ML20063J844

Proposed Tech Specs Re Requirements in 10CFR20

ML20063J844
Person / Time
Site:	Waterford
Issue date:	02/14/1994
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20063J829	List: ML20063J825 ML20063J844
References
NUDOCS 9402240267
Download: ML20063J844 (35)

Text

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DEFINITIONS IDENTIFIED LEAKAGE (Continued)

b. Leakage into the containment atmosphere from sources that are both 5 specifically locaud and known either not to interfere with the operation of leaAage 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-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 (ODCM) 1.16 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alars/ Trip Setpoints, and in the conduct of the Environmen-tal Radiological Monitoring Program. The 00CM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specification 6.9.1.7 l and 6.9.1.8.

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, subsystes, train, component, or device to perfors 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.

9402240267 940214 PDR ADDCK 05000382 P PDR WATERFORD UNIT 3 1-4 Amendment No. 68, 84

DEFINITIONS SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is neither owned, 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.

1.31 Definition 1.31 has been deleted.

l 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.

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 one 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 Amendment No. 68

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. I RADIOACTIVE EFFLUENTS .  :

LIOUID HOLDUP TANKS ,

LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following ynprotected outdoor tanks shall be limited to less than or equal to  :

1.57 x 10' curies,* excluding tritium and dissolved or entrained noble gases.

For outside temporary storage tanks, the curie content shall be limited such that a rupture will not. result in exceeding 10 CFR Part 20 limits at the UNRESTRICTED AREA boundary.  :

a. PWST

b. Outside temporary tank APPLICABILITY: At ell times.

ACTION: l

a. With tree quantity of radioactive material in any of the above listed  !

tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release j -

Report. l

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

SURVEILLANCE REOUIREMENTS i 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample o'f the tank's contents at least once per 7 days when radioactive materials are being added to the tank.  ;

• Based on 80% tank capacity and an MPC of 2 x 10 pC1/mL Cesium-137 equivalent,10 CFR Part 20, Appendix 8$: Table II.

WATERFORD - UNIT 3 3/4 11-8 Amendment No. 84

j 3/4.11 RADI0 ACTIVE EFFLUENTS e

BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 This section deleted.

3/4.11.1.2 This section deleted.

3/4.11.1.3 This section deleted.

3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have~ tank overflows and surrounding area drains cLnnected 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 i 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 i UNRESTRICTED AREA.

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WATERFORD - UNIT 3 83/411-1 Amendment No. 68

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RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION i

3.11.2.6 The quantity of radioactivity contained in each gas storage tank ,

shall be limited to less than or equal t o 8.5 x 104 curies noble gases  !

(considered as Xe-133).  ;

APPLICABILITY: At all times.  !

ACTION:

a. With the quantity of radioactive material in any gas storage tank i exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

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

SURVEILLANCE REQUIREMENTS 1 4.11.2.6 The quantity of radioactive material contained in each gas storage '

tank on-service shall' be determined to be within the above limit at least once l per 7 days until the quantity exceeds 4.25 x 104 curies noble gases (50% of i allowed limit) and then at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank. Tanks isolated for decay will be sampled to verify i above limit is met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following removal from service.

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WATERFORD - UNIT 3 3/4 11-17 I

5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1-1.

LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1-2. ,

MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1. 3 Information regarding radioactive gaseous and liquid effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1-3.

5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor building is a steel containment vessel surrounded by a reinforced concrete shield building.

5.2.1.1 The containment vessel is a cylindrical vessel with a hemispherical dome and an ellipsoidal bottom and having the following design features:

a. Nominal inside diameter = 140 feet.

b. Nominal inside height = 240 feet 4.75 inches. I

c. Nominal thickness of cylindrical wall = 1.903 inches.

d. Nominal thickness of hemispherical dome = 0.95 inch.

e. Nominal thickness of ellipsoidal bottom = 2.25 inches. '

f. Net free volume = 2,680,000 cubic feet.

5.2.1.2 The shield building is a cylindrical structure with a shallow dome roof and having the following design features:

a. Nominal outside diameter = 154 feet.

b. Nominal outside height (from base slab) = 249.5 feet.

c. Nominal thickness of cylindrical wall = 3 feet.

d. Nominal thickness of dome roof = 2.5 feet.

e. Nominal inside radius of dome roof = 112 feet.

f. Nominal annular space = 4 feet.

DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 44 psig and a temperature of 263'F.

WATERFORD - UNIT 3 5-1

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FIGURE 5.1-3 SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS l

WATERFORD - UNIT 3 5-4

l ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

f. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive affluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1. Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,

2. Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,

3. Monitoring, sampling, and analysis of radioactive liquid and gaseous affluents 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 consiitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,

5. Determination of cumulative and projected dose contributions from radioactive affluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

6. Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, WATERFORD - UNIT 3 6-16a AMENDMENT NO. 68 .

e ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT

6. 9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that r.as a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a oescription of the measured values of the operating conditions or characteristics obtained during the test program and a comparison ,

of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.7 shall be submitted annually in accordance with the aforementioned time frame. The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded

• This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.

WATERFORD - UNIT 3 6-17 AMENDMENT NO. 8

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

6. 9.1. 5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and job functions * (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance

[ describe maintenance), waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the indi-vidual total dose need r.r. be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions.

l WATERFORD - UNIT 3 6-17a AMENDMENT NO. 8

ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation  :

of the unit during the previous 12 months of operation shall be submitted within 60 days after January 1 of each year. The report shall include a sumary 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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i f-WATERFORD - UNIT 3 6-19 Amendment No. 68, 84

S ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) 6.10.2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.

c. Ali REPORTABLE EVENTS.

d. Records ci surveillance activitier; inspections, and calibrations required by these Technical Specifications.

e. Records of changes made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

6.10.3 The following records shall be retained for the duration of the unit Operating License:

a. Records and drawing changes reflecting unit design modifications made to systemr and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.

c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient or operational cycles for those unit components identified in Table 5.7-1.

f. Records of reactor tests and experiments. l

g. Records of training and qualification for current members of the unit staff.

h. Records of inservice inspections performed pursuant to these Technical Specifications.

WATERFORD - UNIT 3 6-21 l

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3 ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued)

1. Records of quality assurance activities required by the QA Manual.

J. Records of reviews performed for changes made to procedures or equip-ment 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 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.

p. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consis-tent 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 "alars signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the inten-sity of radiation is greater than 100 area /h but less than 1000 area /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 Permit (RWP)". Any individual or group of individuals permitted to enter such areas

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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 AMEN 0 MENT NO. 68

S ADMINISTRATIVE CONTROLS l

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 activi-ties within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Radiation Protection Supierintendant-Nuclear in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels 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 Shift Supervisor on duty and/or health physics supervision. 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 personnelwithradiationlevelssuchthatamajo;portionofthebodycould receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mress that are located within large areas, such as PWR containment, where no enclosure exists for purposes of lock-ing, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specifica-tion of the RWP, direct or remote (such as use of closed circuit TV cameras) i continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities  !

within the area. l

-6.13 PROCESS CONTROL PROGRAM (PCP) \

6.13.1 The PCP shall be approved by the Commission prior to implementation. l 6.13.2 Licensee-initiated changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This documentation  :

shall contain:

1. Sufficient information to support the change together with I the appropriate analyses or evaluation justifying the change (s) and

' Measurement made at 18 inches from source of radioactivity. l WATERFORD - UNIT 3 6-23 AMENDMENT NO.68 i

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)

2. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b. Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.

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

6.14.2 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This document shall contain:

1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.

b. Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire 00CM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the l report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

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WATERFORD - UNIT 3 6-24 AMENDMENT NO. 68,84 i l

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NPF-38-150 ATTACHMENT B ,

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.g l DEFINITIONS IDENTIFIED LEAKAGE (Continued)

b. Leakage into the conta1nment atmosphere from sources that are both ,

specifically located and known either not to interfere with the operation of i leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE. or L

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

system.  :

t MEMBER (S) 0F THE PUBLIC 6 1.15 MEMBER (S) 0F THE PUBLIC shall 'nclude--all-persnnt ::ho are not occupationally i assosvatad-wittMie-pl ant This-c+tsyny does nat include employees of the 'icesee. +t-s contrac4ws---or--vender s ^l50 vcluded from thic category-are persons wtester-the-stte to-Gerv4(Myapment -or P : deli eries . Th;5 category does include percent who use i per-tws_of_the--site-for-rw-reat40n al occupat4enal or other purposes not-assoc 4atf4 witt+-the-plant be an individual in a controlled or unrestricted area. However, an ,

individual is not a member of the public during any period in which the individual receives an occupational dose. l OFFSITE DOSE CALCULATION MANUAL (00CM) i i

1.16 The OFFSITE DO$E CALCULATION MANUAL (ODCM) shall contain the methodology and -

parameters used in the calculation of offsite doses resulting from radioactive gaseous >

and liquid effluents. in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the environmental radiological monitoring ,

program. The ODCM shall also contain (1) the Radioactive Effluent Controls and &

Radiological Environmental Monitoring Programs required by section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Specification 6.9.1.7 and 6.9.1.8. ,

f 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

'l necessary attendant instrumentation controls electrical power, cooling or seal wr l lubrication or other auxiliary equipment that are required for the system, subsystei,. i train, component, or device to perform its function (s) are also capable of performing-  !

-their related support function (s). ,

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

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WATERFORD - UNIT 3 1-4 Amendment No' 84 h

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DEFINITIONS  ;

SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land or property is not 4s reR4r. owned, nec leased, nc*E otherwise controlled by the licensee.

SOFTWARE 1.3D The digital computer SOFTWARE for the reactor protection system shall be the program codes including their associated data, documentation. and procedures. ,

1.31 Definition 1.31 has been deleted  !

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

STAGGERED TEST BASIS  !

1.33 A STAGGERED TEST BASIS shall consist of:

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a. A test schedule for n systems. Subsystems, trains. or other  !

designated components obtained by dividing the specified test interval into i n equal subintervals. and D, The testing of one system. Subsystem, train. or other designated f 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 cool ant. 2 UNIDENTIFIED LEtM GE 1.35 UNIDENTIFIED LEAKAGE shall be all leakage which is not .lDENTIFIED LEAKAGE or  :

CONTROLLED LEAKAGE. .,

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WATERFORD - UNIT 3 1-7 Amendment No. 68

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i RADIDACTIVE EFFLUENTS i i

LIQUID HOLDUP TANKS  ;

i LIMIT]NG CONDITION FOR OPERATION l

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3.11.1.4 The' quantity of radioactive material contained in each of the following ,

unprotected outdoor tanks shall be limited to less than or equal to 7.85 x 10-3 q_52-# I 10-2 curies,* excluding tritium and dissolved or entrained noble gases. For outside ,

temporary storage tanks, the curie content shall be limited such that a rupture will not l' result in exceeding 10 CFR Part 20 limits at the. UNRESTRICTED AREA boundary.

a. PWST

b. Outside temporary tank APPLICABILITY: At all times.

ACTION:

a. W1th the quantity of radtoactive material in any of the above listed tanks exceeding the above limit immediately suspend all additions of radioactive material to j the tank. within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the i events leading to this condition in the next Annual Radioactive Ef fluent Release Report,

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

SURVEILLANCE REQUIREMENTS f 4,11.1.4 The quantity of radioactive material contained in each of the above listed .f tanks shall be determined to be within the above limit by, analyzing a representative i sample of the tank's contents at least once per 7 days when radioactive materials are i being added to the tank.

BasM-+n-8rA--t-ank-sapae4ta-and-an4?Gg of ? x-404-f4ACCM4um-lU equ4 valet-10 CFR Par-t-24-Ag+ndi- B. TeMe44. j

• Based on 80% tank capacity and 10 times the ef fluent concentration (EC) ,

of 1.0 x 1015_pCi/mL Cesium-137 equivalent.10 CFR Part 20. Appendix B,  !

Table 2, Column 2. ,

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WATERFORD - UNIT 3 3/4 11-8 Amendment No. 84-

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I 3/4.11 RADIDACTIVE EFFLUENTS -l i

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, l 3/4.11.1 LIQUID EFFLUENTS -l I 3/4.11.1.1 This section deleted.

3/4.11.1.2 This section deleted. j i

3/4 11.1.3 This section deleted._ j t

3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the. tank contents and that 1 do not have tank overflows and surrounding area drains connected to the 4 Liquid rRadwaste I tTreatment SSystem.  !

- l Restrictirn the quantity of radioactive material contained in the specified tanks ~l provides assurance that in the event of an uncontrolled release of the tank's contents, the  ;

resulting concentrations would be less than 10 times the values given in 14atts of 10 CFR j Mr4-& Appendix B. Table 14 2. Column 2. to 10 CFR 20.1001-20.2402 at the nearest potable i water supply and the nearest surface water supply in an UNRESTRICTED AREA. _l d

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. i WATERFORD - UNIT 3 B 3/4 11-1 Amendment No. 68 i

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, i RADIDACTIVE EFFLUENTS GAS STORAGE TANK.S LIMITING CONDITION FOR OPERATION  !

3.11.2.6 The quantity of radioact1vity contained in each gas storage tank shall be limited to less than or equal to 8.5 x 10 4curies noble gases (considered as Xe-133 equivalent). l l APPLICABILITY: At all times,  !

ACTION  !

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a. With the quantity of radioactive material in any gas storage tank exceeding the above l'imit, immediately suspend all additions of  ;

radioactive material to the tank ,y4_Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limits and describe the events leading to this condition in the next Radioactive Effluent Release Report. l pursuant to Specification 6.9 1.8. [

D. The provision of Specifications 3.0.3 and 3.0.4 are not  !

applicabla 4 l

[URVElLtANCEREQUIREMENTS l 4,11.2.6 The quantity of radioactive material contained in each gas storage tank on,  !

service shall be determined to be within the above limit at least once per 7 days until the ,

quantity exceeds 4.25 x 104 curies noble gases (50% of allowed limit) and then at least once  ;

per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank. Tanks isolated for '

decay will be sampled to verify above limit is met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following removal f rom {

service.

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WATERFORD - UNIT 3 3/4 11-17 l

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5.0 DESIGN FEATURES i

5.1 SITE  !

EXCLUSION AREA ,

5.1.1 The exclusion area shall be as shown in Figure 5.1-1. -

LOW POPULATION ZONE l 5.1.2 Tne low population zone shall be as shown in Figure 5.1-2. i 1

MAP DEFINING UNRESTRICTED AREAS FOR RADIDACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liauid effluents, which will allow l identification of structures and release points as well as definition of UNRESTRICTED AREAS )

within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC. shall be as shown in  !

Figure 5.1-3.  !

i The definition of UNRESTRICTED AREA used in implementing these Technical Specifications has been expanded over that in 10 CFR 20.1003. Ine UNRESTRICTED AREA boundary may coincide with the Exclusion (fenced) Area boundary. as defined in 10 CFR 100 3(a). but the UNRESTRICTED -

AREA does not include areas over water bodies For calculations performed pursuant to 10 CFR 50.36a. the concept of UNRESTRICTED AREAS. established at or beyond the SITE BOUNDARY. I 15 utilized in the Controls to keep levels of radioactive materials in liquid and gaseous I effluents as low as if reasonably achievable.

5.2 CONTAINMENT CONFIGURATION l 5.2.1 The reactor building is a steel containment vessel surrounded by a reinforced  !

concrete shield building I 5.2.1.1 The containment vessel is a cylindrical vessel with a hemispherical dome and an ell 1psoidal buttom and having the following design features:

a. Nominal inside diameter - 140 feet.

b. Nominal inside height = 240 feet 4.75 inches.

c. Nominal thickness of cylindrical wall - 1.903 inches.

d. Nominal thickness of hemispherical dome = 0.95 inch.

e. Nominal thickness of ellipsoidal bottom - 2.25 inches.

f. Net free volume = 2.680.000 cubic feet.

5.2.1.2 The shield building is a cylindrical structure with a shallow dome roof and having the following design features: .)

i

a. Nominal outside diameter = 154 feet.

b. Nominal outside height (from base slab) = 249.5 feet.

c. Nominal thickness of cylindrical wall = 3 feet.

d. Nominal thickness of dome roof = 2.5 feet, l

e. Nominal inside radius of dome roof = 112 feet.

f. Nominal annular space - 4 feet.

DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 44 psig and a temperature of '263 F.

WATERFORD - UNIT 3 5-1 l

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AND LIQUID EFFLUENTS 1

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. ADMINISTRATIVE CONTROLS PROCEDURES AND PR0(iRAMS (Continued)

f. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for:the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC f rom radioactive ef fluents as low as reasonably achievable. The program-(1) shall be contained in the ODCM, (2) shall be implemented by operating '

procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded The program shall include the following elements:

1. Limitation on the operability of radioactive 11guid and gaseous monitoring instrumentation including surveillance tests and setpoint ,

determination in accordance with the methodology in the ODCM.

2. Limitations on the concentrations of radioactive material releascd in ,

liquid effluents to UNRESTRICTED AREAS conforming to 10 times the concentration values in Appendix B, Table M 2 Column 2 to 10 CFR 20.1001-20.2402.

3. Monitoring. sampling. and analysis of radioactive liquid and gaseous  ;

effluents *n accordwe-wt4h pursuant to M-M6 20.1302 and with l-methodology and parameters in the ODCM.  ;

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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 conforming to Appendix 1 to 10 CFR Part 50.

5. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current Calendar year in accordance with the methodology and parameters in the 00CM 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 ~

j these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50 l

7. Limitations on the dose rate resulting from radioactive material ,

released in gaseous effluents from the site to areas beyond the SITE l BOUNDARY shall be limited to the following:-safer 4ing to th^ doses asec4ated-wi&-10 CP Part 20, Appendi' S. Table M. Columni,

a. For noble gases: Less than or equal to a dose rate of 500-mrem / year to the total body and less than or equal to a dose rate of 3000 mrem / year to the skin, and.

b, For Iodine-131, lodine-133, tritium, and for all radionuclides in particulate form with half lives greater than 8 days:

Less than or equal to a dose rate of 1500 mrem / year to any organ.

WATERFORD - UNIT 3 6-16a AMENDMENT NO. 68-m '=r-- y --

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i ADMINISTRATIVE CONTROLS ,

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicdble reporting requirements of Title 10 Code of Federal I Regulations. the following reports shall be. submitted to the Regional Administrator of -i the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT i

6.9.1.1 A summary report of plant startup and power escalation testing shall be 4

submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level. (3) installation of fuel that-has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in.the FSAR and snall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications, Any corrective actions that were required to [

obtain satisf actory operation shall also be described, Any additional specific details '

rc autred in license conditions based on other commitments shall be included in this  !

report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of 1 the startup test program. (2) 90 days following resumption or commencement of commercial  ;

power operation, or (3) 9 months following initial criticality, whichever is earliest.  !

If the startup report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all  :

three events have been completed.

ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be Submitted prior to March 12 of each year. The initial report shall be submitted prior to March 12 of the year following initial criticality. ,

l The results of specific activity analysis in which the primary coolant' exceeded the limits of Specification 3.4,7 shall be submitted annually in acccedance with the aforementioned time frame. The following information shall be included: ,

(1). Reactor. power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the. first sample in which  ;

the limit was exceeded; (2) Results of the last isotopic analysis for radio iodine performed prior to exceeding the limit, results of analysis while limit was exceeded REVIEWERS NOTE : THE FOOTNOTE BELOW HAS BEEN HOVED TO PAGE 6 17a.

mms-tat +dat4on-wpplements-tt+rM4r+ments of ?O A07 OMO CFR Part 20.- l WATERFORD - UNIT 3 6-17 AMENDMENT NO. 8-

' +

ADMINISTRATIVE CONTROLS  ;

ANNUAL REPORTS (Continued) and results of one analysis after the radio iodine activity was reduced to  ;

less than limit. Each result should include date and time of sampling and the radio iodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radio iodine isotope concentration in micro curies per gram as a function of time for the-duration of the specific activity above steady-state level; and (5) The time duration when the specific activity of the primary coolant  ;

exceeded the radio iodine limit.

6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station utility, and other personnel (including contractors), for whom monitoring was required, receiving an annual deep dose equivalent e*fesures greater than 100 mremjyr- and the_tr associated collective deep dose equivalent (reported in person rem) man rm eyesue according to work and job functionsy (e.g. reactor operations and surveillance. inservice inspection, routine maintenance, special maintenance [ describe maintenance]. waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescence dosimeter (TLD) or film badge measurements. Small exposures totaling i less than 20% of the individual total dose need not be ' accounted for. In the aggregate, at least 80% of the total deep dose equivalent received whok-Mdy-dese from external l sources should be assigned to specific major work functions.

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• This tabulation supplements the requirements of 10 CFR 20.2206cf 10 CFR Part 20. l  ;

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l WATERFORD - UNIT 3 6-17a AMENDMENT NO. 8

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ADMINISTRATIVE CONTROLS ,

t ANNUA! RADIDACTIVE Efft.llENT RELEASE REPORT i 6.9.1.8 The_ Annual Radioactive Ef fluent Release Report covering the operation of the [

unit during the previous w#rnhs year of operation shall be submitted wWun-f4-days efter,lanuerp4Jrior to May 1 of each year. The report shall include a Summary of _the-~ ,

quartities of radioactive liquid and gaseous effluents and solid waste released from the {

unit. The material provided shall be (1) consistent with the objectives outline in the [

DDCM and PCP and (2) in conformance with 10 CfR 50.36a and Section IV.B.1 of Append 1' 'l i to 10 CFR Part  !

50.  !

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WATERFORD - l)4IT 3 6-19 Amendment No. 84 j 1

m ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) 6.10.2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety, c All REPORTABLE EVENTS.

d. Records of surveillance activities; inspections, and calibrations required by these Technical Specifications,

e. Records of changes made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results,

h. Records of annual physical inventory of all sealed source material of record.

6,10.3 The following records shall be retained for the duration of the unit Operating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

i

b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup I histories.  !

I

c. Records of radiation e@osure as required by 10 CFR 20. au-4n44444uels- 'I eraerang -radiat4aw.mtsca,weas. j

d. Records of gaseous and liquid radioactive material released to the environs. (

l

e. Records of transient or operational cycles for those unit components identified in  !

Table 5.7-1.

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f. Records of reactor tests and experiments. .

g. Records of training and qualification for current members of the unit staff.

i h Records of inservice inspections performed pursuant to these Technical j Specifications.  ;

WATERFORD - UNIT 3 6-21. l

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f ADMINISTRATIVE CONTROLS q i

RECORD RETENTION (Continued)

i. Records of quality assurance act1vities required by the OA Manual. .

J. Records of reviews performed for changes made to procedures or equipment _or  !

reviews of tests and experiments pursuant to 10 CFR 50.59.  !

I

k. Records of meetings of the POP,C 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 l life commences and associated installation and maintenance records. ]

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m. Records of secondary water sampling and water quality. l l

)

n. Records of audits performed under the requirements of Specification  !

6.5.2.8. )

i h

0. Records of analyses required by the radiological er . mental monitoring i program that would permit evaluation of the accuras . the analysis at a f later date. This should include procedures effective at specified times j and 0A records showing that these procedures were followed. i

p. Records of reviews performed for charges made to the OFFSITE DOSE  !

CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

'i, 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent witt

~

'h the requirements of 10 CFR Part 20 and shal1 be approved. mairitained and adhered to for .l all operations involving persor.nel radiation exposure. i F

6.12 HIGH RADIATION AREA .

642.1 M-lieu-Of-tle "C4Atfol-4V4Ee" 0" " alarm 444Jnal"-4444 fed-by-paragraph 4f--M-C44 l Par 440-eac4wht944+dia t4erwarea-4tuhich4he--m tensity-of-r-adia44en-4-greatw--ttwn400 l mread4wbut-less-tten4000-ar+m/h-sha114+-twr4taded-and4onsp4euously-posted as e h441h  !

redtet4en-aree-an4+ntr-anc+-tter+to4ha1147-contro14ed4f-requir4cg issuance of -a l Radiat4erwMwk-Sermit-GWP)* Any-4nd iv4daal-or--groutwof-4nd4w49als-fermited-to-enter  :

such-ar+as4ha114e.-prov44+4-wite U- roompanied-ty-ore +r-ser+of--the follaw4rvy  !

av A-red 4a tion 4onttor4 ng-oev4c+wht(twoont4nuously-49d4Eates-tte-+a4&at4en i de-rate-m4*+-area r j NN14*sphysics personnel-or-personnel-escor4ed4y-tealt4sphysiss-per4erme' shall te j esmptArom-the " + ssaanee-requer+6ent--dur4n94rgr4sraance+f-14ieir assigned i radtat4on-protest 4er+-dat4+Gr-provided-they-are4therdse-following-plant-r-adiat4en l pret estion-procedures-for--entrf-into-*4434-r444+14orwareas .- i WATERFORD - UNIT 3 6-22 AMENDMENT NO. 68

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i ADMINISTRATIVE C0tl1ROLS i

i ii!GH RADIATION AREA (Continued) j by A-oadiat4(mmnusrang ev4+-wh4(*&-eonta nowsly--4ntegrates-ttwadiah i dose-rate-an44e-area-and-alarg when a precet-4ntegrat(4-4cse ' e rece4ved- '!

94ry4nto-such ereas w44h444s-conner-4c0 device =y-be-ede-after-the -I dese-rate-le ?el in4te-area-tes-tenn-establ46hed-and-personne' haw been i mada4nowledgeable-of-44w- l c- A-tealtthphy54EG-quel 444ed-4nd4+k4ual (1.e. . Qual 444ed4Awadiat4on [

preteetion-proEsiures)-wi th-.3-ra d4s t4erHh%e-ra te-monitoF4 ng-deV4f+A%46 respons4 bie-4er-prev +d4ng-pos444va-sontml-over-t44-ac44 v i t i es a thto--the ' i area-an4-stell-per4omter4odie-r-adia t4en-survei44ance-et--thP ' rec;uency spes4f4ed-by4te-fee 4444yJadtationJrot+et4er+-Super 4ntendant41cclear in -!

tie-M- [

6-42.2 In-addetton44-tte-r+quirenents-of-Stec444 set 4cr 6.12.1, areas-aef+ss4ble40 pasonr+1-with-radiat40n-levels-suebt4et-a4ajor-fwt4en-of-tt e body could4eee4ve-4n  !

one-hcer-awlesa-greater-than 1000 mnems*-sham-be-pre +4ded-with !ncked doors to prc ent '!

unauttw+1ed-entry-and-tte4eys-sheM-te-ma4nta4ned-ender-4he-ademistrat4ve-for4tro1+f  ;

t he-Sh tit-euparv*sor-orHjuty-and/or-healtt4-phystss-superv4 s4en--Doors--shall-remai n loded-e*eept-dur4ng-fer4eds of access by personnel-under an approved-5lWP-whi+h-nha14 ';

spas 44y-tte-40se-rate-levels-4n-tte-4avred4ste-warberea-and-ttema*4 mum al1owable-stay j t4me-for-4 nd444 duals-4n4 hat-area--Tor-mdiv 449al-area s-asse ss4ble-to-per-sonnel-with #

radiat4e 'e e's-suetuthat-a-maew-fet4cn of the body-+oulo-rece+ve-49-4-hour-awjase-4n - j e+cer s of 1004-arumst-that--are-le+at#d-w&th4n-Jacga-areas, such es P" eentainment , " here i no-enclosure-e*+sts-fer-purfeses-of-lock 4ng. and no enclosure-san-be-reasonably -

constructed-around-tte-4n4444 dual-ar n then4 bat-ar+a-sham 4+-rered+ff-sensp4evously posted-and-a-44eshing-44ght shall be ac-t4vete4-as-a-warnim3-de ' ice In lieu sf-the-stay- l time specif4 eat 4en-of thn ", direet-4"' re"9te (such as use of closed-streu4t-TV  !

saceras4-sont4nuous-surveillenc+-may be made by-per-sonnel-qualified in rad 4at4sn  ![

proteet4on-prec#dures4o-prov4de-pos44we-exposure-sontrol-over-tie-as44v44+es-with4n-t he aree-6.13 PROCESS CONTROL PROGRAM (PCP) l 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 documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This documentation shall contain: ;j r

1. Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change (s) and weasurement-ede-e t-44-4Mhe sfrom-soucee<4-cad 4sact4v44y- l ,

WATERFORD - UNIT 3 6-23 AMENDMENT NO. 68 i d

ADMINISTRATIVE CONTROLS j RECORD RETENT10tf (Continued) ,

i

i. Records of quality assurance activities required by the QA Manual, J. Records of reviews performed for changes made to procedures or equipment or ,

reviews of tests and experiments pursuant to 10 CFR 50.59. ,

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

1. Records of the service lives 01 all hydraulic and mechanical snubbers .

required by Specification 3,7.8 incitding the date at which the service life ,

commences and associated installation and maintenance records. l

n. Records of secondary water sampling and water quality. ,

I

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

6

o. Records of analyses required by the radiological environmental monitoring ' j program that would permit evaluation of the accuracy of the analysis at a ' l later date. This should include procedures ef fective at specified times and OA records showing that these procedures were followed.

{

p. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM  :

6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the  ;

requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all ,

operations involving personnel radiation exposure. ,

I o.12 HIGH RADIATION AREA  !

6.12.1 High Radiation Areas with Dose Rates not Exceeding 1.0 rem / hour *- j A. Each entryway to such an area shall be barricaded and  ;

conspicuously posted as a high radiation area. Such barricades may be

• oreached only during periods of personnel entry or exit.

B. Access to, and activities in, each such area shall be controlled by means of a. Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area (s) and other '!

appropriate radiation protection equipment and measures.

• At 30 centimeters from the radiation source or from any surface penetrated by the j

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radiation.

WATERFORD - UNIT 3 6-22 t

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i ADMINISTRATIVE CONTROLS I HIGH RADIATION AREA (Continued) i C. Individuals qualif ted in radiation protection procedures (e.g.  :

health _ physics technicians) and personnel continuously escorted by such _ {

indiv1 duals may be exempted from the requirement for an RWP or equivalent l while performing their assigned duties provided that they are following plant  ;

radiation protection procedures for entry to, exit f rom, and work in such areas. i i

D. Each individual (whether alone or in a group) entering such an area shall possess: I l

(i) A radiation monitoring device that continuously displays

{

radiation dose rates in the area (" radiation monitoring and indicating  ;

device"); or l (11) A radiation monitoring device that continuously integrates l the radiation dose rates in the area and alarms when the device's dose. l alarm setpoint is reached (" alarming dosimeter"), with an appropriate f alarm setpoint, or  !

l (iii)- A radiation monitoring device that continuously transmits' l dose rate and cumulative dose to a remote receiver monitored by radiation protection personnel responsible for controlling personnel  ;

radiation e5posure within the area, or  ;

i (1v) A self-reading dosimeter and, -l t

t (a) Be under the surveillance, as specified in the RWP or i eg_uivalent., while in the area, of an individual at the work ,

site, qualified in radiation protection procedures, equipped >

with a radiation monitoring and indicating device who is responsible for controlling personnel radiation exposure within  ;

the area, or  ;

i (b) Be. under the surve111ance, as specified in the RWP or l equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection a procedures, responsible for controlling personnel radiation l expoture in the area.  !

r E Entry into such areas shall be made only af ter dose rates in the ,

area have been determined and entry personnel are knowledgeable of them.  ;

WATERFORD - UNIT 3- 6-22a i

c. .

ADMINISTRATIVE CONTROLS l

HIGH RADIATION AREA (Continued) 6.12 2 High Radiation Areas with Dose Rates Greater than 1.0 rem / hour

• but I less than 500 rads / hour 2.

f A. Each entryway to such an area shall be conspicuously posted as a high '

radiation area and shall be provided with a locked door, gate or guard that prevents unauthorized entry, and in addition: i (1) All such door and gate keys shall be maintained under the administrative control of the shift Supervisor and/or health physics Staff on duth (ii) Doors and gates shall remain locked or guarded except during  ;

periods of personnel entry or exit.

l B. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose f rates in the immediate work area (s) and other appropriate radiation protection e_quipment and measures. l l

C. Individuals qualified in radiation protection procedures may be  !

exempted from the requirement for an RWP or equivalent while performing j radiation surveys in such areas provided that they are following plant radiation protection procedures for entry to ex1t from, and work in such '

areas.  !

D Each individual (whether alone or in a group) entering such an l area shall possess:  !

(i) An alarming dosimeter with an appropriate alarm setpoint, or (ii) A radiation monitoring device that continuously transmits e dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to ,

communicate with and control every individual in the area, or i

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• At 30 centimeters from the radiation source or from any surface penetrated by the radi ation. ,

• • At 1 meter from the radiation source or from any surf ace penetrated by the radiation. '

WATERFORD UNIT 3 6-22b  ;

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. . - . . e .:

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)

(iii) A self-reading dosimeter and, I

(a) Be under the surveillance, as specified in the RWP or- i equivalent, of an individual qualified in-radiat1on protection I procedures, equipped with a radiation monitoring and indicating j device who is responsible for controlling personnel exposure .

within the area, or (b) Be under the surveillance as specified in the RWP or equivalent, by means of closed circuit television, of personnel l gualified in radiation protection procedures, responsible for j controlling personnel radiation exposure in the area. and with -

{

the means to communicate with and control every individual in '

the area. i E. Entry into such areas shall be made only af ter dose rates in the [

area have been determined and entry personnel are knowledgeable of them.

F. Such individual areas that are within a larger area that is l controlled as a high radiation area, where no enclosure exists for purpose of ,

locking and where not enclosure can reasonably be constructed around the  !

individual area need not be controlled by a locked door or gate, but shall be ,

barricaded and conspicuously posted as a high radiation area, and a l conspicuous, clearly visible flashing light shall be activated at the area as-  ;

a warning device.

6 13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to 1mplementation.  ;

6.13.2 Licensee-initiated changes to the PCP: I

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This documentation shall contain: j

1. Suf ficient information to support the change together with the ,

appropriate analyses or evaluation justifying the change (s) and

2. A determination that the change will maintain the overall i conformance of the solidified waste product to existing requirements of Federal, State. or other applicable regulations. i b, Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.

i WATERFORD - UNIT 3 6-23 AMENDMENT NO. 68 I

( ~ r- a 1

ADMINISTRATIVE CONTROLS _

6.14 0FFSITE DOSE CALCULATION MANUAL CODCM )

6 14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14 2 Licensee-initiated changes to the ODCM.

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This document shall contain:

1. Suf ficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2. A determination that the change wili maintain the level of radioactive effluent control require.1 by_oursuant to 10 CFR EM6 20.1302. 40 CFR Part 190. 10 CFR 50.55a. and Appendix I to 10 CFR Part 50 and not adversel.y impact the accuracy or reliab11ity of ef fluent, dose or selpoint calculations.

b. Shall become effective af ter review and acceptance by the PORC and the approval of the Plant Manager.

c. Shall be submitted to the Commission in the form of a complete. legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in wh1ch any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.

month / year) the change was implemented.

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WATERFORD - UNIT 3 6-24 AMENDMENT NO. 84