ML022560401

Technical Specification Pages

ML022560401
Person / Time
Site:	Nine Mile Point
Issue date:	09/11/2002
From:	NRC/NRR/DLPM
To:
References
TAC MB2442
Download: ML022560401 (29)

Text

SECTION DESCRIPTION PZ'AGE SECTION DESCRIPTION p AGE 3.3.4 Isolation Valves 4.3.4 Isolation Valves 143 3.3.5 Access Control 4.3.5 Access Control 151 3.3.6 Vacuum Relief 4.3.6 Vacuum Relief 153 3.3.7 Containment Spray 4.3.7 Containment Spray 159 3.4.0 Secondary Containment 164 Limiting Condition for Operation Surveillance Requirements 3.4.1 Leakage Rate 4.4.1 Leakage Rate 165 3.4.2 Isolation Valves 4.4.2 Isolation Valves 168 3.4.3 Access Control 4.4.3 Access Control 170 3.4.4 Emergency Ventilation 4.4.4 Emergency Ventilation 173 3.4.5 Control Room Ventilation 4.4.5 Control Room Ventilation 178 3.5.0 Shutdown and Refueling 182 Limiting.Condition for Oneration Surveillance Requirements 3.5.1 Source Range Monitoring 4.5.1 Source Range Monitoring 183 3.5.2 Refueling Platform Interlock 4.5.2 Refueling Platform Interlock 186 3.6.0 General Reactor Plant 191 Limiting Condition for Operation Surveillance Requirements I 3.6.1 Mechanical Vacuum Pump Isolation 4.6.1 Mechanical Vacuum Pump Isolation 192 3.6.2 Protective Instrumentation 4.6.2 Protective Instrumentation 194 3.6.3 Emergency Power Sources 4.6.3 Emergency Power Sources 255 3.6.4 Shock Suppressors (Snubbers) 4.6.4 Shock Suppressors (Snubbers) 259 AMENDMENT NO. i, 176 iii

DESCRIPTION PAGE SECTION 265 Radioactive Material Sources 4.6.5 Radioactive Material Sources 3.6.5 4.6.6 Through 4.6.10 (Deleted) 3.6.6 Through 3.6.10 (Deleted) 4.6.11 Accident Monitoring Instrumentation 268 3.6.11 Accident Monitoring Instrumentation 4.6.12 Reactor Protection System and Reactor 274 3.6.12 Reactor Protection System and Reactor Trip System Power Supply Monitoring Trip System Power Supply Monitoring 4.6.13 Remote Shutdown Panels 277 3.6.13 Remote Shutdown Panels 4.6.14 (Deleted) 3.6.14 (Deleted) 4.6.15 Main Condenser Offgas 295 3.6.15 Main Condenser Offgas 4.6.16 Through 4.6.22 (Deleted) 3.6.16 Through 3.6.22 (Deleted) 4.7.1 Special Test Exceptions - Shutdown 339 3.7.1 Special Test Exceptions - Shutdown Margin Demonstration Margin Demonstration iv AMENDMENT NO.4-4., 176

SECTION DESCRIPTION pAGE Record Retention 370 6.10 6.11 Offsite Dose Calculation Manual (ODCM) 371 6.12 High Radiation Area 371 a 373 6.13 Fire Protection Inspection Systems Integrity 373 6.14 373 6.15 Iodine Monitoring 373 616 10 CFR 50 Appendix J Testing Program Plan 6.17 Inservice Testing Program 374 6.18 Radioactive Effluent Controls Program 374 376 6.19 Explosive Gas and Storage Tank Radioactivity Monitoring Program AMENDMENT NO -42,4-1-5,4W4, 176 vi

1.16 (Deleted) 1.17 (Deleted) 1.18 (Deleted) 1.19 (Deleted) 1.20 (Deleted) 1.21 (Deleted) 6 AMENDMENT NO.4-4.4,4-7.., 176

1.22 (Deleted) 1.23 (Deleted) 1.24 (Deleted) 1.25 (Deleted) 1.26 (Deleted) 1.27 (Deleted)

AMENDMENT NO. 4.42-, 7 176 7

1.28 (Deleted) 1.29 (Deleted) 1.30 Rleactor Coolant Leakage

a. identified Leakaqe (1) Leakage into closed systems, such as pump seal or valve packing leaks that are captured, flow metered and conducted to a sump or collecting tank, or (2) Leakage into the primary containment atmosphere from sources that are both specifically located and known not to be from a through-wall crack in the piping within the reactor coolant pressure boundary.

b. Unidentified Leakage All other leakage of reactor coolant into the primary containment area.

1.31 Core Onerating Limits Report The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1f. Plant operation within these operating limits is addressed in individual specifications.

AMENDMENT NO. Ui, 176 8

3.6.0 GENERAL REACTOR PLANT A) GENERAL APPLICABILITY Applies to mechanical vacuum pump isolation, reactor protection system and emergency power sources.

B) GENERAL OBJECTIVE LIMITING CONDITIONS FOR OPERATION - To define the lowest functional capability or performance level of the equipment to assure overall Station safety.

SURVEILLANCE REQUIREMENTS -To define the test or inspection required to assure the functional capability or performance level of this equipment.

AMENDMENT NO.;W , 176 191

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUI RIEME:NT LI ITIG CNDIiONFOROPEATIONsUIVEILAC AL. JI" FmFNT; V

3.6.1 MECHANICAL VACUUM PUMP ISOLATION 4.6.1 MECHANICAL VACUUM PUMP ISOLATION

a. (Deleted)

a. (Deleted)

b. At least once during each operating cycle (prior to

b. The mechanical vacuum pump line shall be capable startup), verify automatic securing and isolation of of automatic isolation by closure of the air-operated the mechanical vacuum pump.

valve upstream of the pumps. The signal to initiate isolation shall be from high radioactivity (five times normal) in the main steam line.

AMENDMENT NO. Uik, 176 192

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT UMITNGONDTIONFOROPEATIO SUVEILANC REUIRMEN (8) Mechanical Vacuum Pump Isolation - The mechanical vacuum pump shall be Isolated or the Instrument channel shall be considered Inoperable and Specification 3.6.1 shall be applied.

(9) Diesel Generator Initiation - The diesel generator shall be considered inoperable and Specification 3.6.3 shall be applied.

(10) Emergency Ventilation Initiation - The emergency ventilation system shall be considered Inoperable and Specification 3.4.4 shall be applied, (11) High Pressure Coolant Injection Initiation The high pressure coolant injection system shall be considered inoperable and Specifi cation 3.1.8.c shall be applied.

(12) Control Room Ventilation - The control room ventilation system shall be considered Inoperable and Specification 3.4.5 shall be applied.

AMENDMENT NO.+Q,+*,-4 176 196

BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION High Flow-Main Steam Line, +/--1 psid High Flow-Emergency Cooling Line, +/- 1 psid High Area Temperature-Main Steam Line, +/-:10OF High Area Temperature-Clean-up and Shutdown, +/--6IF High Radiation-Main Steam Line, + 100% and -50% of set point value High Radiation-Reactor Building Vent, + 100% and -50% of set point High Radiation-Refueling Platform, + 100% and -50% of set point with NEDC-30851P-A, Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance Protection System," and MDE-77-0485, "Technical Specification Improvement "Technical Specification Improvement Analyses for BWR Reactor Analysis for Nine Mile Point Nuclear Station, Unit 1."

with NEDC-30851 P-A Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance and Suppl2, "Technical Specification Improvement Analyses for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation,"

Because of local high with NEDC-31677P-A, "Technical Specification Improvement Analyses for BWR Isolation Actuation Instrumentation."

only be done during periods of Station shutdown. These radiation, testing instrumentation in the area of the main steam line isolation valves can functions include high area temperature isolation and isolation valve position scram.

252 AMENDMENT NO. U,, 176

Pages 282 Through 294 Deleted I AMENDMENT NO. iW, 176 282

U MITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT L.IVI~lIN(I OND TIO FOR1P66%04.SU VEILANE"RUI-ME 4.6.15 MAIN CONDENSER OFFGAS I 1 3.6.15 MAIN CONDENSER OFFGAS Applicability: Applicability:

Applies to the periodic test and recording Applies to the radioactive effluents from the main I condenser.

requirements of main condenser offgas.

Obiective:

I Obiective:

To ascertain that radioactive effluents from the main To assure that radioactive material is not released to the environment in any uncontrolled manner and is within the condenser are within allowable values of I OCFR20, Appendix B and IOCFR50, Appendix I.

I limits of 10CFR20 and 10CFR50 Appendix I.

Specification:

Specification:

I The gross radioactivity (beta and/or gamma)

The gross radioactivity (beta and/or gamma) rate rate of noble gases from the recombiner of noble gases measured at the recombiner discharge shall be determined to be within discharge shall be limited to less than or equal to the limits of Specification 3.6.15 at the 500,000 l.i/sec. This limit can be raised to 1 following frequencies by performing an Ci/sec. for a period not to exceed 60 days isotopic analysis of a representative sample provided the offgas treatment system is in of gases taken at the recombiner discharge:

operation.

Monthly.

With the gross radioactivity (beta and/or gamma) rate of noble gases at the recombiner discharge Within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> following an exceeding the above limits, restore the gross increase on the recombiner radioactivity rate to within its limit within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> discharge monitor of greater than or be in at least Hot Shutdown within the next 12 50%, factoring out increases due hours. to changes in thermal power level and dilution flow changes.

176 295 AMENDMENT NO. 442-,

BASES FOR 3.6.15 AND 4.6.15 MAIN CONDENSER OFFGAS Restricting the gross radioactivity rate of noble gases from the main condenser provides assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a very small fraction of the limits of 10CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10CFR Part 50. The primary purpose of providing this specification is to limit buildup of fission product activity within the station systems which would result if high fuel leakage were to be permitted over extended periods.

AMENDMENT NO. WL, 176 296

Pages 297 Through 338 Deleted I AMENDMENT NO. ; 176 1, 297

b. Occupational Radiation Exposure Report. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors), for whom monitoring was performed, receiving an annual deep dose equivalent of

> 100 mrems and the associated collective deep dose equivalent (reported in man-rem) according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special-maintenance (describe maintenance), waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket ion chamber, thermoluminescence dosimeter (TLD,, electronic dosimeter, or film badge measurements. Small exposures totaling

< 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total deep dose equivalent received from external sources should be assigned to specific major work functions. The report covering the previous calendar year shall be submitted by April 30 of each year.

c. Monthly Operating Report. Routine reports of operating statistics and shutdown experience including documentation of challenges to the safety relief valves or safety valves, shall be submitted on a monthly basis, which will include a narrative of operating experience, in accordance with 10 CFR 50.4, no later than the 15th of each month following the calendar month covered by the report.

AMENDMENT NO. 176W362 362

d. Annual Radiological Environmental Operatinq Report*.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses 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 the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological I environmental samples and of all environmental radiation measurements taken during the period pursuant to the I locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

I A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

363 AMENDMENT NO. 176 363

I

e. Radioactive Effluent Release Reoort*

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

AMENDMENT NO. i{i, 176 364

This Page Intentionally Blank I 176 365 AMENDMENT NO. W,

I

f. CORE OPERATING LIMITS REPORT

1. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle for the following:

1) The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for Specification 3.1.7.a and 3.1.7.e.

2) The Kf core flow adjustment factor for Specification 3.1.7.c.

3) The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.1.7.c and 3.1.7.e.

4) The LINEAR HEAT GENERATION RATE for Specification 3.1.7.b.

5) The Power/Flow relationship for Specification 3.1.7.d and e.

and shall be documented in the CORE OPERATING LIMITS REPORT.

2. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents.

4,W AMENDMENT NO. 1/L 176 366

6.9.3 Special Reports Special reports shall be submitted in accordance with 10 CFR 50.4 to the Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. Reactor Vessel Material Surveillance Specimen Examination, Specification 4.2.2(b) (12 months).

b. (Deleted)

c. (Deleted)

d. (Deleted)

e. (Deleted)

f. (Deleted)

g. Sealed Source Leakage In Excess Of Limits, Specification 3.6.5.2 (Three months).

AMENDMENT NO. 4-2-,-- 3, 176 368

This Page Intentionally Blank I 369 AMENDMENT NO. W{-, 176

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

f. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

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

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the 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 SORC and the SRAB.

6.11 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gases and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm-and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b. The ODCM shall also contain the radioactive'effluent controls and radiological environmental monitoring activities, and 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.d and Specification 6.9.1.e.

c. Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

(a) Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and (b) A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; AMENDMENT NO. Ul, 176 371

2. Shall become effective after the approval of the plant manager or a designee; and

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of, or concurrent with, the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shali 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 (i.e., month and year) the change was implemented.

6.12 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601 (a) and (b) of 10 CFR Part 20:

6.12.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

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.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation dose rates in the area, or

2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or 371a I AMENDMENT NO. 176

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (I) Be under the surveillance, as specified in the RWP or equivalent, while In the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified In radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

AMENDMENT NO. 176 371 b I

6.12.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at I Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the Station Shift Supervisor - Nuclear, radiation protection manager, or his or her designee.

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

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 rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified In radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess one of the following:

1. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

2. A radiation monitoring device that continuously transmits 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

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, AMENDMENT NO.442P 176 372

(i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

AMENDMENT NO. 176 372a

I

4. The combined Local Leak Rate Test (Type B & C Tests including airlocks) acceptance criteria is less than 0.6 L., calculated on a minimum pathway basis, at all times when containment integrity is required.

The provisions of Specification 4.0.1 do not apply to the test frequencies specified in the 10 CFR 50 Appendix J Testing Program Plan.

6.17 Inservice Testing Program This program provides controls for inservice testing of Quality Group A, B, and C pumps and valves.

a. Inservice testing of Quality Group A, B, and C pumps and valves shall be performed in accordance with requirements for American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components specified in Section Xl of the applicable ASME Boiler and Pressure Vessel Code Edition and Addenda, subject to the applicable provisions of 10QCFR50.55a;

b. The provisions of Specification 4.0.1 are applicable to the normal and accelerated testing frequencies for performing inservice testing activities; Technical

c. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Specification.

6.18 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a 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 shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 20.2402; 176 374 AMENDMENT NO. 4-54,4-*,3,

c Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. 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 10 CFR 50, Appendix I;

e. 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 ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:

1. For noble gases: a dose rate <500 mrems/yr to the whole body and a dose rate _3000 mrems/yr to the skin, and

2. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days: a dose rate :!500 mrems/yr to any organ;

h. 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 10 CFR 50, Appendix 1;

. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives >8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190; and AMENDMENT NO. 176 375 1

k. Limitations on venting and purging of the primary containment through the Emergency Ventilation System to maintain releases as low as reasonably achievable.

The provisions of Surveillance Requirement 4.0.1 are applicable to the Radioactive Effluent Controls Program surveillance frequencies.

6 19 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Main Condenser Offgas Treatment System and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

a. The limits for concentrations of hydrogen in the Main Condenser Offgas Treatment System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e.,

whether or not the system is designed to withstand a hydrogen explosion); and

b. A surveillance program to ensure that the quantity of radioactivity contained in all outside temporary liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is <10 Ci, excluding tritium and dissolved or entrained noble gases.

The provisions of Surveillance Requirement 4.0.1 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

AMENDMENT NO. 176 376