ _ _ . . _ . _ . _ _ , , . . . _ , >g n

. RADIOLOGICAL ENVIRONMENTAL MONITORING.

3/4.12.3- INTERLABORATORY: COMPARISON' PROGRAM LIMITING CONDITION FOR-OPERATION i

3.12.3 . Analyses shall be performed on all radioactive materials . supplied as lpart of an Interlaboratory Comparison Program that has'been approved by the Commission. -

APPLICABILITY: ' At.all times.

ACTION: ,

a. With analyses not being performed as required above. report the corrective actions taken to prevent a recurrence to the Commission in theLAnnual Radiological Environmental Operating Report pursuant - ~

3- to' Specification 6.9.1.7.

b. The provisions of. Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison. Program shall be described in the 00CM.

'8. 1 A , summary _of'the' results obtained as part of the above required Interlaboratory Comparison Program thall be included in the' Annual Radiological. Environmental Operating Report pu.suant.to; Specification 6.9.1.7.

WATERFORD - UNIT 3 3/4 12-14

.. - . . . ~ . . - - . - - . . - . .. .

4

. 'J -

(NSTRUMENTATION BASES 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 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 alarm / trip setpoints for these-instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits. of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is . consistent with the require-ments of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

, ,. '3/4.3.3.11' -RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

_ The radioactive gaseous effluent instrumentation is provided to monitor and control,tas applicable. the releases of radioactive materials in gaseous effluents ;during actual or potential.- releases of gaseous ef fluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the 00CM to ensure that the alarm / trip will_ occur prior to exceeding the limits of _10 CFR Part 20. This

' instrumentation also includes provisions for monitoring (and controlling) the concentrations'of potentially explosive gas mixtures in the WASTE GAS HOLOUP SYSTEM.

The OPERABILITY and useaof this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A i

to.10 CFR Part 50.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to' ensure that'the turbine overspeed

. protection instrumentation _and the turbine speed control _ valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the' turbine could Lgenerate potentially damaging missiles which could impact and damage safety related components, equipment, or. structures.

WATERFORD - UNIT 3 8 3/4 3-4 u _ - - =.

5 3/4.11 RADIOACTIVE EFFLUENTS

- BASES

'3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.I- CONCENTRATION-Thisispecification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS ,

- will- be less than the concentration levels specified in 10 CFR Part 20, Appendix B,. Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II. A design objectives of Appendix I, 10 CFR Part 50,_to-a MEMBER OF THE PUBLIC and (2) the limits of ,

10 CFR Part_.20._106(e) to the population 4 The concentration limit for dissolved or. entrained _ noble _ gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration is water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The sampling-and analysis of the contents of the regenerative waste tank.

- and the filter flush tank is performed if primary to secondary leakage occurs in a steam generator. The contents of these tanks cannot.be discharged to the

~ UNRESTRICTED AREA if any radioactivity is detected in these tanks since the

. discharge-from these tanks is unmonitored. When radioactivity is detected'in these tanks, the contents from these tanks must be discharged to the liquid radwaste system where the; contents may then-be mon'itored-upon discharge.

The required = detection capabilities for' radioactive materials in liquid waste samples are tabulated in terms .of the lower limits of detection (LLDs).

. Detailed discussion-of the LLO, and other detection _ limits can be found in HASL Procedures.' Manual, HASL-300 (revised annually), Currie, L. A., " Limits.

for Qualitative Detection and Quantitative Determination _ Application to

~

Radiochemistry," Anal. Chemi 40,-586-93 (1968),-and Hartwell, J. K.,

'" Detection limits:for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report _ARH-SA-215 (June 1975).

3/4.11.L 2 '00SE lThis specification 'is provided to implement the requirements of Sections i

- II.A,-III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation . implements the guides set forth in Section II. A of Appendix I.

The. ACTION- statements provide the required operating flexibilty 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 effluents-to .'

UNRESTRICTED AREAS will be kept "as low as is-reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected;by plant operations, there is reasonable assurance that the operation WATERFORD - UNIT 3 8 3/4 11-1 E

w "+-- - e-, g- - g 3 & , r *Per-> w

7

_ _ ._ _ - _ .__ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _.m. _ _ __ _,

RADIOACTIVE EFFLUENTS BASES

'0OSE (Continued) of the facility will not: result in radionuclide concentrations in the finished -

drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the 00CM implement the require-ment 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 oathways is unlikely-to be substantially underestimated.- The equations specified in the ODCM for calculating the doses due to-the actual release rates of radio '

active-materials inLliquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, . Appendix I," Revision 1, October- 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental-and Routine Reactor. Releases for the Purpose of Implementing Appendix I," April 1977.

- 3/4.- 11.1. 3 LIQUID RADWASTE TREATMENT SYSTEM

-The OPERABILITY of the liquid radwaste treatment system. ensures that this system will be available for use:whenever liquid effluents require treatment prior to-release. to the environment . The requirement that the

. appropriate portions of this' system be used when specified provides assurance

'that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part~50.36a,7 G eneral Design Criterion 60 of Appendix A'

.to.10 CFR1Part'50.and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of-the: liquid radwaste treatment system were.specified as a suitable

< fraction'of the dese: design objectives set forth.in Section II. A of Appendix I,

- 10' CFR Part 50,. for liquid ef fluents.

-3/4.11.1.4 LIQUID HOLOUP'TAHKS

-The . tanks listed in this specification include all those outdoor radwaste

~

tanks that are -not surrounded by ' liners,-dikes, or walls capable of holding .

the. tank contents and that do not have tank overflows: and surrounding area drains connected toithe 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 tank's -contents, the resulting concentrations would be less than the limits'of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an

= UNRESTRICTED-AREA.

WATERFORD - UNIT 3 8 3/4 11-2

_ .- . . -~ -- - - .

RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous ef fluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS.

The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B. Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA,-

either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBEMS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits 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 less than or equal to 500 mrems/ year to the total body or to less than or equal to 3000 n. rems / year to the skin.

These release rate limits also restrict, at all times, the corresponding

. thyroid dose rate above background to a child via the-inhalation pathway to less than or equal to 1500 mrems/ year.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower. limits of detection (LLDs).

Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A. , " Limits for Qualitative Detection an'd Quantitative Determination - Application to Radio-chemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K. , " Detection Limits for Radioanalytical Counting Techniques," Atlantic P.ichfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.11.2.2 OOSE - NOBLE GASES This specification is provided to implement the requirements of Sections

. II.B, III. A and IV. A of Appendix I,10 CFR Part 50. The Limiting Condition

-for Operation implements the guides set forth in Section II.B of Appendix I.

The ACTION statements provide the required 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 gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of WATERFORD - UNIT 3 B 3/4 11-3

i RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES (Continued)

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 dose calculation methodology and para-meters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.

The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

Grab sampling of effluents from the main condenser evacuation and turbine gland sealing system is not required when this source has been continously discharging to the plant stack over the past 30 days. If no primary to secondary leakage in the steam generator exists, then there should be no radioactive release from the main condenser evacuat%n and turbine gland sealing system and the gross beta or gamma monito.'ag for noble gases will be sufficient to determine if any radioactivity is present in the release. If a primary to secondary leak exists, then the release from the_ main condenser evacuation and turbine gland sealing system wi~11 be samplingtwill be sampled and analyzed in - ordance with Table 4.11-2.' ~

a ?,;c 3/4.11.2.3 DOSE - 10 DINE-131. 10 DINE-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 Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix 1.

The ACTION statements provide the required 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 effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures 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 ODCH calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with WATERFORD - UNIT 3 B 3/4 11-4

RADIOACTIVE EFFLUENTS BASES DOSE-10 DINE-131, 10 DINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM (Continued) the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Ef fluents in Routine Releases from 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, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy 1'

vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man, 3/4.11.2.4 GASEOUS RADWASTE TREATMENT The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The discharge from the main condenser evacuation and turbine gland sealing system shall be required to be directed to the plant stack when the release rate of I-131 from this source is > 2 x 10 4 pCi/s. The require-ment that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in j gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing.

the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of

.)otentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled

, in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

WATERFORD - UNIT 3 8 3/4 11-5

l l

)

i 1

' RADIOACTIVE EFFLt,5NTS

. BASES-

}

3/4.11.2.6 GAS STORAGE TANKS-Thisispecification considers postulated radioactive releases due to a ,

waste gas system leak or failure, and limits the quantity of radioactivity contained in each pressurized gas storage tank in the WASTE GAS HOLOUP SYSTEM to assure that. a release would be'substantially below the guidelines of 10 CFR Part 100 for a' postulated event.

~

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the. ,

tark's contents, the resulting. total body exposure to a MEMBER OF THE PUBLIC i at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with' Standard Review Plan 11.3, Branch Technical Position'ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981.

.3/4.11.3-- SOLIO RADIOACTIVE WASTE

.This specification implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR.Part 50. The process parameters included in establishing the PROCESS ~ CONTROL PROGRAM may include,

,," but are' not limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical-constituents, and mixing and curing times.

3/4.11.4 TOTAL DOSE-

, This. specification is provided to meet the dose -limitations of 40 CFR

.P art 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and-direct radiation exceed 25 mrems to- the total body or any organ, except the thyroid, which shall be. limited to less than or equal to 75 mrems. For sites containing. up to four. reactors, it is highly unlikely that the resultant dose

".. to a. MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the-individual reactors remain' within twice the dose design objectives of Appendix I, and if direct radiation doses from the. reactor units and outside -

storage tanks are kept small. 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 40 CFR-Part 190 limits. For the purposes of the--

Spr.cial Report, 'it may be assumed that the dose commitment to the MEMBER OF "dE PUBLIC from other uranium fuel cycle sources is negligible, with the

" exception'that dose contributions from other nuclear-fuel cycle facilities at

-the same site or within a radius of 8 km must be considered. If the dose to ,

WATERFORD - UNIT 3 B 3/4 11-6

1 RADIOACTIVE EFFLUENTS BASES TOTAL 00SE (Continued) any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1. 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.

z WATERFORD - UNIT 3 8 3/4 11-7

. I 3/4.12 RADIOLOGICAL ENVIRONMFNTAL MONITORING BASES 3/4.12.1- MONITORING PROGRAM The radiological envi.ronmental monitoring program required by this specification provides representative measurements of radiation and of radioactive materiale in those exposure pathways and for those radionuclides l that lead to the highest potential radiation exposures of MEMBERS OF THE ;

PUBLIC resulting from the plant eperation. This monitoring program irrplements 1 Sectice IV.B.2 of Appendix ! 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 the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environ-mental Monitoring._ The initially specified monitor _ing program will be effective-for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The require' detection capabilities for environmental sample analyses are tabulated in cerms of the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for rou;ine environmental measurements'in industrial laboratories. It should be recognized that the LLD is defined as an a priori-(before the fact) limit representing the capability of a' measurement system and not as an a_ posteriori (after the fact) limit for a', particular measurement.

Detailed discussion ~of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry,"' Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limits for;Radicanalytical Counting Techniques," Atlantic Richfield Hanford ~

. Company Report ARH-SA-215_ (June 1975).

WATERFORD - UNIT 3 B 3/4 12-1

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.2 LAND OSE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if riquired by the results of this census. The best information f rom the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfics the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of grea'.er than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2 .

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

)

e WATERFORD - UNIT 3 8 3/4 12-2 i

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

1. Training of personnel,

2. Procedures for monitoring, and -

3. Provisions for maintenance of sampling and analysis equipment.

c. Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

1. Identification of a sampling schedule for the critical variables and control points for these variables,

2. Identification of the procedu*es used to measure the values of the critical variables,

3. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,

4. Procedures for the recording and management of data,

5. Procedures defining corrective actions for all off-control point chemistry conditions, and

6. A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events requireri to initiate corrective action.

-d. Post-accident Samplino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

1. Training of personnel,

2. Procedures for sampling and analysis, and

3. Provisions for maintenance of sampling and analysis equipment.

e. Basemat Monitoring A program for monitoring of the Nuclear Plant Island Structure (NPIS)

Common Foundation Basemat to ensure the continued integrity of the Basemat. The program shall include:

1. settlement of the basemat

2. changes in ground water chemistry that could effect corrosion of reinforcing steel

3. seasonal variation in ground water levels

4. mapping of significant cracking in the basemat and adjacent walls.

'$7'R; 080 - UNIT 3 6-16

,+__a___.

ADMIN]$TRATIVE CONTROLS

~

(

HONTHLY OPERATING REPORTS 6.9.1.6 Routine reports e trating statistics and shutdown experience, including documentation o'. .I challenges to the safety valves, shall be submitted on a monthly ba , to the Director, Office of Resource Management, ,

U.S. Nuclear Regulatory Cu.. mission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6. 9.1. 7 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial repor' shall be submitted prior to May 1 of the year following initial criticality.

.The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance repo.rts, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specifi_ cation 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the (

4 results of analysis of all radiological environmental samples and of all '

environmental radiation measurenents taken during the period pursuant to the locations specified in the Table and Figures in the 00CM, as well as summarized and tabulated res'ults of these analyses and measurements in the format of the table i'n the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the rt.1rt, 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. ,

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps

covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion of all deviations from the sampling schedule of Table 3.12-1; and discussion of all an'alyses in which the LLO required by Table 4.12-1 was not achievable.

0ne map shall cover stations near the SITE BOUNDARY a second shall include the more distant stations.

WATERFORD - UNIT 3 6-18

ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

6. 9.1. 8 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.

The Semiannual Radioactive Effluent Release Reports shall include a summary of ,

the quantities r,f radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-

active Materials in Liquid and Gaseous Effluents from Light water-cooled Nuclear Power Plants," Revision 1 June 1974, with data summarl2ed on a quarterly basis following the format of Appendix B thereof.

The Semiannual Radioactive Effluent Release Report to be submitted within +

60 days after January 1 of each year shall include an annual summary of hourly .

meteorological data collected over the previous year. This annual summary may I be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured),

or !n the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous ef fluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure. ,

time and location, shall be-included in these reports. The meteorological conditions concurrent with the t me of release of radioactive materials in gaseous ef fluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation >

doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The Semiannual Radioactive Effluent Release Report shall also include once a year an assessment of radiation doses to the 1iktly most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental e Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are i

given in Regulatory Guide - 1.109, Rev.1, October -1977,

)

In lieu of submission with the first half year Semiannual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

l l' l WATERFORD - UNIT 3 6-19

l 1 ,

i j ADMINISTRATIVE CONTROLS i

I SEM! ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued) 4

[ The Semiannual Radioactive Effluent Release Reports shall include the following

! information for each class of solid waste (as defined by 10 CFR Part 61)

shipped offsite during the report period

1 j a. Container volume,

b. Total curie quantity (specify whether determiaed by measurement or j estimate),

l- c. Principal radionuclides (specify whether determined by measurement !

or estimate), i

d. Source of waste and processing employed'(e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

L e. Type of container (e.g. , LSA, Type A, Type B, large Quantity), and E .

f. Solidification agent or absorbent (e.g., cement, urea formaldehyde),

t

. The Semiannual Radioactive Effluent Release Reports shall include a list and !

description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting

, period.

T

' The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to ~

the OFFSITE DOSE CALCULATION MANUAL (00CM), as well as a listing of new loca- '

tions for dose calculations and/or environmental monitoring identified by the .

- land us6 census-pursuant to Specification 3.12.2.

INDUSTRIAL SURVEY OF T0XIC OR HAZARDOUS CHEMICALS REPORT ,

6.9.1.9 Surveys and analyses of major industries in the vicinity of Waterford 3 which could have significant inventories of toxic chemicals onsite to determine impact on safety shall be performed and submitted to the Commission at least

once every 4 years.

6.9.1.10 A _ survey of major pipelines (> 4 inches) within a 2-mile radius of

' Waterford 3, which contain explosive or,, flammable materials and may represent a hazard to Waterford.3, including scaled engineering drawings or maps which indicate the pipeline locations, shall be performed and submitted to the Com- !

mission at least once every 4 years.

SPECIAL REPORTS

- 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

6._10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal- Regulations, the following records shall be retained for at least the minimum per.iod indicated.

s

! WATERFORD UNIT 3 6-20 i

.s, nc--,-.,r.,~,,-,-v o e w w m -, ~me,,- , nn ,- - ,- r-, , - , , ~ , - - ~ ~ ~ - ~ - ~ ~ ~ - - ~ - - ~ ~ ~ - - ~ ~ - ' - ~ ~ ~ " - " "

l l

ADMINISTRATIVE CONTROLS

~ RECORD RETENTION (Continued) i.- Records of quality assurance activities required by the QA Manual. {

i

j. Records of reviews performed for changes made to procedures or

~

- equipment or reviews of tests and experiments pursuant to 10 CFR 50.59. ;

k. Records of meetings of the PORC and the SRC.

1. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the ;

service-life commences and associated installation and maintenance

~

records.

t

m. Records of' secondary water sampling and water quality. _

n.- Records of audits performed under the requirements of Specification 6.5.2.8.

o.' Records of analyses required by the radiological environmental

. monitoring. program that would permit evaluation of the accuracy-of the analysis at a.later date. This should include procedures -.

effective at specified times and QA records showing that these procedures were followed.

6.11 RADIATION PROTECTION PROGRAM

_{

6.11.1 Procedures for personne1' radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved,. ,

maintained and adhered to for all operations involving personnel radiation exposure. .

~

6.12 HIGH RADIATION AREA ,

6.12.1 In ' lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the ^<

intensity of radiation is greater than 100 mrem /h- but less than .1000 mrem /h shall be barricaded and conspicuously posted as a high radiation area and-:

entrance thereto-shall be controlled by requiring issuance of a Radiation Work LPermit (RWP)*. Any individual or group of individuals permitted to enter such areas.shall be prcvided with or accompanied by one or more of the following: ,

i a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

Health physics personnel or personnel escorted by health physics personne1 ~

L shall be exempt from the RWP issuance requirement during the performance of their. assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

lI l

WATERFORD - UNIT 3 6-22 L d' vi9 g-g a e---

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)

ADMINISTRATIVE CONTROLS i HIGH RADIATION AREA (Continued) l

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established ,

and personnel have been made knowledgeable of them.

c. A health physics qualified individual (i.e., qualified in radiation '

protection procedures) with a radiation dose rate monitoring device '

who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Radiation Protection Superin- )

tendent-Nuclear in the RWP. I 6.12.2 In addition to the requirements of Specification 6.12.1, areas accessitAe to personnel with radiation lovels such that a major portion of the body could receive in one hour a dose greater than 1000 mrems*.shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shif t Supervisor on duty and/or health physics super--

vision. Doors shall remain locked except during periods of, access by personnel under an approved RWP which shall specify the dose rate levels in the-immediate "ork

. area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a ,

major portion of the body could. receive in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a dose in excess of j 1000 mrems* that:are located within large areas, such as PWR containment, where '

no enclosure exists for purposes of locking, and no enclosure can be reason-ably constructed around the individual areas, then that area shall be. roped: 7 off, conspicuously posted and a flashing light'shall be activated as a warning '

device. In lieu of the stay time specification of the RWP, direct'or remote z

(such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive

exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 . Licensee-initiated changes to the PCP:

a. Shall.be submitted to the Commission in the Semiannual Radioactive ,

Effluent Release Report for the period in which the change (s) was .

made.- This submittal shall contain:

1. Sufficiently detailed information to totally support the rationale -

for the change without benefit of additional or supplemental information;

Measurement made at 18 inches from source of radioactivity, f

WATERFORD - UNIT 3 6 23

, -._.-,a .-------.-.-a..-- .- -.- -. - . -.- -.

1 ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued) l

2. A determination that the change did not reduce the overall l conformance of the waste product to existing criteria of l 10 CFR Part 61 and for burial at low-level waste sites; and

3. Documentation of the fact that the change has been reviewed and found acceptable by the PORC.

b. Shall become effective upon review and acceptance by the PORC.

6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee-initiated changes to the 00CM:

a. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:

1. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the 00CM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);

2. A dt:ter.t.ination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and

3. Docume, nation of the fact that the change has been reviewed end-found acceptable by the PORC.

b. Shall become effective upon review and acceptance by the PORC.

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS

6.15.1 Licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):

a. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussion of each change shall contain:

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

i WATERFORD - UNIT 3 6-24 I

l l

ADMINISTRATIVE CONTROLS MAJOR CHANGES TO RADI0 ACTIVE LIOUID, GASEOUS, AND SOLID WASTE TREATMENT

$YSTEMS (Continuedi '

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59,

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

5. An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;

6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous of fluents and in solid waste, to the

actual releases for the period prior to when the changes are.to be made;

7. An estimate of the exposure to plant operating personnel as a -

l result of the change; and

8. Documentation of the fact that the change was reviewed and found acceptable by the PORC.

b. Shall become effective upon review and acceptance by the PORC.

WATERFORD - UNIT 3 6-25

. ~ . _ _ _ . _. . . - - . .-.-=.-.- . .. --~~.-.- - . . . - . . . . .-.. . . - -_-

,4 I

L i

Attachment B-NPF-38-112

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1 1

1 I

INDEX DEFINITIONS (Continued)

SECTION PAGE 1.29 SITE B0VNDARY............................................... 1-7 C6t, 1.30 SOFTWARE.................................................... 1-7 h.YS0LIDIFICATION.............................................. 1-[

1,32 55uktt CHECK................................................ 1-7 1.33 STAGGERED TEST BASIS........................................ 1-7 1.34 THERMAL P0WER............................................... 1-7 1.35 UN I D E NT I F I E D L E A KAG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 1.36 UNRESTRICTED AREA........................................... 1-8 1.37 VENTILATION EXHAUST TREATMENT SYSTEM........................ 1-8 1.38 VENTING..................................................... 1-8 1.39 WASTE GAS HOLDUP SYSTEM..................................... 1-8 WATERFORD - UNIT 3 II

INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LI N EA R H EAT RAT E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 2-1 3/4.2.2 P LANAR RADI AL PEAKING FACT 0RS. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 2-3 !

3/4.2.3 AZIMUTHAL POWER TILT.................................... 3/4 2-4 3/4.2.4 DNBR MARGIN............................................. 3/4 2 6 3/4.2.5 RCS FLOW RATE........................................... 3/4 2-10 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE.................... 3/4 2-11 3/4.2.7 AXIAL SHAPE INDEX....................................... 3/4 2-12 3/4.2.8 PRESSURIZER PRESSURE.................................... 3/4 2-13 3/4.3 INSTRUMENTATION

~

3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION...................... 3/4 3-1 e

3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION...................................... 3/4 3-13 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION................. 3/4 3-28 INCORE DETECTORS..................................... 3/4 3-34 SEISMIC INSTRUMENTATION.:............................ 3/4 3-35 METEOROLOGICAL INSTRUMENTATION....................... 3/4 3-38

,g, ,,. REMOTE SHUTDOWN INSTRUMENTATION...................... 3/4 3-41 ACCIDENT MONITORING INSTRUMENTATION.................. 3/4 3-44 CHEMICAL DETECTION SYSTEMS. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-47 l

rGL LOOSE-PART DETECTION INSTRUMENTATION.................

3/4 3-54 RADIOACTIVE LIQUID EFFLUENT HONITORING \

TEL - INSTRUMENTATION....................................

==== . mm. 3/43-55[

A rv, .

_ - - _ ~ . _ ~ ~ ~ ~ ~ _ . _ .

RADI0ACTIVEGASEOUSEFFLUENT)HONITORING l bh ""!^ 6'"

INSTRUMENTATION.................................... 3/4 3-60 3/4.3.4 TURBINE OVERSPEED PROTECTION............................ 3/4 3-68 l

WATERFORD - UNIT 3 V Amenament No. 50

1 l-i .

.INDEX LIMITING CONDITIONS FOR OPERATIONS AND SURVEILLANCE REQUIREMENTS i SECTION PAGE ;

~

3/4.10 SPECIAL TEST EXCEPTIONS (Continued) ,

3/4.10.2 MTC, GROUP HEIGHT, IN5!RTION, AND POWER DISTRIBUTIch 19175 ............................ 3/4 10-2 3/4.10.3 REACTOR COOLANT LO0fS................................... 3/4 10-3 ,

3/4 10-4

-3/4.10.4 CENTER CEA MISALIGNM('NT.... ............................

3/4.10.5 NATURAL CIRC'Jl.A1 ION TR$i!NG. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-5 +

3/4.11 RADI0ACTIVEEFFLUEg,5 3/4.11.1 LIQUID EFFLUEN ,TS.

CONCENTRATION........................... ............... 3/4 11-1 3/4 11-6 1)E'[ T 00$E......................... ........................

N........................ 3/4 11-7 QIQUID RA0 WASTE TREATMENY ] _

LIQUID HOLOUP TANKS........................'............. 3/4 11-8 3/4.11.2 GASEOUS. EFFLUENTS ___

IOOSE RATE................................................ 3/4 11-9 I DOSE - NOBLE GASES...................................... 3/4 11-13 DC1. T DOSE - 100!NE-131, 100INE-133, TRITIUM, AND RADIONUCLIOES IN PARTICULATE F0RM.................... 3/4 11-14 ,

@SE0VSRA0WASTETREATMENT._............................ U411-lh EXPLOSIVE GAS MIXTURE.................................. 3/4 11-16 GAS STORAGE TANKS...................................... 3/4 11-17 g [ 3/4.11.3 SOLIO RADIOACTIVE WiSTE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/411-15) 3/4.11.4 TOTAL 00SE........... _................................ 3/4 11-19J I L

g - _--

~N

. 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING ,

1 3/4.12.1 MONITORING PR0 GRAM..................................... 3/4 12-1 3/4.12.2 LAND USE CENSUS........................................ 3/4 12-13

. 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM..................... 3/4 12-14 Q,- _ -_. -_.

1 WATERFORD - UNIT 3 X i

j ..

. - . - - _ . . _ _ _ ~ _ , _ _ _ _ . _ _

1 .

o INDEX BASES

, SECTION PAGE 3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.9 CONTAINMENT P'JkGE VALVE ISOLATION SYSTEM. . . . . . . . . . . . . . B 3/4 9-2 3/4.9.10 and 3/4.5.11 WATER LEVEL - REACTOR VESSEL and SPENT FUEL P00L....................................... B 3/4 9-3 3/4.9.12 FUEL HANDLING BUI LDING VENTI LATION SYSTEM. . . . . . . . . . . . . B 3/4 9-3 1

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN....................................... B 3/4 10-1 3/( 10.2 MTC, GROUP HEIGHT, INSERTION, AND s POWER DISTRIBUTION LIMITS........................... B 3/4 10-1

) ~3/4.10.3 R EACTO R COO LANT L00PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4'10-1 3/4.10.4 CENTER CEA MISALIGNMENT............................... B 3/4 10-1 3/4.10.5 NATURAL CIRCULATION TESTING. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS....................................... B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS...................................... B 3/4 11-3

[3/4.11.3 SOLID RADI0 ACTIVE WASTE................................ B 3/4 11-6 T

{ 3/4.11.4 TOTAL 00SE............................................. B 3/411-6 3/4.12 RADI0 ACTIVE ENVIRONMENTAL MONITORING f3/4.12.1MONITORING PR0 GRAM..................................... B 3/4 12-1 3/4.12.2 Lino uSE CENSUS........................................ B 3,4 12-2 3/4.12.3 INTERLABORATORY COMPARISON PRDGRAM. . . . . . . . . . . . . . . . . . . . B 3/412-2 l \q DEL WATERFORD - UNIT 3 XIV

i INDEX j ADMINISTRATIVL CONTROLS

. SECTION PAGE ,

4 6.5.2 SAFETY REVliW COMMITTEE................................... 6-10 FUNCTION............................................... 6-10 ,

COMPOSITION............................................ 6-10 l ALTERNATES............................................. 6-10 CONSULTANTS............................................ 6-10 L MEETING FREQUENCY..'.................................... 6-11 QU0 RUM................................................. 6-11 REVIEW................................................. 6-11 AUDITS................................................. 6-12

{'

AUTHORITY.............................................. 6-13 RECOR05................................................ 6-13 -

6.6 REPORTABLE EVENT ACT!0N..................................... 6-13 '

6.7 S A F ETY L I M I T V ! 0 LAi ' O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-13 6.8 PROCEDURES AND PR0 GRAMS..................................... 6-14 6.9 REPORTING REQUIREMENTS...................................... 6-16 j

6.9.1 ROUTINE REP 0RTS........................................... 6-16 jRENUA4 i

STARTUP REP 0RT......................................... 6-17 ANNUAL REP 0RTS......................................... 6-17 ,

MONTHLY OPERATING REP 0RT............................... 6-18 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..... 6-18 1

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT......... 6-19 L INDUSTRIAL SURVEY OF T0XIC CHEMICALS REPORT............ 6-20 i

1. :6.9.2 SPECIAL REP 0RTS........................................... 6-20 i.

6.10 RECORD RETENTION........................................... 6-20 WATERFORD - UNIT 3 XVII L .

1 INDEX ADMINISTRATIVE CON 1ROLS SECTION PAGE 6.11 RADIATION PROTECTION PR0 GRAM............................... 6-22 6.12 HIGH RADIATION AREA........................................ 6-22 ,

6.13 PROCESS CONTROL PR0 GRAM.................................... 6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................ 6-24 IEW 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS. AND SOLIO

( WASTE TREATMENT SYSTEMS.................................... 6-24 9

WATERFORD - UNIT 3 XVIII L

LNDEX l LIST OF TABLES (Continued)

TABLE PAGE 4.3-$ METEOROLOGICAL MONITORING IhSTRUMENTATION i

SURVEILLANCE REQUIREMENTS............................. 3/4 3e40 ,

3.3 9 REMOTE SHUTDOWN INSTRUMENTATION....................... 3/4 3 42 4.3 6 REMOTE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................. 3/4 3-43 3.3-10 ACCIDENT MONITORING INSTRUMENTATION................... 3/4 3-45 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................. 3/4 3-46 tu I l

hf3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING

. INSTRUMENTATION....................................... 3/4 3 56 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................. 3/4 3-58 gU, Y313 S .INSTRUMENTAf!0N.......................................

IEflVBIRDUS EFFLUENT) MONITORING 3/4 3-61

(&Fwwttc,y w or.c 4.3-9 MUiDI0 ACTIVE GASE0US_ EFFLUENT) MONITORING IN$7RUMENTATION SURVEI((ANCE REQUIREMENTS............. 3/4 3-65 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED '

DURING INSERVICE INSPECTION.... ...................... 3/4 4-15 4.4-2 STEAM GENERATOR TUBE INSPECTION. . . . . . . . . . . . . . . . . . . . . . . 3/4 4 16 -

3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES...... 3/4 4-20

. 3.4-2 REACTOR COOLANT - SYSTEM CHEMISTRY. . . . . . . . . . . . . . . . . . . . . . 3/4 4-22 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS............................. 3/4 4-23 4.4-4 PRIMARY C0OLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-26 4.4-5' REACTOR VESSEL MATERIAL SURVEILLANCE

-, PROGRAM - WITH0RAWAL SCHEDULE. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-32 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS. . . . . . . . . . . . 3/4 6-5 l

l 3.6 CONTAINMENT ISOLATION VALVES.......................... 3/4 6-21

] RGHOM

(

~

WATERFORD - UNIT 3 XXI Amendment No. 3,50 l

[

S INDEX m '

LIST OF TABLES (Continued)

TABLE, PAGE 3.7-1 STEAM LINE SAFETY VALVES PER L00P. . . . . . . . . . . . . . . . . . . . . 3/4 7-2 3.7-2 MAXIMUM ALLOWABLE LINEAR POWER LEVEL - HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS. .. ... . . . . 3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVIT(

SAMPLE AND ANALYSIS P R0 GRAM. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-8 3.7-3 ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS.......... 3/4 7-14 l

4.8-1 DIESEL GENERATOR TEST SCHEDULE. . . . . . . . . . . . . . . . . . . . . . . 3/4 8-7 4.8-la ADDITIONAL RELIABILITY ACTIONS....................... 3/4 8 7a

,' 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS. . . . . . . . . . . . . . . . . . . . 3/4 8-11 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE 0EVICES................................... 3/4 8-18

- 3.8-2 MOTOR-OFERATED VALVES 1HERMAL OVERLOAD h on PROTECTION AND/0R BYPASS DEVICES..................... 3/4 8-53 f 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS P R 0G RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 11- 2 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS P R 0 G RAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 /4 11- 10 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. . . . . . . . 3/4 12-3 3.12-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES............................. 3/4 12-9

. . . s:

4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS............................................. 3/4 12-10 4

)

WATERFORD - UNIT 3 XXII Amendment No. ), 23, 50

d DEFINITIONS IDENTtCIED LEAKAGE (Continued)

b. Leakage into the containment atmosphere from sources that are both toecifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAMGE, or

c. Reactor Coolant System leakage through a steam generator to the secondary system.

MEMBER (5) 0F THE PUBLIC ,

1.1" MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL (00CM) g* s 1.16,[The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology fdparametersusedinthecalculationofoffsitedosesduetoradioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the environmental radio-(logicalmonitoringprogram. )

OPERABLE - OPERABILITY 1.17 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when.it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1.18 An OPERATIONAL MODE (i.e. MODE) shall correspond to any one inclusive combination of core reactivity' condition, power level and average reactor coolant temperature specified in Table 1.2.

WATERFORD - UNIT 3 1-4

i a ,

I i

i The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology

! and parameters used in the calculation of offsite doses resulting from radio-l active gaseous and liquid effluents, in the calculation of gaseous and liquid 4

effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-i mental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and i l Semiannual Radioactive Effluent Release Reports required by Specification 6.9.1.3 and 6.9.1.4.

1 L

t I

i i

b 1

\-

I i

I l

l

OEFINITIONS PHYSICS TESTS 1.19 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and relatea instrumentation and (1) d'escribed in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PLANAR RA0! AL PEAKING FACTOR - F xy 1.20 The PLANAR RADIAL PEAKING FACTOR is the ratio of the peak to plane average power density of the individual fuel rods in a given horizontal plane, excluding the effects of azimuthal tilt.

PRESSURE BOUNDARY LEAKAGE 1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non isolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

PROCESS CONTROL PROGRAM (PCP) ,

[ _

IJ2 h PROCESS CONTROL PROGRAM shall contain the provisions to assure that the SOLIDIFICATION of wet radioactive wastes results in a waste form with prop-erties that meet the requirements of 10 CFR Part 61 and of low-level radioactive waste disposal sites. The PCP shall identify process parameters influencing SOLIDIFICATION such as pH, oil content,2 H O content, solids content, ratio of solidification agent to waste and/or necessary additives for each type of antic-ipated waste, and the acceptable boundary conditions for the process parameters shall be identified for each waste type, based on laboratory scale and full scale testing or experience. The PCP shall also include an identification of conditions that must be satisfied, based on full scale testing, to assure that dewatering of bead resins, powdered resins, and filter sludges will result in volumes of free water, at the time of disposal, within the limits of 10 CFR /

Part 61 and of low-level radioactive waste disposal sites. /

~

Tr , r rac% w e. - , enc r.

newt w ii n PURGE - PURGING 1.23 PURGE or PURGING shall be the controlled p a cess of discharging air or gas from a confinement to maintain temperature, p" essure, humidity, concentra-tion or other operating condition, in such a manne,' that replacement air or gas is required to purify the confinement.

WATERFORD - UNIT 3 1-5

_~ . - ._ .

1 9-1 1

The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, i sampling, analyses, test, and determinations to be made to ensure that pro-

! cessing and packaging of solid radioactive wastes based on demonstrated pro-1 cessing of actual or simulated wet solid wastes will be accomplished in such a

., way as to assure compliance with 10 CFR parts 20, 61, and 71, state regula-i tions, burial ground requirements, and other requirements governing the j

disposal of solid radioactive waste.

5 l

2

?

6 3 l ,

!- .t 4

3 l:

Y I

,,%- - - . - _ . - . . - - . , _ . . , - . . - , , - + , . . ~ . ~ , , . . . . ~ , . . , . , . . _-4.-..:... . .. - .,-m -.. . . . . . . ~ . . . -l . . ~ - . _ , - , . . ~.~-m....

DEFINITIONS SITE BOUNDARY -

l 1.29 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee, d

SOFTWARE 1.30 The digital computer SOFTVARE for the reactor protection system shall be the program codes including their usociated data, documentation, and procedures.

OG L-SOLIDIFICATION 1 SOLIDIFICATION shall be the immooilization of wet radioactive wastes such I as31 evaporator bottoms, spent resins, sludges, and reverse osmosis concentrates as a result of a process of thoroughly mixing the waste type with a solidifica-tion agent (s) to form a free standing monolith with chemical and physical charac-QeristicsspecifiedinthePROCESSCONTROLPROGRAM.

SOURCE CHECK 1.32 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGEREDTESTB,AS]

1,33 A STAGGERED TEST BASIS shall consist of:

a. A test' schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test ,

interval into n equal subintervals, and

b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

l THERMAL POWER 1.34 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNIDENTIFIED LEAKAGE 1.35 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

WATERFORD - UNIT 3 1-7

I _ _

j INSTRUMENTATION 10 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMIT CONDITION FOR OPERA 110N ,

'3.3.3.10 radioactive liquid effluent monitoring instrumentat . channels i shown in Tabl 3-12 shall be OPERABLE with their alarm / trip oints set to ensure that the its of Specification 3.11.1.1 are not exc ed. The alarm /

trip setpoints of e channels shall be determined and sted in accordance with the methodology parameters in the OFFSITE DOSE .CULATION MANUAL (00CM).

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid eff monitoring instrumentation channel alarm / trip setpoint less co ative than required by the above Specification, immediatal usp the release of radioactive liquid effluents monitored by affect channel, or declare the channel inoperable,

b. With less than th minimum number of ra active licuid effluent monitoring inst mentation channels OPERA , take the ACTION shown in Table 3.3- . Restore the inoperable ins mentation to OPERABLE status with 30 days or, if unsuccessful, ex in in the next Semiannua adioactive Effluent Release Report, ursuant to Specifi ion 6.9.1.8, why this inoperability wa ot corrected withi he time specified. Releases need not be t inated after 30 d- s provided the specified ACTIONS are continue

c. T provisions of Specifications 3.0.3 and 3.0.4 are n applicable.

SURVEIL CE REQUIREMENTS -

4.3 .10 Each radioactive liquid effluent monitoring instrumentation ch el s i be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURC ECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

DEL

! WATERFORD - UNIT 3 3/4 3-55 AMENDMENT NO. 17

, ._- - _ . ._ ~ _ - .- -

r

j. ,

l ,. TABLE 3.3-12 [

D g RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 8

l g MINIMUM ;

! , CHANNE

! c TRUMENT OPERW_E ACTION f

, 55 i

-* 1. RADIOACTIVITY MONIT PROVIDING ALARM AND I w AUTOMATIC TERMINATI0 RELEASE

a. Boric Acid Condensate arge 1 28

b. Waste. Waste Condensate and dry Discharge 1 28 !

c. Dry Cooling Tower Sumps 1/ sump 29

d. Turbine Building Industrial Waste Sump 1 29 w -

D e. Circulating Water Discharge (Blowdown t Ex er j and Auxiliary Component Cooling Wa Pumps)# 1 29

2. CONTINUGUS COMPOSITE SAMPLERS

a. Steam Generator Blowdown uent Line 1 29

3. FLOW RATE MEASUREMENT DEV '

a. Boric Acid Cond ate Discharec 30 j j b. Waste, Was ondensate and Laundry Discharge 1 30 i

c. Turbi ullding Industrial Waste Sump

N.A. N.A.

j E j d. Cooling Tower Sumps

N.A. N.A.

{

i

}

Circulating Water Discharge * (Blowdown and Blowdown Heat Exchanger and Auxiliary Component Cooling Water Pumps) N.A.

l i i

?

j # Automatic termination of blowdown discharge only l 1 -

~

i

L. I TABLE 3.3-12 (Continued)

TABLE NOTATIONS

Pump performance curves' generated in place shall be us o estimate flow. 1 ACTION STATEMENTS ACTION 28 - Wit he number of channels OPERABLE less thar quired by the Minim releases via this pa ChannelsOPERABLErequirement,eff1)tsaremadeto ay may continue provided best ef7 repair th instrument and that prior to tiating a release:

l

a. At leas "wo independent sample re analyzed in accordance ,

with Spec' cation 4.11.1.1.1, id

b. At least two :hnically q .ified members of the Facility Staff independe ly verif ;he release rate calculations and discharge lin valv' ;

ACTION 29 - With the number of channe OPERABLE less than required by the Minimum Channels OPERAB r irement, effluent releases via this pathway may conti pro ded best efforts are made to repair the instrumen ad that ab samples are analyzed for radioactivity at a er limit o, etection of at least 10-7 microcurie /mL.

a. At least e per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when of the seco cry coolant is greater t ! specific activity / gram n 0.01 microcurie DOSE E . ALENT I-131, or

b. At st once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the spe fic activity of t secondary coolant is less than or eq to 0.01 micro-ie/ gram DOSE EQUIVALENT I-131.

ACTION 30 - Witd het number of channels OPERABLE less than requ d by the Mi mum Channels OPERABLE requirement, effluent relea. via s pathway may continue provided best efforts are ma to ipair the instrument and that the flow rate is estimate t east once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump perfo ance curves generated in place may be used to estimate flow.

N WATERFORD - UNIT 3 3/4 3-57 AMENDMENT NO. 17

TABLE 4.3-8

Ei y1 10 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS h CHANNEL i CHANNEL SOURCE CHANNEL FUNCTIONAL i i INSTRUMENT CHECK CHECK CALIBRATION TEST i E

G 1. RADI0 ACTIVITY MONITORS IDING i w ALARMS AND AUTOMATIC TE ATION OF RELEASE [

l

a. Boric Acid Condensate Disch P P R(3) Q(1)

b. Vaste, Waste Condensate and Lau P P R(3)

Discharge Q(1) :

c. Dry Cooling Tower Sumps D M R(3)

I Q(5) ;

d. Turbine Building Industrial Waste Sump R(3) Q(5) j

e. Circulating Water Discharge g) w 2

(Blowdown Heat Exchanger and Auxiligry Component Cooling Water i

w Pumps) M R(3) Q(5)

E 2. CONTINUOUS COMPOSITE SAMPLERS

{ a. Steam Generator Blowdown Ef fluent D(6) R Q !

3. FLOW RATE MEASUREMENT DEVICES !

j ] a. Boric Acid Condensate Di arge D(4) N.A. R Q

]

b. Waste Waste Condens and Laundry D(4) N.A. R Discharge Q !

i c. Turbine Buildi ndustrial Waste Sump N.A. N.A. N.A.

g d. Dry Coolin wer Sumps N.A. N.A. N.A.

c. N.A. ;

g e. Circul g Water Discharge >

y, (B !

down and Blowdown Heat z changers and Auxiliary ,

?

Component Cooling Water Pumps)

N.A. N.A. N.A. N.A.

y .

t i

Automatic termination of Blowdown discharge only i

_I____________.___ _ _ . _ _ - _ _ _ ~!

l l

TABLE 4.3 8 (Continued)

TABLE NOTATION (1 The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic is ation this pathway and control room alarm annunciation occur if any o he f lowing Conditions exists:

1. -- trument indicates measured levels above the alarm /tr setpoint.

2. Circ t failure.

. 3. Instrumt ' indicates a downscale failure.

(2) The CHANNEL FUNC ONAL TEST shall also demonstr that control room alarm annunciation ecurs if any of the follo g conditions exists:

1. Instrument indic es measured level ove the alarm setpoint.

2. Circuit failure.

(3) The initial CHANNEL CALIBRA LON 1 be performed using one or more of the reference standards certL i by the National Bureau of Stendards or using standards that have bee ibtained from suppliers that participate in measurement assurance ac it' s with NBS. These standards shall permit calibrating the sy m for ver its intended range of energy and measurement range. For sequent ANNEL CAllBRATION, sources that have f

been related to the in' al calibrat n shall be used.

(4) CHANNEL CHECK shall nsist of verifyin indication of flow during periocs

+

of release. CHAN CHECK shall be made least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which co nuous, periodic, or bat releases are made.

(5) The CHANNEL F $110NAL TEST shall clso demons ate that automatic isolation of this patt t y occurs if the instrument indica s measured levels above the alarin/ p setpoint and that control room al m annunciation occurs if any of he following conditions exists:

1. I rument indicates measured leve h above the rm set.

2. ircuit failurt:.

3. Instrument controls not set in operate mode.

(6) ANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on day on which continuous releases are made to the Circulating Water System o Waterford 3 waste pond.

L 4 DEL WATERFORD - UNIT 3 3/4 3-59 Amendment No. 1

MSTRUMENTATION RADICACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.11 The radioactive .;seous effluent monitori~ng instrumentation channels .

shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ens that +.he limits of Specification 3.11.2.1 are not exceeded. The ala trip oints of these channels shall be determined and adjusted in act nce with the 'ethodology and parameters in the ODCM.

APPLICABILIT - As shown in Table 3.3-13.

ACTION:

a. With'a radica ive gaseous effluent monitori _.-instrumentation channel alarm /t- setpoint less conserva > than required by the above Specificatio .immediately suspen 4he release of radioactive gaseous effluents mo 'tored by the a' cted channel, or declare the channel iroperable, or .ange the . . point so it is acceptably j conservative.

b. With less than the minimu, m%rofradioactivegaseouseffluent monitoring instrumenta ' channM OPERABLE, take the ACTION shown in Table 3.3-13. Re re the inope le instrumentation to OPERABLE status within 30 d or, if unsucces 1, explain in the next Semi- l annual Radioacti Effluent Release Repo pursuant to Specification 6.9.1.8, why -'s inoperability was not cor eted within the time specified. eleases need not be terminated a r 30 days provided the spec ed ACTIONS are continued. I

c. The <ovisions of Specifications 3.0.3 and 3.0.4 are applicable.

SURVE il.LA REQUIREMENTS ,

4.3. 21 Each radioactive gaseous effluent monitoring instrumentation c el sh be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE r CK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

REPLAG W rTH TEXT FRou Wen PA E WATERFORD - UNIT 3 3/4 3-60 AMENDMENT NO. 17 1

TNSTRUMENTATION MIE SIVE kM+kuGHVH GASFOUC !""" AH4FP MONITORING INSTRUMENTATION LIMITING COND1 TION POR OPERATION exploalve 3.3.3.11 The " " - gascotta -f fittete monitoring instrumentation channola shown in Tablo 3.3-13 nhall be OPERABLE with their Alarm / Trip Sotpointo set to ensure that the limits of Specificationa 3 11.2 1 and 3.11.2.5 are not exceeded. W Alarr,/ Trip P _ t pcint of--thes chunnele ri-cting ap cification 1.11.2.1 aberli i+ de% mincd and ftdittat ed in arcardener wit h tai r-thedricgy and-pnenmetcr- in ihc 9Estr APPLICABILITY: As shown in Table 3.3-13 ACTION:

explosivo

a. With an redicactive gasecw offla nt monitoring inntrumentation channeT Alarm / Trip Setpoint less conservativo than required by the above specification, 47.r e diatc ly uapend the rc imM rntHonct2V+ gn cs m T f f lttente i onit ored--by the affected chann--1, or declare the channel inoperable and take the ACTION shown in Tablo 3.3-13. ~

oxplonive

b. With less than the minimum number of radic active gasrc ac cffluent monitoring inst.rumentation channoin OPERABLE, take the ACTION nhown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 dayn and if unsuccessful explain in the neat F risatnttal i;ndienet-ive "f fluc it i;clcanc Pcpcrt preparo and .

submit a Special Report to the Commission pursuant to Qiocification G.9.1.4 6.'3.2 to explain why this inoperability was not corrected in a t.imely manner,

c. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVETLLANCE REQUIREMENTS explotuve 4.3.3.11 Each . udica:uvi g a s h,su c H4ttet* monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CilANNEL CllECK, 60tH406 GHE6H7 CilANNEL CALIBRATION and CilANNEL FUNCTIONAL TEST at the frequenclos t,hown in Table 4.3-9.

m ADO:

{gp TABLE 3.3-13 RADIDACTIVElGAkOUS' EFFLUENT)MONITORINGINSTRUMENTATION~

n p

o L DEL- O E t_. MINIMUM CHANNELS

-INSTRUMENT OPERABLE APPLICABILITY : ACTION I

g ]

~

1. WASTE GAS 110LDUP_ SYSTEM O ~

, a. Noble Gas Activity Monitor - '

Providing Alarm and Automatic Termination of Release 1

35- D ML '

b. Effluent System Flow Rate Measuring Device 1

36

2. bTE GAS 110LDUP SYSTEM EXPLOSIVE GAS i MONITORING SYSTEM

$ a. Hydrogen Monitor **

1 38

{

w (

b.

~

Oxygen Monitors 2 ** 40 f ML- -

3. MAIN CONDENSER EVACUATION AND TURBINE' -

GLAND SEALING SYSTEM

a. Noble Gas Activity Monitor 1

37

b. Iodine Sampler # 1

39 .

I

c. _ Particulate Sampler # 1

39 !

d. Sampler Flow Rate Monitor 1

36 I

-I

If a primary to secondary leak exists or if the noble gas monitors in-the main condenser evacuation and -

turbine gland sealing system or- if the steam generator blowdown monitor indicates the presence of radioactivity I in the secondary system, the flow from this release point shall be diverted immediately to the plant stack.

These instruments are in the plant stack and sampling for radioiodines and particulates shall occur at the plant vent when this occurs. _

i

, , . . . ,_m

TABLE 3.3-13 (Continued)

M RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l 4 '

@ MINIMUM CHANNELS I MENT OPERABLE APPLICABILI ACTION

@ 4. REACTOR AUXIL BUILDING q VENTILATION SYST w (PLANT STACK)

a. Noble Gas Activity Mon -

Providing Alarm and Autom Termination of Release # 1

37

b. Iodine Sampler

39

c. Particulate Sampler 1

39

$ d. Flow Rate Monitor

36

e. Sampler Flow Rate Monitor 1

36 S. FUEL HANDLING BUILDING VENTILATION SYSTEM (NORMA ;

a. Noble Gas Activi Monitor 1 *** 37

b. Iodine Samp 1

39

c. Particu e Sampler 1 *** 39 ;

d. Flo ate Monitor 1 ***

36

e. mpler Flow Rate Monitor 1 ***

f

Automatic termination of containment purge only.

l

(

4 i

TABLE 3.3-13 (Continued)

, TABLE NOTATIONS E

At all times.J - DEL

- During WASTE GAS HOLOUP SYSTEM operation. C)E.L_

h*Withirradiatedfuelinthestoragepool DE L ACTION STATEMENTS '

[ ION A 35 - With the number of channels OPERABLE'less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided best s are made to repair the instrument and that prior to ini ,ing .

the release:

At least two independent samples of the t s contents are analyzed, and

b. At ast two technically qualifie abers of the facility staf dependently verify the ase rate calculations and dis e valve lineup; ACTION 36 - With the number of nnels ABLE less than required by the Minimum Channels OPER uirement, effluent releases via this pathway may contin ovided best efforts are made to re-pair the instrument tha e flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , r the was as holdup tank this action item is applica only during pe ' ds of release. For the main

! condenser e tion and turbine 91 sealing systems, this action ite plies only during releas 'a the discharge silence d only during turbine gland se g operations and/or vacu ump operation.

ACTION 37 - the number of channels OPERABLE less than req d by the inimum Channels OPERABLE requirement, effluent relea via this pathway may continue provided best efforts are made re-pair the instrument and that grab samples are taken at lea

' once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . However, containment purging of

' radioactive effluents must be immediately suspended during this A condition for the plant stack only.

L ACTION 38'- With the number of channels OPERABLE-less than required by the l~

Minimum Channels OPERABLE requirement, operation of the WASTE GAS HOLDUP SYSTEM may continue provided best efforts are made to repair the instrument and that grab samples are collected at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for the onservice gas decay tank.

l l

WATERFORD - UNIT 3 3/4'3-63 AMENDMENT NO.17

TABLE 3.3-13 (Continued)

Da ACTION STATEMENTS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided best efforts are LACTION39-made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment as required in Table A 1'-1 ACTION 40 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the WASTE GAS HOLOUP SYSTEM may continue provided best efforts are made to repair the instrument and that the system is sampled by either the remaining monitor or by a grab sample at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and tne oxygen concentration remains less than 2L If there are no monitors OPERABLE, WASTE GAS HOLDUP SYSTEM operation may continue provided best efforts are made to return at least one channel to OPERABLE status and that a grab sample is taken and analyzed from the onservice gas decay tank at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and the oxygen concentration remains less than 11 With oxygen concentration exceeding 1%, reduce the oxygen concentration to less than 1% within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

WATERFORD - UNIT 3 3/4 3-64 AMENDMENT NO.17

9 Aco:

$1pt oseve C, Ab b TABLE 4.3-9 k RADIDACTIVEGASEOUSEFFLUENT)MONITORINGINSTRUMENTATIONSURVEILLANCEREQUIREMENTS E

3 CHANNEL- MODES IN MlICH

@ CHANNEL- SOURCE -CilANNEL FUNCTIONAL SURVEILLANCE

, INSTRUMENT CHECK CHECK' CALIBRATION TEST IS REQUIRED C

j'i 1. WASTE GAS HOLDUP SYSTEM

-e

" a. Noble Gas Activity Monitor -

Providing Alarm and Automatic [g Termination of Release P P R(3) Q(1) *

b. Effluent System Flow Rate Measuring Device P N.A. R Q

2. WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM

a. Hydrogen Monitor D N.A. Q(4) M **

T

$; b. Oxygen Monitors D N.A. Q(S) H **

3. MAIN CONDENSER EVACUATION AND' TURBINE GLAND SEALING SYSTEM -

a. Noble Gas-Activity Monitor D M R(3) _Q(2) * [ ,

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A. *

d. Sampler Flow Rate Monitor D N.A. R Q

m,

. TABLE 4.3-9-(Continued)-

g RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 28 g CllANNEL. MO IN WHICH o CilANNEL SOURCE CilANNEL FUNCTIONAL URVEILLANCE INSTRUMENT CllECK CHECK CALIBRATION TEST IS REQUIRED E

q 4. REACTOR AUXILIARY ING o y VENTILATION SYSTEM i i (PLANT STACK)

a. ' Noble Gas Activity Monitor - i Providing Alarm and Automatic-

f Termination of Release # D M R Q(6)

r

..b. Iodine Sampler W .A. N.A. N.A. *

, c. Particulate Sampler W N. .H.A. N.A.

D-

., d. Flow Rate Monitor 0 -

.A. Q

$ e. Sampler Flow Rate Monitor D N.A. R Q i S. FUEL llANDLING BUILDING !

VENTILATION SYSTEM (NORMAL)

! a. Noble Gas Activity Mo or D M R(3) Q(2 ***

! b. Iodine Sampler W H.A. N.A. N.A. ***

l

c. Particulate ampler W N.A. N.A. N.A. ***

, d. Flos R Monitor D N.A. R Q

l

e. Sa er Flow Rate Monitor D N.A. R Q ***

l

[

Au atic termination of' containment purge only.

P i

i TABLE 4.3-9 (Continued)

Oct TABLE NOTATIONS

- During WASTE GAS HOLOUP SYSTEM operation., __

- [ ***When irradiated fuel is in the spent' fuel pool. \

f MLp (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation

\

of this pathway and control room alarm annunciation occurs if any of the 1 following conditions exists: j

1. Instrument indicates measured levels above the alarm / trip setpoint. l

2. Circuit failure.

3. Instrument indicates a downscale failure. ,

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs .if any of the following conditions exists: j

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure. -

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate .

in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and i measurement ~ range. For subsequent CHANNEL CALIBRATION, sources that have

((4) Thebeen related to the initial calibration shall be used.

CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. Zerovolumeper5nthydrogen,.balancenitrogen,and

2. > Four volume percent hydrogen, balance nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. Zero volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance nitrogen.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation-Leci.y ~o f this pathway occurs if the instrument indicates measured -levels above the alarm / trip setpoint and that control room alarm annunciation occurs-

.if any of the following conditions exists:

1. Instrument. indicates measured levels above the alarm set.

2. Circuit failure..

3. Instrument controls not set in operate mode. /

l J

I-WATERFORD - UNIT 3 3/4 3-67 1

M4.11RADI0ACTIVEEFFLUENTS 3/ 1 LIQUID EFFLUENTS l CONCENT LIMITING CONDITIO ' R OPERATION ,

m 3.11.1.1 The concentra n of radioactive material >1 eased in liquid effluents to UNRESTRICTED AREAS (see igure 5.1-3) shall b imited to the concentrations specified in 10 CFR Part 20, 3endix B, Table , Column 2 for radionuclides other than dissolved or entrai noble gase for dissolved or entrained noble gases, the concentration sh be 11 sed to 2 x 10 4 microcurie /ml total activity.

At all times.

APPLICABILITY:

ACTION:

With the concentration of dioactive material re ed in -liquid effluents to UNRESTRICTED AREAS e eding the above limits, im iately restore the concentration to with' the above limits, and describe events iriding to this condition in t next Semiannual Radioactive Effluen elease 9 port.

SURVEILLANCE QUIREMENTS 4.11.1. Radioactive liquid wastes shall be sampled and analyzed ording to th sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in ac or-dance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are raintained within the limits of pecification 3.11.1.1, WATERFORD - UNIT 3 3/4 11-1 AMEN 0 MENT N0. 17

l

(

TABLE 4.11-1 010 ACTIVE LIQU10 WASTE SAMPLING AND ANALYSIS PROGRAM

\ LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF AC ITY (LLD)a TYPE EQUENCY FREQUENCY ANALY S (pCi/mL>

A. Batch Waste P P Release Each atch Each Batch Princ4 al Gamma 5x10 7 c

Tanks b ,f,g,h,i Emi >rs

1. Boric Acid 1x10 6 Condensate 1 [ 31 P M issolved and 1x10 5 Entrained Gases

2. Waste One BatcVM (Gamma Emitters)

Condensate P H-3 1x10 5 Each Batch Compos

. Laundry Gross Alpha 1x10 7 I Waste (

4. Turbine P Q Sr-89, Sr-90 5x10.s d

Building Each Batch mposite Industrial Waste Fe- 1x10 6 Sumps *

5. Dry Cooling Tower Sumps

1 and #2*

6. ' Regenerative Waste

7. Filter Flush

-8. Waste l

l l

i 1 release from this source is batch in nature.

'{

l 1-l l

WATERFORD - UNIT 3 3/4 11-2

MAy is '83 18:18 OATEL SE RVICES CORP. PAGE.03 r '

TAB.LE 4.11-1 (Continued)

.. lower L1HI F MINIMJM OF DETECTION LIQUID LEASE SAMPL]HG ANALYSIS TYPE OF T1YlTY (LLD)a FREQUENCY FREQUENCY Y315 . (pct /rit)

8. Continuo W W P ipal Ganna 5x10 7 Releases esf c

. Grab sample ftters

1. Turbine I-131 1x10 8 Sufiding Industrial h Wute Sumps **. .

M Dissolved and 1x10 5

2. Dry Cooling Sample Entrained Gases .

Tower 1 (Gansa Emitters)

.g plaa .

4

3. Dry Cooling 'W .

M d

H-3 M05 Tower i Grab Sa Composite N 82" '

Grost Alpha 1x10 7

4. Clitulating Q 3"O ' "

sita d

. Water G Sample Discharge- . Fe-55 1x.10 8

. .. Steam Cene-rator Blow- -

down HX

5. Auxiliary C nent Cooling Vater Pumps When release from this source is continuous in nature.

i .

,. MAY l6 'B3 I8:e! QRTEL SERVICES CORP. PAFE B6 TABLE 4.11-1 (Continued)

'1 ' *

/ LOWER LIMIT

. KININUM LIQUID RELEASE $AR?L1HG:',- 0F DETECTION ANALYSIS TYPE OF ACTIV1 YT7E ENCY (LLD)a T1tEQUENCY ANALYSIS (uC1/mL)

B. Continuous Beleases e,f W

k V

d PTfDCIPal, a 5xj0'I Contin s Composite Emitters 6 Sters Cenerator I-131 lx10-6 Blevdown Dischirge j.I ,

H D solved and lx10-5 Grab Sample trained Cases maa Emitters)

U N -3 lx10 ~0 Continnocs Composit Creas pha Ix10~

W Sr-89 St- Sx10" Continuousk osite#

,, Te-55 .

Ix10-6 k

VATERFOR.D - UntT 3 3/4 11-3a M 6W ENT NO. 1

- , . . - . - . - - - - - ~ . - - - - - - = ~ ~ ~ - = = = = ~'*"-****--""**"*""*""***""**'"*"**""*""

i TABLE 4.11-1 (Continued) 1ABLE NOTATION a

The LLD is efined, for purposes of these specifications, a he smallest concentrati of radioactive material in a sample that wil yield a net count, above system ackground, that will be detected with 95% obability with only 5% probabilit of falsely concluding that a blank obser tion represents a "real" signal.

For a particular easurement system, which may incl Je radiochemical separation:

4' D LLO =

E*V- .22 x 106 Y exp ( t)

Where:

LLD is the "a priori" i er limit of etection as defined above, as microcuries per unit mas or volume ss is the standard deviati of ie background counting rate or of the c0unting rate of a blank sa. e s appropriate, as counts per minute, E is the counting efficiency, counts per disintegration,

( V is the sample size in un s of 1ss or volume, 2.22 x 108 is the number of disinte ations per minute per microcurie, Y is the fractional r iochemical yie when applicable, A is the radioacti decay constant for e particular radionuclide, and 6t for plant eff ents is the elapsid time etween the midpoint of sample collection and e time of counting.

Typical valu of E, V, Y, and at should be u d in the calculation.

It should be cognized that the LLT, i, defined as a priori fact) limit presenting the capabill*.y of a measure t systi.:,(before ano not tre as an a posterior (after the fact) limif. for a particular surement.

b A batch ease is the discharge 0: liquid wastes of a crete volume.

Prior t sampling for analyses, ea:h baten shall be isnl d, and then thorou ly mixed by a method descr' bed in the ODCM to ass representative sampi g, i

WATERFORD - UNIT 3 3/4 11-4

( TABLE 4.11-1 (Continued)

TABLE NOTATIONS C

The princ al gamma emitters for which the LLO specification appl >s include th following radionuclides: Mn-54, Fe-59, Co-58, Co-6 Zn-65, Mo-9 Cs-134 Cs-137, Ce-141, and Ce-144. This list d s not mean that only the nuclides are to be considered. Other gamma p ks that are identifiable, gether with those of the above.nuclides, sha also be analyzed and reported in he Semiannual Radioactive Effluent Release eport pursuant to Specification 6. .8.

d A composite sample one in which the quantity of liqu . si.mpled is proportional to the quantity of uid waste discharged and in whic the method of sampling employed results in a ecimen that is representative f t'ie liquids released.

'A continuous release is discharge of liquid was s rf a nondiscrete volume, e.g., from a volu.. of a system that has a input flow during the continuous release.

P rior to analyses, all sample aken for the c osite shall be thoroughly mixed in order for the composit sample to be epresentative of the effluent release.

91f the contents of the filter flus ank o the regenerative waste tank

. contain detectable radioactivity, no isc rges from these tanks shall be made

- to the UNRESTRICTED AREA and the conte of these tanks shall be directed to

( the liquid radwaste treatment system.

h Turbine Building Industrial Waste Su . (T 5)

. . _ The TBIWS shall be required to be ampled an analyzed in accordance with this table if any of the following co itions exis (1) Primary to secondary akage is occurr ; or, (2) Activity is presen .n the secondary syst as indicated by either the SGB monitors secondary sampling an nalysis; or, (3) Activity was pr ent in the TBIWS during the evious 4 weeks.

If none of the above s~ uations exists, then the samplin and analysis of this stream need not be p 'ormed.

l I

sampling and analy s of the dry cooling tower sumps and the uxiliary component cooling water pum discharge will be required only when detec ble activity exists in the C Sampling and a lysis of the circulating water discharge-steam ge rator blowdown heat xchanger discharge (CWD-SGB) will be required only en detectable a ivity exists in the secondary system.

(

WATERFORD - UNIT 3 3/4 11-5 L

1

...* May is *05 10:25 QRTEL SERVICES CORP. PAGE.07 yble4.11-1(Continued)

TABLE NOTATIONS

't.

y .,

Sampling and sealysis of t steam generator blovd vill be required only when the blevdova is di ted to the circulat water system or' Waterford 3 waste pond.

, ,, Steam generator blevdovu to the terford 3 was pond vill be limited to situations requiring secondary e - stry contr where the Circulating Vater System is not available or th seconda chemistry is outside the requirements for Circul. sting Vater S tem d rge. Blovdown to the vaste pood will be terminated apoo ,de ett of samplea 'ctivity greater than the LLD liivels of Table 4.11-1 Se B.*

,. To be repres'entative of the quantitie concentration of radioactive materials in liquid effluents, sampi sha be collected continuously in proportion to the rate of flow o the e uent stream.

I Steam generator blowdown dischar to the was pond shall be limited to a period of six months with circulating ater system discha'rge'

,, path not available unless radi . ion monitoring automatic isolation capabilities are added to the aste pond discha pa th.

l 1

e i

i

\

VATERJORD - UNIT 3 3/4 11-Sa AMFNDMrNT NO. 1

I,,, IO I,.6,.[m0.9 E,;,0,1,,,*,*,,,,,,,

, - . . -- , ,, , -w,,m

RADIOACTIVE EFFLUENTS DOSE LIMITING TION FOR OPERATION 3.11.1.2 The do or dose commitment to a MEMBER OF THE P IC from radioactive materials in liqui effluents released to UNRESTRICTED A 5 (see Figure 5.1-3) shall be limited:- .

a. During any cai dar quarter to less than equal to 1.5 mrems to the total body d to less than or equa' o 5 mrems to any organ, and

b. During any calendar r to less t or equal to 3 mrems to the total body and to less han or e to 10 mrems to any organ.

APPLICABILIT/: At all times.

ACTION:

a. With the calculated dos rom th release of radioactive materials in liquid effluents e eding any the above limits, prepare and submit to the Commis n within 30 s, pursuant to Specifica-tion 6.9.2, a Spec' Report that-ide ifies the cause(s) for exceeding the li .(s) and defines the rrective actions that have been take reduce the releases a the proposed corrective actions to be en to assure that subsequ t releases will be in compliance wi the above li. nits. This Spe 'al Report shall also include (1)Jhe results of radiological analy s of the drinking water sour p and (2) the radiological impact o finished drinking water su ies with regard to the requirements o 40 CFR Part 141,

b. The p isions of Specifications 3.0.3 and 3.0.4 ar not applicable.

SURVEILLANCE QUIREMENTS 4.11.1.2 umulative dose contributions from liquid effluents for the urrent-calend uarter.and the current calendar year shall be determined in cordance with t methodology and parameters in the ODCM at least once per 31 day l

i WATERFORD - UNIT 3 3/4 11-6

RADI0 ACTIVE EFFLUENTS LIQUID MDWASTE TREATMENT SYSTEM LIMITING x

TION FOR OPERATION

[

3.11.1.3 The liq *d radwaste treatment system shall be OPERABLE a appropriate portions of the sys m shall be used to reduce releases of radica vity when the projected doses d to the liquid. effluent to UNRESTRICTED AS (see Figure 5.1-3),would exce 0.06 mrem to the total body or 0.2 em to any organ in a 31 dey period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid was being dis rged without treatment and in excess of the above limits nd any rtion of the liquid radwaste treatment system not in operati , are and submit to the Commis-sion within 30 days pursuant to S fication 6.9.2 a Special Report that includes the following info ion:

1. Explanation of why liqu' radwaste as being discharged without treatment, identifica n of any ino rable equipment or subsystems, and the son for the in rability,

.( 2. Action (s) taken restore the inoperable quipment to OPERABLE status, and

3. Summary de iption of action (s) taken to prev a recurrence,

b. The provisi of Specifications 3.0.3 and 3.0.4 are no applicable.

SURVEILLANCE R REMENTS 4.11.1.3. oses due to liquid releases to UNRESTRICTED AREAS shall be p ected at least o ce per 31 days in accordance with the methodology and parameters in the ODCM, 4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be demonstrated OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

WATERFORD - UNIT 3 3/4 11-7

i RADIOACTIVE EFFLUENTS 3/4.11.hASE005 EFFLUENTS O

DOSE RATE LIMITING CONDITI FOR OPERATION s .-

3.11.2.1 The dose r a due to radioactive materials re sed in gaseous effluents from the sit to areas at and beyond the SIT BOUNDARY (see Figure 5.1-3) shall be limited the following:

a. For noble gases: ess than or equal t 00 mrems/yr to the total body and less than equal to 3000 ms/yr to the skin, and

b. For iodine-131, iodine 33, for ium, and for all radionuclides in particulate form wit alf-l' >s greater than 8 days: Less than or equal to 1500 mrems/yr o organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate (s) excee ' the above li 'ts, immediately restore the release rate to within the ove limit (s), an . escribe the events leading to this condition in the xt Semiannual'Radioa ive Effluent Release Report.

t-SURVEILLANCE REQUI .ENTS 4.11.2.1.1 d'ose rate due to noble gases in gaseous fluents shall be determine be within the above limits in accordance wit the methodology and par ers in the 00CM.

4.11. 1.2 Representative samples and analysis of gaseous eff nts shall be obtained in accordance with the sampling and analyses program sp ified in Table 4.11-2.

4.11.2.1.3 Based upon the sampling and analysis performed in Table 4.11-2 the dose rate due to I-131, I-133, H-3, and all other radionuclides in particulate form with half-lives greater than 8 days shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

WATERFORD - UNIT 3 3/4 11-9

TABLE 4.11-2 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM o MINIMUM LOWER LIMIT OF-E SAMPLING . ANALYSIS TYPE OF DETECTION (L i

G k RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCi/m c P P 3

A. Vaste lloldup Each Tank Each Tank Principal Gamma Emitters b y Tanks Grab Sample c

B. Containment PUR Each URGE' Each PURGE Principal Gamma Emitters h 1x10 4 (Plant Stack) rab Sample C

M ll-3 [ 1x10 8 C 1 Plant Stack M'* Principal Noble Gas a 1x10 4 b

Grab Samp M Emitters 11- 3 1x10 6 R

C.2 Fuel Handling M**) Principal le Gas Gamma 1x10 4 Building Ven- Grab Sample M Emitte C tilation H-3 1x10 6 4 (Normal)

Exhaust D.1 All Release Types Continuousf ,h,j gg I-1 1x10 i2 ds listed in Charcoal B., C.1, and Samp1 I-133 1x10 10 C.2 above D.2 Main Condenser Continuousf ,h,j gg 1x10 81 PrincipagParticul Gamma Evacuation and Particulate Emitters Turbine Gland Sample Sealing System

, Ce .auousf ,h,j H Gross Alpha 0 18 l Composite Particulate Sample f ,h, Continuous Q Sr-89, Sr-90 1x10 11 Composite Particulate

, Sample l Continuous * ') Noble Gas Noble Gases 1x10 8 Monitor Gross Beta or Gamma

i TABLE 4.11-2 (Centinued)

TABLE NOTATION a

The LLO i efined, for purposes of these specifications, as th smallest concentrati of radioactive material in a sample that will y d a net count,

, above system ekground, that will be detected with 95% prob ility with only 5% probabilit f falsely concluding that a blank observati represents a "real" signal, For a particular . surement system, which may include diochemical separation:

4' S b

LLO =

E V 2. i x 106 Y exp (-AA Where:

LLO is the "a priori" low limit of de >ction as defined above, as microcuries per unit mass o volume, sb is the standard deviation o the ackground counting rate or of the counting rate of a blank sample appropriate, as counts per minute, E is the counting efficiency, a c ts per disintegration,

( V is the sample size in units f mass volume, 2.22 x 106 is the number of disintegrati s per minute per microcurie, Y is the fractional radi hemical yield, w applicable, A is the radioactive cay constant for the p icular radionuclide, and ,

at for plant efflu ts is the elapsed time betwe the midpoint of sample collection and th time of counting.

Typical values E, V, Y, and at should be used in calculation.

It should be rec nized that the LLD is definet as an a r1 i (before the fact) limit rep senting the capability of a measurement sys and not as an a posteriori ( ter the fact) limit for a parti:ular measureme i

i l

t WATERFORD - UNIT 3 3/4 11-11

TABLE 4.11-2 (Continued)

TABLE NOTATIONS b

The p ncipal gamma emitters for_ which the LLD specification appl >s include the fo wing radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe- 5, and Xe-138 noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Z 65, Mo-99, I-131, I 3, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine an particulate releases. .-his list does not mean that only these nuclides e to be considered. Other gamma peaks that are identifiable, toget >r with those of the above nu ides, shall also be analyzed and reported i the Semiannual Radioactive E' uent Release Report pursuant to Specific ion 6.9.1.8.

C Sampling shall a be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months foil ing shutdown, startup, or a THERMAL POWE hange exceeding 15% of RATED THE AL POWER within a 1-hour period. Ana sis for principle gamma emitte , as defined in (b) above shall be compi d within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of sampli g.

! d Tritium grab samples sh 1 be taken at least on per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flood

' Tritium grab samples shall taken at leas once per 7 days from the ventilation exhaust from the ent fuel po area, whenever spent fuel is in the spent fuel pool.

I The ratio of the sample flow rate t i sampled stream flow rate shall be known for the time period covered ach dose or dose rate calculation made

( in accordance with Specifications 3 2.1, 3.11.2.2, and 3.11.2.3.

9 5amples shall be changed at leas once 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after hanging, r after removal from sampler.

Sampling shall also be perfor. at least e per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdo , startup or MAL POWER change exceeding 15% of RATED THERMAL POWER 1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and anal s shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changi . When samples coll ed for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the correspon g LLDs may be increase a factor of 10. This requirement does not a ly if (1) analysis shows t the DOSE EQUIVALENT I-131 concentration in the imary coolant has not increas more than a factor of 3; and (2) the nobl gas monitor shows that effluent ivity has not increased more th- a factor of 3.

h If no primary secondary leakage exists, then only the g s beta or gamma l noble gases a lysis need be performed for the main condense vacuation and turbine gla sealing system. If a primary to secondary leak ists and the release fr the main condenser evacuation and turbine gland se ng system has not b n released via the plant stack, then the sampling and lysis i must be erformed.

I Note ) above is not app'icable for the plant stack unless the noble s mon .or shows that effluent activity has increased by a factor of 3.

3 F al Handling Building sanpling is required whenever irradiated fuel is i e storage pool.

(

WATERFORD - UNIT 3 3/4 11-12

.. . . - - . - - . . = - - . - . .. - . - - - - . . - .

RADIOACTIVE EFFLUENTS DOSE - NdIBEm0ASES LIMITING COND FOR OPERATION 3.11.2.2 The air dose 'e to noble gases released in gas s effluents to areas at and beyond the SITE B ARY (see Figure 5.1-3) shal e limited to the following:

a. During any calendar q ter: Less than equal to 5 meads for gamma radiation and les han or equ so 10 mrads for beta radiation and,

b. During any calendar year: Le .han or equal to 10 mrads for gamma radiation and less than or o 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION

a. With the cale ed air dose from radioac e noble gases in gaseous effluents e eding any of the above limits, repare and submit to ,

the Comm' on within 30 days, pursuant to Sp ification 6.9.2, a Specia ,eport that identifies the cause(s) for xceeding the '

limi . ) and defines the corrective actions that ve been taken

t educe the releases and the proposed corrective tions to be en to assure that subsequent releases will be in pliance with the above limits.

, The. provisions of Specifications 3.0.3 and 3.0.4 are not licable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and-current calendar year for. noble gases shall be vetermined in accordance with the methodology and parameters in the 00CM at least once per 31 days.

t WATERFORO - UNIT 3 3/4 11-13 l

i l

1 I

RADIOACTI EFFLUENTS DOSE - IODIN 1, 10 DINE-133, TRITIUM, AND RADIONUCLIOES IN PARTI TE FORM LIMITING CONDITI OR OPERATION 3.11.2.3 The dose to a EMBER OF THE PUBLIC from iodine-13 iodine-133, tritium, and all radionuc ' des in particulate form with h . -lives greater than 8 days in gaseous effl nts released to areas at a . eyond the SITE BOUNDARY (see Figure 5.1-3) s 11 be limited to the fo wing:

a. During any calendar qu ter: Less than o qual to 7.5 mrems to any organ and,

b. During any calendar year: ss than equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose f m the rele e of iodine-131, iodine-133, tritium, and radionuclid in particulot form with half-lives greater than 8 days, in aseous effluents ceeding any of the above limits, prepare and s it to the Commissio within 30 days, pursuant to Specification 6.9 , a Special Report that dentifies the cause(s) l it and defines the correc 've actions that have forexceedingthe'bthereleasesandthepropos been taken to red corrective actions to be taken to ure that subsequent releases wil be in compliance with the above mits,

b. The provisi of Specifications 3.0.3 and 3.0.4 are not licabl2.

SURVEILLANCE REQUI ENTS 4.11.2.3 Cum ive dose contributions for the current calendar quarter and current cale r year for iodine-131, iodine-133, tritium, and radionuclides in particulat orm'with half-lives greater tnan 8 days shall be determined in accordan with the methodology and parameters in the 00CM at least once per 31 days.

WATERFORD - UNIT 3 3/4 11-14

I l

% l 10 ACTIVE EFFLUENTS GA RA0 WASTE TREATMENT LIMITIN DITION FOR OPERATION 3.11.2.4 The TILATION EXHAUST TREATMENT SYSTEM and the WA GAS HOLDUP SYSTEM shall be C RABLE and appropriate portions of these s' ems shall be used to reduce rele es of raoicactivity when the projected oses in 31 days due to gaseous efflue releases to areas at and beyond th SITE BOUNDARY (see Figure 5.1-3) would exc d either:

a, 0.2 mrad to air . m gamma radiation, or

b. 0.4 mrad to air fro. eta radiation, or

c. 0.3 mrem to any organ o a MEMBER OF TH dBLIC.

APPLICABILITY: At all times.

ACTION:

a. With radioactive gassous waste g discharged without treatment and in excess of the above lim < s, repare and submit to the Commis-sion within 30 days, pursuant ,o Sp ification 6.9.2, a Special Report that includes the fol wing in rmation:

1. Identification of any noperable eq pment or subsystems, and the reason for the i perability,

2. Action (s) taken t restore the inoperab equipment to OPERABLE status, and

3. Summary descr' ion of action (s) taken to p vent a recurrence,

b. The provisions o Specifications 3.0.3 and 3.0.4 ar not applicable.

SURVEILLANCE RE0VIREMEN" 4.11.2.4.1 Doses du o gaseous releases to areas at and beyond th ITE

. BOUNDARY shall be p Jected at least once per 31 days in accordance the methodology and pa meters in the 00CM.

4.11.2.4.2 Th stalled Gaseous Radwaste Treatment System, shall be demonstrated 0 RABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

J l

WATERFORD - UNIT 3 3/4 11-15

RADI0 ACTIVE _E ELUENTS 3/4.11.3 SOLI A010 ACTIVE WASTE LIMITING CCNDITI FOR OPERATION

. .f 3.11.3 Radioactive stes shall be SOLIDIFIED or dewatered in ordance with the PROCESS CONTROL GRAM to meet shipping and transportati requirements during transit, and d osal site requirements when received the disposal site.

APPLICABILITY: At all t s.

ACTION:

a. With SOLIDIFICATION . dewatering not me ng disposal site and shipping and transpor.

ion requirement suspend shipment of the inadequately processed tes and corr t the PROCESS CONTROL PROGRAM, the procedures, d/or the id waste system as necersary to prevent recurrence,

b. With SOLIDIFICATION or dewat in ot performed in accordance w'M.

the PROCESS CONTROL PROGRAM, test tM improper iy p; ccessec wast:t in each container to ensure it a,eets burial ground and s'iippir,g requirements and (2) take a op te administrative action te prevent recurrence.

c. With the installed equi nt incapa ~ of meeting Specification 3.11.3

(. or declared inoperable restore the e ipment to OPERABLE status or provide for contract pability to pro ss wastes as necessary to satisfy all applica transportation a disposal requirements.

I l

d. The provisions of pecifications 3.0.3 an .0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 SOLIDIFICATION at least one representative tc specimen from at least every tenth batch of h type of wet radioactive wastes g., filter sludges, l

spent resins, evapor r 'ottoms, boric acid solutions, and odium sulfate rei.ed in accordance with the PROCESS TROL PROGRAM, solutions) shall be

a. If any t t specimen fails to verify SOLIDIFICATION, he SOLIDIFICATION l

of the tch under test shall be suspended until such ime as additional test s cimens can be obtained, alternative SOLIDIFICA N parameters can b determined in accordance with the PROCESS CONTRO ROGRAM, and ubsequent test verifies SOLIDIFICATION. SOLIDIFI ION of the tch may then be resumed using the alternative SOLIO CATION par eters determined by the PROCESS CONTROL PROGRAM.

5. If he initial test specimen from a batch of waste fails to ify l- IDIFICATION, the PROCESS CONTROL PROGRAM shall provide for e 11ection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION.- The PROCESS CONTROL PROGRAM shall be modified as' required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent ll 1

batches of waste.

l WATERFORD - UNIT 3 3/4 11-18

RADI0 ACTIVE EFFLUENTS 3/4.1kTOTALDOSE LIMITING O! TION FOR OPERATIdN 3.11.4 The val (calendar year) dose or dose commitment t ny MEMBER OF THE PUBLIC due relases of radioactivity and to radiatic rom uranium fuel cycle sources s 1 be limited to less than or equal to

mrems to the total body or any organ, xcept the thyroid, which shall be ited to less than or equal to 75 mrems.

APPLICABILITY: At al imes.

ACTION:

a. With the calcula doses from the ease of radioactive materials in liquid or gaseo effluents ex ding twice the limits of Specifi-cation 3.11.1.2.a.

1.1.2.b, .2.2.a, 3.11.2.2.b, 3.11.2.3.a.

.or 3.11.2.3.b, calcul, ions sh - be made including direct radiation contri.butions from the . act units and from outside storage tanks to determine whether the a limits of Specification 3.11.4 have been exceeded. If such is e case, prepare and submit to the Commission within 30 day rsuant to Specification 6.9.2, a Special Report that defines th orr tive action to be taken to reduce subsequent releases t reven .ecurrence of exceeding the above limits and includes e schedul for achieving conformance with the above limits. Thi pecial Repo , as defined in 10 CFR 20.405c, shall include an lysis that es ates the radiation exposure (dose) to a MEM OF THE PUBLIC f uranium fuel cycle sources, including all luent pathways ana ' rect radiation, for the calendar year hat includes the relea s) covered by this report.

It shall al describe levels of radiat n and concentrations of radioactiv aterial involved, and the c e of the exposure levels or conce ations. If the estimated dose ' exceeds the above j i limits, d if the release condition result < in violation of 40 CF art 190 has not already been correcte the Special Report shal' nelude a request for a variance in acco nce with the l pr ions of 40 CFR Part 190. Submittal of the eport is con-si . ed a timely request, and a variance is grant until staf f on on the request is complete.

l

b. le provisions of Specifications 3.0.3 and 3.0.4 are t applicable.

SURVEI NCE REQUIREMENTS l

\.

l 4.1 .1 Cumulative dose contributions from liquid and gaseous effl ts

! sh be determined in accordance with Specifications 4.11.1.2, 4.11. and 4.11.2.3, and in accordance with the methodology and parameters in the CM.

4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from radwaste' storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Specification 3.11.4.a.

m WATERFORD - UNIT 3 3/4 11-19 l i

l' l

,w- , -

s . /

3/4.11RADIOLOGICALENVIRONMENTALMONITORING 3/4.12. ONITORING PROGRAM LIMITING C ITION FOR OPERATION 3.12.1 The ra ological environmental monitoring prograrr hall be conducted as specified in able 3.12-1. ,

APPLICABILITY: At 11 times.

ACTION:

a. With the radio gical environmental mon';oring program not being conducted as spe 'fied in Table 3.12-1 prepare and submit to the Commission, in th Annual Radiologica ' Environmental Operating Report required by ecification 6.9 .7, a description of the reasons for not con ting the prog m as required and the plans for preventing a recu ence,

b. With the level of radioa ivity a the result of plant effluents in an envircnmental sampling 1edi 'at a specified location exceeding the reporting levels of Ta e . 12-2 when averaged over any calendar quarter, prepare and submit 'the Commission within 30 days, pursuant to Specificatan 6.9.2, a Sp 1 Report that identifies the cause(s) for exceeding the limit (s) d efines the corrective actions to be taken to reduce radioacti eff ents so that the potential annual

( dose

to A HEMBER OF THE .UBLIC 1 less than the calendar year limits of Specification ,3.11.1.2, .11.2.2, and 3.11.2.3. When more than one of the r ionuclides Table 3.12-2 are detected in the sampling mediu , this report hall be submitted if:

concentratiory 1) , ,loncentr ion (2) ...) 1.0 reporting le (1) recorting evel (2) .

When radionucli other than those in Tab 3.12-2 are detected and are the result plant effluents, this rep t shall be submitted if the potential nual dose

to A MEb8ER OF TH PUBLIC is equal to or greater than le calendar year limi *.s of Spec 'ications 3.11.1.2, 3.11.2.2, a 3.11.2.3. This repor. is not re ired if the measured level of r ioactivity was not the iesult of pla t effluents; however, in such a event, the condition shall be reporte ind described in i the Ann Radiological Environmental Operating Re rt,

c. With k or fresh leafy vegetable samples unavailab from one or more the sample locations required by Table 3.12-1, identify loc ons for obtaining replacement samples and add the to the

! ra logical environmental monitoring program within 30 s. The

^The met ology and parameters used to estimate the potential annual se to a MEND F THE PUBLIC shall be indicated in this report.

i WATERFORD - UNIT 3 3/4 12-1

, RADIOLOGICAL _ENVIRONM TAL MONITORING LIMITING CON 0! TION FOR 0 TION (Continued) pl10N: (Continued) specific locations fron. >hich sampl were un vailable may then be deleted from the monitor progr . Pu suant to Specification 6.9.1.8, identify the caus of t unavaiaability of samples and identify the new location (s) '

obtaining replacement samples in the next Semiannua". Radioacti Effluent Release Report and also incisde in the report a rev >d 'gure(s) and table for the 00CM ref!ectirg the new locatic s).

d. The provisions of Speci cations 3.0. and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS , s 4.12.1 The radiological e ronmental monitoring samp s shall oe collected pursuant to Table 3.12-1 m the specific locatior.s giv in the table and figure (s) in the ODCM, . shall be analy:ed pursuant to t requirements of Table 3.12-1 and the d ction capabilities required by Tabl 4.12-1.

f l\

l WATERFORD - UNIT 3 3/4 12-2 l .

i

TABLE 3.12-1 A

?? RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

E NUMBER OF~

REPRESENTATIVE E EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FRE CY

3 AND/OR SAMPLE SAMPLE LOCATION 5* COLLECTION FREQUENCY OF ANAL 3 I " b

1. ECT RADIATION 31 routine monitoring stations Quarterly Gamma e quarterly.

j either with 2 or more dosimeters or with one

- instrument for measuring and recording dose rate continuously,

laced as follows

an ring of stations, one in

< o, each me logical sector in the 3: general are the SITE BOUNDARY, w

7 an outer ring of st s, I in 10 of the meteorologica ctors '

in the 6- to 8-km range fr e site; the balance of the stations to be placed in special ' erest areas such as populat' centers, nearby residences, 1s, and in 1 or 2 areas serve as control stations. ,

The number, media, freque nd location of samples may vary from site to site. This table ents an l acceptable minimum prog or a site at which each entry is applicable. Local site characterists must be examined to reine if pathways not covered by this table may significantly contribute to an !

individual's dose should be included in the sampilng program.

% TABLE 3.12-1 (Continued)

A ig RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

E o

NUMBER OF REPRESENTATIVE g EXPOSURE PATliWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY q AND/QR SAMPLE SAMPLE LOCATIONS, COLLECTION FREQUENCY Of ANALYSIS

2. AIR Radioion and Samples from 5 locations Continuous sampler RadiciodL Cannister:

Particula operation with sample I-1 inalysis weekly.

3 samples from close to the collection weekly, or ITE BOUNDARY locations, in more frequently if di nt sectors., of the required by dust articulate Sampler:

highes culated annual average loading. Gross beta radioactivity ground-lev Q. analysis folleging

, filter change; g I sample from the "nity of a Gamma isotopic analysis, y coeraunity having the st of composite (by

'? calculated annual average location) quarterly.

ground-level D/Q.

I sample from a control location, as for example 15-30 km distant and in winddirection.gheleastpreva

3. WATERBORNE

a. Surface # 1 sample upstr Compositesampfeover isotopic analysis' I sample d ream 1-month period month , Composite for tritium a

, sis quarterly.

b. Ground 5 es from 1 or 2 sounes Quarterly Gamma is topic tritium b

aly if likely to be affected analysis quarterly.

- m g TABLE 3.12-1 (Continued)

A q RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

E c) NUMBER OF REPRESENTATIVE gj EXPOSURE PATilWAY SAMPLES AND SAMPLING AND 1YPE AND FREQUENCY l

q AND/OR SAMPLE SAMPLE LOCATIONS, COLLECTION FREQUENCY OF ANALYSIS un

c. rinking 1 sample of each of 1 to 3 of Composite sample I-131 analy on each composite the nearest water supplies that over 2-week period 9 when the e calculated for the could be affected by its when I-131 analysis cons on of the water is discharge. is performed, monthly gre than 1 mrem per year.y

~

composite otherwise C osite for gross betg and isotopic analyses monthly.

Ccmposite for tritium analysis quarterly.

un e

d. Sediment 1 sample from downstr , rea Semiannually -

Gamma isotopic analysis y from with existing or potentia semiannually.

q> shoreline recreational value.

v.

4. INGESTION

a. Milk Samples from milking animals Semimonthly Gamma isotopic' and 1-131 in 3 locations within 5 km animals are on analysis semimonthly when distance having the highe pasture; monthly at animals are on pasture; dose potential. If the are other times ly at other times.

none, then, I sampic om milking animals in each areas between 5 to 8 km dis where doses are calcui gtobegreaterthan 1 mres yr .

mple from milking animals !

et a control location 15-30 km 1 distant and in the least prevalent wind direction.C i

e

jE TABLE 3.12-1 (Continued)

M

$; RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

E o NUMBER OF REPRESENTATIVE g EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUEN

q AND/OR SAMPLE SAMPLE LOCATIONS, COLLECTION FREQUENCY OF ANALYSIS __

b. h and I sample of each commercially Sample in season, or Gamma isoto c analysis' te- and recreationally important semiannually if they on edib1 ortions.

brate. species in vicinity of plant are not seasonal discharge area.

I e of same species in areas 'nfluenced by plant discharge.

{$ c. Food I sample of each ipal class At time of ha _t i Gamma isotopic analysis

Products of food products from area on edible portion.

q> that is irrigated by wate es which liquid plant wastes hav discharged.

Samples of 1 to 3 different ki onth y n Gamma isotopic' cnd I-131 of broad leaf vegetation g available analysis.

nearest each of two differ offsite locations of hi _st predicted annual ave e ground-level D/Q if milk spling is not performed.

I sample each of the similar Monthly when Gamma isotopi d I-131 broat af vegetation grown available analysis.

1 km distant in the least i

evalent wind direction if milk sampilng is not performed.

_ _____m-s

. - _ _ - _- . . - - - .- =

TABLE 3.12-1 (Continued)

TABLE NOTATIONS a

Specific parameter of distance and direction sector from the cen line of one reactor, and add ional description where pertinent, shall be rovided for each and every sample cation in Table 3.12-1 in a table and fi re(s) in the ODCM. Refer to NUREG-0 , " Preparation of Radiological Efflue Technical Specifications for Nucle Power Plants," October 1978, and to adiological Assessment Branch Technica Position, Revision 1, November 15 . Deviations are permitted from the requ d sampling schedule if specim are unobtain-able due to hazardous conditi s, seasonal unavailability, alfunction of automatic sampling equipment a other legitimate reasons If specimens are unobtainable due to sampling equ ment malfunction, corr ive action shall be completed prior to the end of the ext sampling period. All deviations from the sampling schedule shall be docu nted in the Annua adiological Environ-mental Operating Report pursuant to ecification 6.9 .7. It is recognized that, at times, it may not be possibi r practicabl to continue to obtain samples of the media of choice at the m t desired cation or time. In these instances suitable alternative media and cations ay be chosen for the particular pathway in question and appropr te s titutions made within 30 days in the radiological environmental m it ng program. Pursuant to Specification 6.9.1.8, identify the cause of unavailability of samples for that pathway and identify the new locatio ) for obtaining replacement samples in the next Semianuual Radioactive Ef t Release Report and also include in the report a revised. figure (s) a tab for the 00CM reflecting the new location (s).

I b 0ne or more instruments, such as a pres rized ion mber, for measuring and recording dose rate continuously may be sed in place , or in adaition to, integrating dosimeters. For the purpo .s of this table, a thermoluminescent dosimeter (TLD) is considered to be . phosphor; two or ore phosphors in a packet are considered as two or mot Josimeters. Film ta s shall not be used as dosimeters for measuring d ct radiation. The fre ency of analysis or readout for TLD systems will d end upon the characterist s of the spe-cific system used and should be lected to obtain optimum do information with minimal fading.

The purpose of this sample to obtain background information. If it is not practical to establish cont locations in accordance with the d tance and wind direction criteria, o er sites that provide valid background ata may be substituted, d

Airborne particulate .ple filters shall be analyzed for gross beta dio-activity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or e after sampling to allow for radon and thoron ughter decay. If gross bet activity in air particulate samples is greater tha 10 times the yearly me of control samples, gamma isotopic analysis shall b performed on the i ividual samples.

' Gamma isotopic alysis means the identification and quantification of gamm emitting radion lides that may be attributable to the effluents from the '

facility.

t WATERFORD - UNIT 3 3/4 12-7

TABLE 3.12-1 (Continued)

TABLE NOTATIONS (Continued)

I The " upstream sample -hall be taken at a distance bey d significant influence of the discha . The " downstream" sample e 11 be taken in an area beyond but near the mixin 'one. " Upstream" samples n an estuary must be taken far enough upstream t e beyond the plant i vence. Salt water shall be sampled only when the recel

.g water is utili d for recreational activities.

9A composite sample is one in which quan y (aliquot) of liquid sampled is proportional to the quantity of flo ' g uid and in which the method of sampling employed results in a specimen . is representative of the liquid flow. In this program composite sample uots shall be collected at time intervals that are very short (e.g., h ly) lative to the compositing period (e.g., monthly) in order to as re obta ing a representative sample, h

Groundwater samples shall be tak- when this sour is tapped for drinking or irrigation purposes in areas wh . the hydraulic gra ent or recharge proper-ties are suitable for contamin- on.

I for the maximum organ and a< group, using the The dose shall be calcula methodology and parameter in the ODCM.

d If harvest occurs mor than once a year, sampling shall be pe ormed during each discrete harves If harvest occurs continuously, samplin . hall be

( monthly. Attentic shall be paid to including samples of tuberou, nd root food products.

WATERFORD - UNIT 3 3/4 12-8

_ . _ - _ - - - _ _ _ _ _ _ . _ _ _ _ _ _ - _ . _ _ . _ _ . _ _ - _ - _ - _ - - _ . - _ _ - _ - _ _ _ _ - . - _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ . _ . - _ _ _---__-..__m

- - =

1 g TABLE 3.12-2 a

i

[" REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES S

o Reporting levels g WATER AIRBORNE PARTICULATE FI511 HILK FOOD 000CIS q ANALYSIS (pCi/t) OR GASES (pCi/m3 ) (pCi/kg, wet) (pCi/t) ( kg, wet)

H-3 20,000 Mn-54 1,000 30,000

, Fe-59 400 10,000 Co-58 1,000 30,000 i

, , Co-60 300 000 D

y Zn-65 300 20, s m

E Zr-Nb-95 400 I-131 2 0.9 3 100 Cs-134 30 10 1,.000 6 1,000 Cs-137 50 20 2,000 70 2,000 Ba-la-140 200 300 t

)

l j

_ m -

]

g TABLE 4.12-1 ,

A a q DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)b,c l L

g WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCIS NT q ANALYSIS i/L) OR GAS (pCi/m3 ) (pCi/kg, wet) (pCi/E) (pCi/kg, wet) i/kg dry) ;

w gross beta 3 0.01

. H-3 2000

[ Mn-54 15 130 Fe-59 30 260 Co-58,60 15 I w

D Zn-65 30 260 M

Zr-Nb-95 15 ,

d I-131 1 0.07 1 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 i

9 l

i I

TABLE 4.12-1 (Continued)

TABLE NOTATIONS a

This does not mean that only these nuclides are to be consi red. Other peaks th are identifiable, together with those of the above .lides, shall also be an zed and reported in the Annual Radiological Envi nmental Operating R rt pursuant to Specification 6.9.1.7.

b Required detect capabilities for thermoluminescent do' ..eters used for environmental mea" ements shall be in accordance with recommendations of Regulatory Guide 4.

C The LLD is defined, for rposes of these specific ons, as the smallest concentration of radioac e material in a sample aat will yield a net count, above system background, t. will be detected w' 95% probability with only 5% probability of falsely es uding that a bl observation represents a "real" signal, for a particular measurement syst which y include radiochemical separation:

4.66 s LLD =

E V 2.22 x 106 - -

(-AaT)

( Where:

LLD is the "a priori" lowe imit of detect 1 as defined above, as microcuries per unit mas r volume, sh is the standard de tion of the background c ting rate or of the counting rate of a b nk sample as appropriate, a ounts per minute, E is the counting ficiency, as counts per disinteg tion, V is the sampi ize in units of mass or volume, 2.22 x 106 the number of disintegrations per minute pe icrocurie, Y is the 'actional radiochemical yield, when applicable,

- A is radioactive decay constant for the particular radionue 'de, and At r environmental samples is the elapsed time between sample c ection, o nd of the sample collection period, and time of counting ypical values of E, V, Y, and at should be used in the calculation.

(

WATERFORD - UNIT 3 3/4 12-11

TABLE 4.12-1 (Continued)

TABLE NOTATIONS It should be recognize . hat the LLO is defined a n a priori (before the fact) limit representing e capability of a me remeiit system and not as an a posteriori (after the fa limit for a par" .ular measurement. Analyses shall be performed in such a nner that th .tated LLDs will be achieved under routine conditions. Occ nally b ground fluctuations, unavoidable small sample sizes, the presence in fering nuclides, or other uncontrol-lable circumstances may render thes Os unachievable. In such cases, the contributing factors shall be iden and described in the Annual Radiological Environmental Oper ng Re pursuant to Specification 6.9.1.7.

d LLO for drinking water s les. .

If no drinking er pathway exists, the LLD of gamma isotopic anal s may be used.

l k WATERFORD - UN;T 3 3/4 12-12 l

RAD OGICAL ENVIRONMENTAL MONITORING 3/4.1 LAND USE CENSUS LIMITING NDITION FOR OPERATION .

3.12.2 A la use census shall be conducted and shall iden fy within a distance of 8 (5 miles) the location in each of the 16 teorological sectors of the arest milk animal, the nearest resident and the nearest garden

of grea than 50 m2 (500 f t2) producing broad ,caf vegetation.

APPLICABILITY: A all times.

ACTION:

a. With a land e census identifying a 1 ation(s) that yields a cal-culated dose dose commitment great than the values currently being calcula in Specification 4. .2.3, identify the new location (s) in e next Semiannual dioactive Effluent Release Report, pursuant o Specification 9.1. 8.

b. With a land use c us identifyi a location (s) that yields a calculated dose or se commit t (via the same exposure pathway) 20% greater than at locatior rom which samples are currently being obtained in acc dance th Specification 3.12.1, add the new location (s) to the rad logi 1 environmental monitoring program within 30 days. The sa 11 location (s), excluding the control

( station. location, having lowest calculated dose or dose commitment (s),

via the same exposure pat y, may be deleted from this monitoring program after October 31 he year in which this land use census was conducted. Pursuan to ecification 6.9.1.8 identify the new location (s) in the nex Semia ual Radioactive Effluent Release Report and a'so inclu in the eport a revised figure (s) and table for the ODCM reflec g the ne ocation(s).

c. The provisions of pecifications 0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use e sus shall be conducted du g the growing season at least once per 12 mo s using that information tha will provide the best results, such as by door-to-door survey, aerial su ey, or by consulting local agriculture horities. The results of the la use census shall be incluced in the A ual Radiological Environmental Oper ing Report pursuant to Specification 6. 1. 7.

Broad leaf v etation sampling of different kinds of vege tion may be performed at the SITE UNDARY in each of two dif ferent direction se rs with the highest predicted Qs in lieu of the garden census. Specification or broad leaf vegetatio sampling in Table 3.12-1 Part 4.c. shall be follow , including analysis f control samples.

WATERF0 - UNIT 3 3/4 12-13

I RADIO CAL ENVIRONMENTAL MONITORING 3/4.12.3 TERLABORATORY COMPARISON PROGRAM LIMITING CO N FOR OPERATION 3.12.3 Analyses sh be performed on all radioac ve materials supplied as part of an Intrelaboro 'ry Comparison Program th has been approved by the Commission.

APPLICABILITY: P.t all time.

ACTION:

a. With analyses not being p ormed as required above, report the corrective actions taken a event a recurrence to the Commission in the Annual Radiologi 1 Ens onmental Operating Report pursuant to fpecification 6.9. .

b. The provisions of ecifications 3. and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENT 4.12,3 The Interla atory Comparison Program shall be ribed in the 00CM.

' A summary of the r uits obtained as part of the above req ed Interlaboratory Comparison Progt shall be included in the Annual Radiologi Environmental Operating Repor pursuant to Specification 6.9.1.7.

i WATERFORD - UNIT 3 3/4 12-14

f- ,

l .

i l

.: 6 (NSTRUMENTATION BASES

ph _

i 3/4.3.3.10 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor 4

{

' and control, as applicable, the releases of radioactive materials in liquid 4

effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted f in accordance with the methodology and parameters in the 00CM to ensure that

' the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

i The OPERABILITY and use of this instrumentation is consistent with the require-mentsofGeneralDesignCriteria60,63,and64ofAppendixAto10CFRPart50.)

gg , pT4.3.3.15 LRAD10 ACTIVE GASEOUS EFFLUENT) MONITORING INSTRUMENTATION C"P 6 /ISd M d n [d controlk ~dioactive gaseous effluent instrumentation is pr ided to monitor

, as applicable, the releases _of radioactive materials in gaseous .

effluents during actual or potential-releases of gaseous effluents. The 1 alarm / trip setpoints for these instruments shall be calculated and adjusted f in accordance with the methodology and parameters in the 00CM to ensure that thej g ,[ alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. fihis instrumentation Qlsofincludes provisions for monitoring (and controllEg) tne concentrationtof potentially explosive gas mixtures in the WASTE GAS HOLOUP SYSTEMhe OPERABILITa5d use'6T This insTMimEnUT71on is consistM (the~ requirements of General Design Criteria 60,. 63, and 64 of Appendix A-

, CEL, i

uoJO CFR Part 50.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection . instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment, or structures, l-i I

WATERFORD - UNIT 3 8 3/4 3-4

- _ _ _ _ .. .m - . _ _ . _ . _ _ _ . . _ . . _. _ _ _ . _ _ _ _ _ _ _ _ _ _ . . - __

3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATf0N -

T is specification is provided to ensure that the concentration of radida e materials released in liquid waste effluents to UNRESTRICTED A." a will be I than the concentration levels specified in 10 CFR Part 20, Appendix B, le II, Column 2. This limitation provides additional a rance that the leve of radioactive materials in bodies of water in UNRES' CTED AREAS will resu in exposures within (1) the Section II.A design ectives of Appendix I, 10 R Part 50, to a MEMBER OF THE PUBLIC and (2 . e limits of 10 CFR Part 20.106( to the population. The concentration l' .t for dissolved or entrained noble ga is based uDon the assumption that 135 is the controlling radioisotop nd its MPC in air (submersion) s converted to an equivalent c;ncentration water using the methods d ibed in International Commission on Radiological - tection (ICRP) Public on 2.

The sampling and analysis the contents the regenerative waste tank.

ano the filter flush tank is perfu ed if pr ry to secondary leakage occurs in a team genetstor. The contents the tanks cannot be discharged to the UNRESTh1CTED AREA if any radioactivit etected in these tanks since the dischargi from these tanks is unmonit When radioactivity is detected in these tanks, the contents from thes ank ust be discharged to the liquid radwaste system where the content , ay then monitored upon discharga.

The required detection c Dilities for ra 'oactive materials in liquid aste samples are tabulate terms of the lowe imits of detection (LLDs).

Detailed discussion of t LD, and other detectio limits can be found in HASL Procedures Manual, SL-300 (revised annually), urrie, L. A., " Limits for Qualitative Dete n ana Quantitative Determinat + Application to Radiochemistry," A Chem. 40, 586-93 (1968), and Har 11, J. K.,

" Detection limits Radioanalytical Counting Techniques ' Atlantic Richfield Hanford Company sort ARH-SA-215 (June 1975).

3/4.11.1.2 l This ification is provided to implement the requirement f Sections and IV.A of Appendix I, 10 CFR Part 50. The Limiting ndition II.A, If' for Ope tion implements the guides set forth in Section II. A of Ap ndix 1.

ihe A ON statements provide the required operating flexibilty and the same me implement the guides set forth in Section IV,A of Appendix I to j ass e that the releases of radioactive material in liquid effluents to l

UN dTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation l WATERFORD - UNIT 3 B 3/4 11-1 l

4 l

RADI0 ACTIVE EFFLUENTS

, BASES DOSE (Continued) o 5e facility will not result in radionuclide concentrations in the finie d drin water that are in excess of the requirements of 40 CFR Part 141 ehe dose ca lation methodology and parameters in the 00CM implement the <uire-ment in Se on III.A of Appendix I that conformance with the guid f Appendix I b own by calculational procedures based on models data, such that the actual - osure of a MEMBER OF THE PUBLIC through a .priate pathways is unlikely to be stantially underestimated. The equa ' s specified in the ODCM for calcula the doses due to the actual re se rates of radio-active materials in liq effluents are consistent . the methodology provided in Regulatory Gui 1.109, " Calculation snnual Doses to Man from ,

Routine Releases of Reactor uents for the ose of Evaluating Compliance with 10 CFR Part 50, Appendix I, evision sctober 1977 and Regulatory Guide 1.113. " Estimating Aquatic 0 rsi of Effluents from Accidental and Routine Reactor Releases for the Purp f Implementing Appendix 1," April 1977.

3/4.11.1.3 LIQUID RADWASTE TRE ,1rr SYSTEM The OPERABILITY of th iquid radwaste treat t system ensures that this system will be ava' ale for use whenever liqu ffluents require treatment prior to re tse to the environment . The r irement that the appropriate portio f this system be used when specifie rovides assurance that the release radioactive materials in liquid efflue will be kept "as low as is sonably achievable." This specification impi nts the requirements 10 CFR Part 50.36a, General Design Criterion 60 o ppendix A to 10 CFR t 50 and the design objective given in Section 11.0 o endix I to 10 CF art 50. The specified limits governing the use of appropri portio of the liquid radwaste treatment system were specified as a sui ble frac n of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

3/4.11.1.4 LIOUID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or wal'Is capable of holding the tank contents and that do not have tank 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 tank's contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surf ace water supply in an UNRESTRICTED AREA.

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l RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS I S/4.11.2.1 DOSE RATE I

1 specifict. tion is provided to ensure tnat the dose at any time at and beyond t SITE BOUNDARY from gaseous etikerM .' rom all units on the site will be wi in the annual dose limits of 10 CFR Part 20 to UNRESTRICTED ARE' The annual c e limits are the doses associated with the concentrations 10 CFR Part 2 Appendix B. Table II, Column 1. These limits provide enable assurance that dioactive material discharged in gaseous effluents 1 not result in the exp ure of a MEMBER OF THE PUBLIC in an UNRESTRICT sREA, either within or cu ide the SITE BOUNDARY, to annual average e entrations exceeding the limits cified in Appendix B, Table II of 10 , Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who ma times be within the SITE BOUNDARY, the oc. ancy of that MEMBER OF THE P C will usually be sufficiently low to compens for any increase in the mospheric diffusion factor abcVe that for the SIT "'0VNDARY. Examples o .alculations 'or such MEMBERS OF THE PUBLIC, with the repriate occup factors, sha'l be given in the ODCM. The specified relea rate limits strict, at all ',imes, the corresponding gamma and beta dose r above ackground to a MESBER OF THE PUBLIC at or beyond the SITE BOUNDARY l than or equal to 300 mrems/ year to the total body or to less than or eqt .o 3000 mrems/ year to the skin.

These release rate limits also restrict - 11 times, the c'stresponding thyroid dose rate above background to chi via the inha1 4 tion pathway to less than or equal to 1500 mrems/ye .

The required cetection capa ities for radi tive materials in gaseous waste samples are ttbulated in rms of the lower its of detection (LLDs).

Detailed discussion of the L and other detection its can be found in HASL Procedures Manual, HAS. s00 (revised annually), rie, L.A., " Limits for Qualitative Det:ctien andJ5antitative Determination n lication to Radio-chemistry," Anal. Chem.# D, 586-93 (1968), and Hartwell, K., " Detection Limits for Racioant.lytfbl Counting Techniques," Atlantic hfield Hanford Company Report ARP-S W 15 (June 1975).

3/4.11.2.2 DOSE OBLE GASES This spec' cation is provided to implement the requirements Sections II.8, III.A IV.A of Appendix I, 10 CFR Dart 50. The Limiting Co. tion for Operati implements the guides set forth in Section II.B of Apper I.

The ACTIO tatements provide the required operating flexibility and a e same tim mplement the guides set forth in Section IV.A of Appendix I t assure t the releases of radioactive material in gaseous effluents to UNREST' vTED AREAS will be kept 'as low as is reasonably achievable." The Surveis ance Requirements implement the requirements in Section III.A of l A WATERFORD - UNIT 3 B 3/4 11-3

i l

9 RADI0 ACTIVE EFFLUENTS BA$ES OOSE - NOBLE GASES (Continued)

Appendi that conformance with the guides of Appendix I be shown by calculat 1 procedures based on models and data such that the actual exposure o MEMBER OF THE PUBLIC through appropriate pathways is uni y to be substant' ly underestimated. The dose calculation methodology a para-meters establ 5ed in the 00CM for calculating the dctes due to th ctual release rates radioactive noble gases in gaseous effluents ar onsistent with the methodo provided in Regulatory Guide 1.109, "Cale tion of Annual Doses to M from Routine Releases of Reactor Effluen for the Purpose of Evaluating Compi ce with 10 CFR Part 50, Appendix I," vision 1, October 1977 and Regulatory ' e 1.111. " Methods for Estimating , ospheric Transport and Dispersion of Case Effluents in Routine Releases om Light-Water Cooled Reactors," Revisi 1, July 1977.

The ODCM equations prov d for determining

air doses at and beyond

the SITE BOUNDARY are based up the historical trage atmospheric conditions.

Grab sampling of effluents f the mai ondenser evacuation and turbine gland sealing system is not require when s source has been continously discharging to the plant stack over p 30 days. If no primary to secondary leakage in the steam generat xists, then there should be no radioactive release from the main conc r evacuation and turbine gland sealing system and the gross beta or mm onitoring for noble gases will be sufficient to determine if any rad etivit -is present in the release. If a primary to secondary leak exists ,en the r a_se s from_the main condenser evacuation and turbine gland se ng system w1 be sampling ;will be sampled and analyzed in accordance wi able 4.11-2 M ~

4 7- _

3/4.11.2.3 DOSE - IODINE- . 10 DINE-133, TRITI ND RADIONUCLIDES IN PARTICULATE FORM This specificat is provided to implement the req 'rements of Sections II.C. III. and IV.A of Aopendix I, 10 CFR Part The Limiting Conditions for Op tion are the guides set forth in Sectic II.C of Appendix 1.

The ACTION stat nts provide the required operating flexibi +y and at the same time impi nt the guides set forth in Section IV.A of A ndix I to assure that releases of radioactive materials in gaseous ef uents to UNRESTRICT REAS will be kept "as low as is reasonably achieva ." The 00CM cale tional methods specified in the Surveillance Requireme s impleme he requirements in Section III.A of Appendix I that conf mance I

with t guides of Appendix I be shown by calculational procedures b d on model nd data, such that the actual exposure of a MEMBER OF THE PUBLIC thro a appropriate pathways is unlikely to be substantially underestimated.

The CM calculational methodology and parameters for calculating the dost.s due to the actual release rates of the subject materials are consistent with l

WATERFORD - UNIT 3 8 3/4 11-4 l

t

i RADIOACTIVE EFFLUENTS BASES l -

00SE-10 DINE-131, 100lNE*133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM (Continued)

)'

the thodology provided in Regulatory Guide 1.109, " Calculation of Annu Doses Man from Routine Releases of Reactor Effluents for the Purpo ,f Evaluati Compliance with 10 CFR Part 50, Appendix I," Revision 1 .tober 1977 and latory Guide 1.111 " Methods for Estimating Atmosp .c Transport ,

and Dispersi f Gaseous Effluents in Routine Releases from . t-Wate r- 1 Cooled Reactors, evision 1. July 1977. These equations provide for determining the a 1 doses based upon the historical age atmospheric conditions. The rel rate specifications for iodi 31, iodine-133, tritium, and radionucl1 in particulate form wit if-lives greater than 8 days are defendent upon existing radionuci pathways to man in the l areas at and beyond the SIT UNDARY. The p ays that were examined in the development of these calcu l ons were: individual inhalation of :

airborne radionuclides, (2) depos % n of dionuclides onto green leafy vegetation with subsequent consumpt' . man, (3) deposition onto grassy l areas where milk animals and meat pr .g animals graze with consumption i of the milk and meat by man, and depo ion on the ground with subsequ( .c exposure of man.

3/4.11.2.4 GASEOUS RADWAST REATMENT The OPERABILITY of e WASTE GAS HOLOUP SYSTEM a the VENTILATION EXHAUST TREATMENT SYS ensures that the systems will available for use whenever gaseous ef ants require treatment prior to rel e to the environment. The d' harge from the main condenser evacuati and turbine gland sealing sy* m shall be required to be directed to the nt stack when the release ra of I-131 from this source is > 2 x 10

pCi/s. he reouire-ment that th ppropriate portions of thest systems be used, when ecified, provides re onable assurance that the releases of radioactive mate is in gaseous e" uents will be kept "as los as is reasonably achievable", is specifi . ion implements the requirements of 10 CFR Part 50.36a, Genera esign Crite 60 of Appendix A to 10 CFR Part 50 and the design objectives gi n in Sect' II.0 of Appendix ! to 10 CFR Part 50. The specified limits governing thej e of appropriate portions of the systems were specified as a suitable fraftion of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

3/4.11.2.5 EXPLOSIVE GAS HIXTURE -

This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the WASTE GAS HOLOUP SYSTEM is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the reouirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

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l RADIOACTIVE EFFLUENTS BASES 3/4.11.2.6 GAS STORAGE TANKS This specification considers postulated radioactive releases due to a

, waste gas system leak or f ailure, and limits the quantity of radioactivity contained in each pressurized gas storage tank in the WASTE GAS HOLDUP SYSTEM to assure that a release would be substantially below the guidelines of 10 CFR Part 100 for a postulated event.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11 5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981.

2 3/4.11.3 SOLIO RADIOACTIVE WASTE Thh specification implements the requirements of 10 CFR 50.36a an General sign Criterion 60 of Appendix A to 10 CFR Part 50. The pr s parameter ' cluded in establishing the PROCESS CONTROL PROGRAM , nelude, but are not ited to waste type, waste pH, waste / liquid / sol- cation agent /catalys tios, waste oil content, waste principal .ical constituents, an ixing and curing times.

3/4.11.4 TOTAL' DOSE This specification i ovided to meet dose limitations of 40 CFR Part 190 that have been inco ated into FR Part 20 by 46 FR 18525. The specification requires the prepa ion submittal of a Special Report whenever the calculated doses from generated radioactive effluents and direct radiation exceed 25 mrems to s tal body or any organ, except the thyroid, which shall be limited iess t or equal to 75 mrems. For sites containing up to four reactors is highly likely that the resultant dose

, to a MEMBER OF THE PUBLIC wi' exceed the dose its of 40 CFR Part 190 if the individual reactors re n within twice the d design objectives of Appendix 1, and if direc< diation doses from the r tor units and outside storage tanks are kept 11. ~ The Special Report will ecribe a cource of action that should r it in the limitation of the annual e to a MEiBER OF THE PUBLIC tu with the 40 CFR Part 190 limits. For the pu ses of the Special Report, may be assumed that the dose commitment to t MEMBER OF THE PUBLIC fro ther uranium fuel cycle sources is negligible, w the exception th dose contributions from other nuclear fuel cycle fac1 .ies at the same s< or within a radius of 8 km must be considered. If the e to WATERFORD - UNIT 3 B 3/4 11-6

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4 1

, RADIDACT:VE EFFLUENTS BASES f .

TOTAL DOSE (Continued) any R OF THE PUBLIC is estimated to exceed the requirements o wrR Part 19 , special Report with a request for a variance ( d the release condi esulting in violation of 40 CFR P . have not already been corrected), in dance with the provis o 40 CFR 190.11 and 10 CFR 20.405c, is consi o be a ti quest and fulfills the requirements of 40 CFR Part 19 v staff action is completed. The variance only relates to the 14 .

CFR Part 190, and does not apply >

any way to the other re . nts for dose ation of 10 CFR Part 20, o addressed in Specif ons 3.11.1.1 and 3.11.2. , individual is not considered a P OF THE PUBLIC during any period h he/she is e.

in carryi > t any operation that is part of the nuclear cle.

t 4

WATERFORD - UNIT 3 B 3/4 1.'-7

4 J

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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l

, BASES a

! =

3/4.12.1 MQNIIORING PROGRAM The radio cal environmental monitoring program reo d by this specification pro es representative measurements of re tion and of j radioactive materia in those exposure pathways and f those radionuclides that lead to the highe potential radiation exposur of MEMBERS OF THE PUBLIC resulting from th lant operation. This itoring program implementsSection IV.B.2 of Appendix to 10 CFR Part 50 thereby supplements the radiological effluent monito program by fying that the measurable concentrations of radioactive m rials a evels of radiation are not higher than expected on the basis of the flu measurements and the modeling of the environmental exposure pathways, idance for this monitoring program is provided by the Radiological Assest ranch Technical Position on Environ-mental Monitoring. The initia11- peci monitoring program will be effective for at least the fir years o ommercial operation. Following this period, program changes be initiate sed on operational experience.

The required detect' capabilities for envi ental sample analyses

] are tabulated in terms the lower limits of detect .(LLDs). The LL0s i required by Table 4. are considered optimum for rou'. e environmental measurements in in rial laboratories. It should be re ized that the LLO is defined as an riori (before the fact) limit representi. ;he capability of a measuremen ystem and not as an a,posteriori (after the <

limit for a particular surement.

Detail discussion of the LLO, and other detection limits, can b ound in HASL Pr edures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qual tive Detection and Quantitative Determination - Application to Radiocht stry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K. , " Detection Limits d r Radioanalytical Counting Techniques," Atlantic Richfield Hanford y Report ARH-SA-215 (June 1975).

WATERFORD - UNIT 3 8 3/4 12-1

1 l

3/4. DIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.2 LAND CENSUS l This specificat is provided to enfure th .hanges in the use of areas at and beyond the SITE ' DARY are ident f fied d that modifications to the radiological environmental nitoring progr re made if required by the results of this census. The t informa from the door-to-doar survey, from aerial survey or from cons ing w . local agricultural authorities shall be used. This census satis. s .e requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Rest ting the census to gardens of greater than 50 m2 provides assurance th i 'ficant exposure pathways via leafy vegetables will be identified monito since a garden of this size is the minimum required to produce quantity (. kg/yr) of leafy vegetables assumed in Regulatory Guid .109 for consum on by a child. To determine this minimum garden size ,e following assump ns were made: (1) 20% of the garden was used for gr ng broad leaf vegetation i.e., similar to lettuce and cabbage), and (2 vegetation yield of 2 kg/mi.

3/4.12.3 INTERLt RATORY COMPARISON PROGRAM The req ement for participation in an approved Inter) ratory.

Comparison ogram is provided to ensure that independent chec on the precisio 1d accuracy of the measurements of radioactive materi in

, enviro tal sample matrices.are performed as part of the quality surance progr for environmental monitoring in order to demonstrate that the 'sults ar lid for the purposes of Section IV.B.2 of Appendix ! to 10 CFR Pa k 50.

WATERFORD - VNIT 3 B 3/4 12-2 yr.----- y,r-yw-yw---y,- y *w--- ml+-

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4 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

1. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment, ,

c. Secondary L'ater Chemistry A program for monitoring of secondary water chemistry to inhibit j steam generator tube degradation. This program shall include: ,

1. Identification of a sampling schedule for the critical variables and control points for these variables,

2. Identification of the procedures used to measure the values of the critical variables, ,

3. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,

4. Procedures for the recording and management of data,

5. Procedures defining corrective actions for all off-control !

point chemistry conditions, and

6. A procedure identifying (a) the authority responsible for the

. interpretation of the data, and (b) the sequence and timing of administrat1ve events required to initiate corrective action.

d. Post-accident Samplino A program whien will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples unoer accident conditions. The program shall include the following:

1. Training of personnel,

2. Procedures for sampling and analysis, and

3. Provisions for maintenance of sampling and analysis equipment,

e. Basemat Monitorino A program for monitoring of the Nuclear Plant Island Structure (NPIS)

Common Foundation Basemat to ensure the continue 1 integrity of the Basemat. The program shall include:

1. settlement of the basemat

2. changes in ground water chemistry that could ef fect corrosion of reinforcing steel

3. seasonal variation in ground water levels

, b#'

4. mapping of significant cracking in the basemat and adjacent Tc.xT OR walls.

H G y T* I W o

. 'PAGES WATERFORO - UNIT 3 6 ,16

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ADMINISTRATIVE CONTROLS l PROCEDURES AND PROGRAMS (Continued) .

I

f. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.364 for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the 00CH, (2) shall be implemented by operating procedures, and (3) shall in-clude remedial actions to be taken whenever the program limits are ,

exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and. gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the ODCM,

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM,

4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50,

5) Determination of cumulative and projected dose contributions from radioactive offluents for-the current calendar quarter and current calendar year in accordance with the methodology. and parameters in the ODCH at least every 31 days,

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radio-L activity when the projected doses in a 31-day period would exceed 2 percent of the. guidelines for the annual dose or dose commitment conforming to Appendix ! to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous _ effluents to areas beyond the SITE BOUNDARY

(

l conforming to the doses associated with 10 CFR Part 20 Appendix B, Table II, Column 1, I

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HL1vJ~A(!Db ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.4 f. Radioactive Effluent Controls Procram (Continued)

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

9) Limitations on t.ke annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131 Iodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous ef fluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix ! to 10 CFR Part 50,

10) Limitations on venting and purging of the Mark II containment through the Standby Gas Treatment System to maintain releases as low as reasonably achievable (BWRs w/ Mark II containments),

and

11) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190,

g. Radiological Environmental Monitorino Program A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental expo-sure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the method-ology and parameters in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at ,

and beyond the SITE BOUNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the L measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance pro-j gram for environmental monitoring.

l

ADMINISTRATIVE CONTROLS

(

MONTHLY OPERATING REPORTS 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covtred by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 Routine Annual Radiological Environmental Operating Repo ps covering the operation of the unit during the previous calendar year shal' ae submitted prior to .ay 1 of each year. The initial report shall be submi d prior to May 1 of year following initial criticality.

.The Annual R "ological Environmental Operating Reports s 1 include summaries, interpretation. arJ an analysis of trends of the resu ' of the radiological environmental si eillance activities for the report -iod, including a comparison with p operational studies, with opera al controls as appropriate, and with previous ironmental surveillance repc , and an assessment of the observed impacts of e plant operation on the ironment. The reports shall also include the resu of land use censuse equired by Specification 3.12.2.

g The Annual Radiological .ironmental Ope ting Reports shall include the (

results of analysis of al adiological nvironmental samples and of all '

environmental radiation mea ements ken during the period pursuant to the locations specified in the Ta e an igures in the OOCH, as well as summarized and tabulated res'ults of these ses and measurements in the format of the table i'n the Radiological Asses nt Branch Technical Position, Revision 1, November 1979. In the event at me individual results are not available for inclusion with the repo , the ort shall be submitted noting and explaining the reasons for the missi results, he missing data shall be, submitted as soon as possible in a s alementary rep ~ .t.

The reports shall a include the followi : a summary description of the radiological envir mental monitoring progr ' at least two legible maps

covering all sa ing locations keyed to a ta .e giving distances and directions from the cente ine of one reactor; the result ' f licensee participation in the Interlab tory Comparison Program, requirec Specification 3.12.3; discussion all deviations from the sampling se ule of Table 3.12-1; and discussio nf all an'alyses in which the LLD require by Table 4.12-1 was not achievab .

0ne map shall cover stations near the SITE BOUNDARY a second shall include the more distant stations.

OG.L_(T?crucc wrrH TCyr FccM p cxr P Ac,e WATERFORD - UNIT 3 6-18

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,- ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

!' 6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpreta-tions, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be

, consistent with the objectives outlined in (1) the ODCM and (2) Sections

! IV.B.2, IV.B.3, and IV.C of Appendix 1 to 10 CFR Part 50.

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ADMINISTRATIVE CONTROLS .

SEMIANNUAL RADICACTIVE EFFLUEN tLt xte k 6.9.1. Routine Semiannual Radioactive Effluent Release Reports covering the operati of the unit during the previous 6 months of operation shall be submitte within 60 days af ter January 1 and July 1 of each year. The r iod of the fi . report shall begin with the date of initial criticality.

1 Radioactive Effluent Release Reports shall include ummary of The Semiannua the quantities . radioactive liquid and gaseous effluents and id waste released from the it as outlined in Regulatory Guide 1.21, " asuring, Evaluating, and Rep ting Radioactivity in Solid Wastes and leases of Radio-s active Materials in L uid and Gaseous Ef fluents f rom Lig Water-Cooled Nuclear Power Plants," vision 1, June 1974, with data mmarized on a quarterly basis following the form 'of Appendix B thereof.

The Semiannual Radioactive E ' uent Release Report- be submitted within 60 days af ter January 1 of eac . ear shall inclu an annual summary of hourly meteorological data collected ov .the previou ar. This annual summary may be either in the form of an hour-b our list on magnetic tape of wind speed, wind direction, atmospheric 5 ilit and precipitation (if measured),

or in the form of joint f requency dist 'b 'ons of wind speed, wind direction, and atmospheric stability.* This same , ort shall include an assessment of the radiation doses due to the radioac ' liquid and gaseous effluents released vio calendar year. This same report from also shall the unit or station include an assessment during the of p'e radi ion doses from radioactive liquid and gaseous effluents to M' ERS OF TH UBLIC due to their activities inside the SITE BOUNDARY (Figure .1-3) during . report period. All assumptions used in making the ' assessments, i. specific activity, exposure time and location, shall be i uded in these repo .

The meteorological conditions concurrent with ' time of release of ra loactive materials in gaseous effluents, as dete ined by sampling frequency nd measurement, shall j be used for determining gaseous pathway doses. The ssessment of radiation doses shall be performe :in accordance with the methodol and parameters in ,

the OFFSITE DOSE CALC ' ATION MANUAL (ODCM). ,

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The Semiannual Rad etive Effluent Release Report shall also clude once a '

year an assessmen Hof radiation doses to the likely most expose ' EMBER OF THE

,PUBLIC from rea r releases and other nearby uranium fuel cycle urces, I including dose rom primary ef fluent pathways and direct radiatio for the l l' previous cal ar year to show conformance with 40 CFR Part 190, Env nmental Radiation P ection Standards for Nuclest Power Operation. Acceptabl ethods e

for calcul ng the dose contribution from liquid and gaseous effluents given in gulatory Guide 1.109, Rev. 1, October 1977. .

In eu of submission with the first half year Semiannual Radioactive Effluent

! R ase Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be providEL to the 1 NRC upon request.

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WATERFORD - UNIT 3 6-19

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ,

6.9.1.8' The. Semiannual Radioactive Effluent Release Report covering the oper-

- ation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each. year. The report shall in-clude a. summary of the quantities of radioactive liquid and gaseous effluents and-solid waste released from the unit. - The material provided shall be (1)-consistent with the objectives outlined in the ODCM and PCP and (2) in

. < ;conformance with 10.CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

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ADMINISTRATIVE CONTROLS

' SEMIANNUAL-RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)

T Semiannual Radioactive Effit.ent Release Reports shall include t following i ation for.each class of solid waste (as defined by 10 CFR P .61) shipp ffsite during the report period:

a. ainer volume,

b. Tota rie quantity (specify whether determ d by measurement or estimat

c. Principal r ' nuclides (specifv wheth determined by measurement or estimate),

d. Source of waste an cessing eyed (e.g., dewatered spent resin, compacted dry w , orator bottoms),

e. Type of container (e.g. A, .e A, Type B, large Quantity), and

f. Solidification age or absorbent , cemat, urea formaldehyde).

The Semiannual Radioact Effluent Release Reports 1 include a list and description of unpla releases from the site to UNR CTED AREAS of radioactive materi in gaseous and liquid effluents made ing the reporting period.

The Semiannu Radioactive Effluent Release Reports shall include hanges made durin he reporting period to the PROCESS CONTROL PROGRAM (PCP) and to -

the OFFSITE DOSE CALCULATION MANUAL (00CM), as-well as a listing of new loca-tions for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

INDUSTRIAL SURVEY OF T0XIC OR HAZARDOUS CNEMICALS REPORT 6.9.1.9 Surveys and analyses of major industries in the vicinity of 'Waterford 3 which could have significant inventories of toxic chemicals onsite to determine impact on safety shall be performed and submitted to the Commission at least once every 4 years.

L6.9.1.10 A. survey of major pipelines (> 4 inches) within a 2-mile radius of Waterford 3, which contain explosive or flammable materials and may represent a hazard to Waterford 3, including scaled engineering drawings or mans which

. indicate the pipeline locations, shall be performed and submitted to the-Com-mission at least once every 4 years.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional administrator of the Regional Office of the NRC within the time period specified for each report.

6.10 RECORD RETENTION 6,10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at L least the minimum period indicated.

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. ADMINISTRATIVE CONTROLS .

RECORD RETENTION (Continued) ,

i. Records of quality assurance activities required by the QA Manual. 1

j. Records of reviews performed for changes made to procedures or ,

equipment or reviews of tests and experiments pursuant to 10-CFR 50.59.

k. Records of meetings of the PORC and the SRC.

1. Records.of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records.

m. Records of secondary water sampling and water quality,

n. Records of audits pei 'rmed under the requirements of Speci fication 6. 5.2.8.

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o. Records of analyses required by the radiological environmental ,

'490:

monitoring program that would permit evaluation of the accuracy of

'DG#I og gEucr the analysis at a later date. This should include procedures effective at specified times and QA records showing that these

-'9 AN procedures were followed.-

6.11 RADIATION PROTECTION PROGRAM 4

6.11.1- Procedures for personnel radiation protection shall be prepared consistent with'the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all' operations involving personne1 radiation exposure. .

6.12 HIGH RADIATION AREA-6.12.1 In ' lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of _ radiation is ' greater than 100 mrem /h but less than 1000 mrem /h shall be barricaded and conspicuously posted asL a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work- ,

Permit'(RWP)*, Any . individual or group of individuals permitted to enter such ,

areas shall be provided with or accompanied by one or more of the following: '

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

Health physics personnel or personnel escorted.by health physics personnel-shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

WATERFORD - UNIT 3 6-22 t y- ~ ,. ,- -- -

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p. . Records of reviews. performed for changes mado to the OFFSITE DOSE l' CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

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,4 ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)

b. A radiation monitoring device which continuously integrates the radiation' dose rate in the area and alarms when a preset integrated dose is received. _ Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of_them,

c. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Radiation Protection Superin-tendent-Nuclear in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation lovels such that a major portion of the body could receive in one hour a dose greater than 1000 mrems* shall be provided with locked doors to prevent unauthori;:ed entry, and the keys shall be maintained under the administrative control of the Shif t Supervisor on duty and/or health physics super-vision. ' Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a dose in excess of 1000 mrems* that are-located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reason-ably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee-initiated changes to the PCP:

ppij a. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was RGPLAC6 made. This submittal shall contain:

WMMgW 1. Sufficiently detailed information to totally support the rationale.

for the change without benefit of additional or supplemental cy g sG information;

Measurement made at 18 inches from source of radioactivity.

WATERFORD - UNIT 3 6-23

.I a.' Snall be documented and records of reviews performed shall be retained as required by Specification-6.10.3 p. This docwnentation shall contain

1) -Sufficient:information to support the change together with-the appropriate analyses or evaluation justifying the change (s) and ;

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ADMINISTRATIVE CONTROLS g PROCESS CONTROL PROGRAM (Continued)_

Y 2. ' A determination that the change did not reduce the overall-conformance of-the waste product.to existing criteria of MNA 10 CFR Part 61 and for burial at low-level waste sites; and NCxt g Pacs 3. Documentation of the fact that the change has been reviewed and found acceptable by the PORC.

b. 'Shall become effective upon review and acceptance by the PORC.

6.14 0FFSITE 005E CALCULATION MANUAL (00CM) 6.14.1; The ODCH_shall be approved by the Commission prior to implementation, Licensee-initiated changes to the 00CM:-

g [ 6.14.2

-a. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:

1. . Sufficiently detailed.information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of.a package of those pages of the 00CM to be changed with each page numbered and provided with an approval-and date box, together'with appropriate analyses or evaluations justifying the change (s);

2. A determination that the change'will'not reduce the accuracy or reliability of dose calculations or setpoint determinations;

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and-

3. Documenation of the fact that.the change has been reviewed and I found ' acceptable by the PORC.

b.- Shall become effective upon review and acceptance by the PORC.

6.15 MAJOR CHANGES TO RADIOACTIVE LIQUIO, GASEOUS, AND SOLIO WASTE TRtATHENT SYSTEMS

6.15.1 Licensee-initiated major changes to the radioactive waste systems -

(liquid, gaseous,_and-solid): -

a. Shall'bel reported-to.'the Commission in the Semiannual Radioactive Effluent Release' Report for the period in which the e' valuation was reviewed by the PORC. .The discussion of each change shall contain:

^ Licensees may choose to' submit the information called for in this Specification as parttof the annual FSAR update, s

WATERFORD - UNIT 3: 6-24 INSERT BNM N1E l

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I) 2 A determination that the change will maintain the overall con-formance of the solidified waste product to existing require-ments if Federal, State, or other applicable regulatio'ns,

b. Shall become effective after review and acceptance by ths PORC and the approval of the Plant Manager, j INSG.RT & :

b a. Shall be do ented and records of reviewsThis performed shall be documentation shall ed as required by Specification 6.10.3p.

contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and f 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 20 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations,

b. Shall become effective after review and acceptance by the PORCand the approval of the Plant Manager.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire 00CM as a part af or concurrent with the Sealannual Radioactive Effluent Relea's Report for the period of the Each change shall report in which any change to the 00CM was made.

be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall q indicate the date (e.g., month / year) the change was implemented, ,

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ADMINISTRATIVE CONTROLS AJOR CHANGES TO RADIOACTIVE LIOUIO, GASEOUS, AND SOLIO WASTE TREATMENT gh$YSTEMS (Continued)

A summary of the evaluation that led to the determinati . hat the change could be made in accordance with 10 CFR 50 .

2. S cient detailed information to totally supp the reason for change without benefit of additional supplemental inform n;

3. A detailed ription of the equipme , components, and processes inv d and the interfa with other plant systems;

4. An evaluation of th hange, h shows the predicted releases of radioactive materi . in quid and gaseous effluents and/or quantity of solid waste differ from those previously predicted in tia licen a ication and amendments thereto;

5. An evaluation of change, w shows the expected maximum exposures to a 3ER OF THE PUBL in the UNRESTRICTED AREA and to the ge al population that fer from those previously estimated i he license application e amendments thereto;

6. A comp son of the predicted releases of ioactive materials, in 1 id and gaseous effluents and in soli ste, to the

) ac releases for the period prior.to when t hanges are to b ade;

7. An estimate of the exposure to plant operating perso 1 as a result of the change; and

8. Documentation of the fact that the change was reviewed and found acceptable by the PORC.

b. Shall become effective upon review and acceptance by the PORC.

s WATERFORD - UNIT 3 6-25

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Attachment C NPF-38-112 UNT-05-014 (Offsite Dose Calculation Manual)

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ML20065N596

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