ML20129K340

Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620

ML20129K340
Person / Time
Site:	Oyster Creek
Issue date:	11/12/1996
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20129K338	List: ML20129K337 ML20129K340
References
NUDOCS 9611210028
Download: ML20129K340 (14)

Text

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1.28 FRACTION OF RATED POWER (FRP)

The FRACTION OF RATED POWER is the ratio of core thermal power to rated thermal power.

I 1.29 TOP OF ACTIVE FUEL (TAF) - 353.3 inches above vessel zero.

1.30 REPORTABLE EVENT

[

'A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 l

CFR Part 50.

I 1.31 IDENTIFIED LEAKAGE IDENTIFIED LEAKAGE is that leakage which is collected in the primary containment equipment drain tank and eventually transferred to radwaste for processing.

1.32 UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE is all measured leakage that is other than identified leakage.

1.33 PROCESS CONTROL PLAN The PROCESS CONTROL PLAN shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processmg of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61 and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

1.34 AUGMENTED OFFGAS SYSTEM (AOG)

The AUGMENTED OFFGAS SYSTEM is a system designed and installed to holdup and/or process radioactive gases from the main condenser offgas system for the purpose of reducing the radioactive material content of the gases before release to the environs.

1.35 MEMBER OF THE PUBLIC A MEMBER OF THE PUBLIC is a person who is not occupationally associated with GPU Nuclear and who does not normally frequent the Oyster Creek Nuclear Generating Station site.

The category does not include contractors, contractor employees, vendors, or persons who enter the site to make deliveries, to service equipment, work on the site, or for other purposes associated with plant functions.

1.36 OFFSITE DOSE CALCULATION MANUAL (ODCM)

An OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and OYSTER CREEK 1.0-6 Amendment No.: 14, 28,29,75,84,108,138,166 Correction 10-10-78 9611210028 961112 PDR ADOCK 05000219' P

PDR

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e

' param'eters to be used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous and liquid efIluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Efiluent Controls and Radiological r

Environmental Monitoring Programs required by Section 6.8.4; and (2) descriptions of the information that should be included in the Annual Radioactive Efiluent Release Report AND Annual Radiological Environmental Operating Report required by Specifications 6.9.1.d and 6.9.1.e, respectively.

1.37 PURGE PURGE OR PURGING is the controlled process of discharging air or gas from a confmement and replacing it with air or gas.

1.38 EXCLUSION AREA EXCLUSION AREA is defined in 10 CFR part 100.3(2). As used in these technical specification, the Exclusion Area boundary is the perimeter line around the OCNGS beyond which the land is neither owned, leased, nor otherwise subject to control by GPU (ref ODCM Figure 1-1). The area outside the Exclusion Area is termed OFFSITE or UNRESTRICTED AREA.

i 1.39 REACTOR VESSEL PRESSURE TESTING System pressure testing required by ASME Code Section XI, Article IWA-5000, including system leakage and hydrostatic test, with reactor vessel completely water solid, core not critical and section 3.2. A satisfied.

1.40 SUBSTANTIVE CHANGES SUBSTANTIVE CHANGES are those which affect the activities associated with a document or the document's meaning or intent. Examples of non-substantive changes are: (1) correcting spelling, (2) adding (but not deleting) cign-off spaces, (30 ble-: king in notes, cautions, etc, (40 changes in corporate and personnel titles which do not reassign responsibilities and which are i

not referenced in the Appendix A Technical Specifications, and (5) changes in nomenclature or editorial changes which clearly do not change function, meaning or intent.

I 1,41 DOSE EOUIVALENT I-131 1

DOSE EQUIVALENT I-131 shall be that concentration ofI-131 microcuries per gram which alone would produce the'same thyroid dose as the quantity and isotopic mixture ofI-131, !-

132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 or Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Efiluences for the Purpose of Evaluating Compliance with 10 CFR Par 40 Appendix I."

. OYSTER CREEK 1.0-7 Amendment No.: 108,120,125,126,138,147

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1,42

• AVERAGE PLANAR LINEAR HEAT GENERATION RATE The AVERAGE PLANAR LINLAlt HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit i

length of fuel rod for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at that height.

1.43 CORE OPERATING LIMITS REPORT l

The Oyster Creek CORE OPERATING LIMITS REPORT (COLR) is the 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 6.9.1.f. Plant operation within these operating limits is addressed in individual specifications.

1 l.44 LOCAL LINEAR HEAT GENERATION RATE The LOCAL LINEAR HEAT GENERATION RATE (LLHGR) shall be applicable to a specific j

planar height and is equal to the AVERAGE PLANAR LINEAR GENERATION RATE (APLHGR) at the specified height multiplied by the local peaking factor at that height.

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1.45 SHUTDOWN MARGIN (SDM)

SHUTDOWN MARGIN is the amount of reactivity by which the reactor would be subcritical j

when the control rod with the highest reactivity worth is fully withdrawn, all other operable control rods are fully inserted, all inoperable control rods are at their current position, reactor a

water temperature is 68 F, and the reactor fuel is xenon free. Determination of the control rod with the highest reactivity worth includes consideration of any inoperable control rods which are i

not fully inserted.

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i OYSTER CREEK 1.0-8 Amendment No.: 147,178 5

j Reactor Modes Min. No. of Min. No. of in which Function OPERABLE or Instrument j

Must Be OPERABLE OPERATING Channels Trip

[ tripped]

OPERABLE Action

)

Function Setting Shutdown Refuel Startup _R_un Trip Systems Trio System Required

• H. Isolation Condenser Isolation (See Note hh)

Isolate

1. High Flow

$ 20 psig P X(s)

X(s)

X X

2 2(oo)

Isolation i

Steam Line Condenser, comply with l

2. High Flow 5 27" P H2O X(s)

X(s)

X X

2 2(oo)

Spec. 3.8 i-Condensate See note dd Line I. Offgas System Isolation

1. High 5 2,000 mrem /hr X(s)

X(s)

X X

1(ii) 2(ii)

See Notejj

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Radiation In Offgas Line (e)

J. Reactor Building Isolation and Standby Gas Treatment System Initiation Isolate Reactor

1. High Radiation 5100 mR/ X(w)

X(w)

X X

1 1

Building i

Reactor Building hr and Initiate j

Operating Floor Standby Gas Treatment

2. Reactor 517 mR/hr X(w)

X(w)

X X

1 1

System or i

Building Manual j

Ventilation Surveillance 2

Exhaust for not more j

thar. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

3. High Drywell 5 3.5 psig X(u)

X(u)

X X

1(k) 2(k)

(total for Pressure all instru-ments under l

J)

4. Low-Low

> 7'2" above X X

X X

1 2

in any 30-day Reactor Water TOP OF period Level ACTIVE FUEL OYSTER CREEK 3.1-12 Amendment No.: 72,79,91,108,112,171 Change: 4

TABLE 3.1.1 (CONT'D)

Action required when minimum conditions for operation are not satisfied. Also permissible to trip inoperable trip system. A channel may be placed in an j

inoperable status for up to six hours for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE instrument channelin the same trip system is monitoring that parameter.

See Specification 2.3 for Limiting Safety System Settings.

Notes:

Permissible to bypass, with control rod block, for reactor protection system reset in REFUEL MODE.

a.

b.

Permissible to bypass below 800 psia in REFUEL and STARTUP MODES.

c.

One (1) APRM in each OPERABLE trip system may be bypassed or inoperable provided the requirements of Specification 3.1.C and 3.10.C are satisfied. Two APRM's in the same quadrant shall not be concurrently bypassed except as noted below or permitted by note.

Any one APRM may be removed from service for up to six hours for test or calibration without inserting i

trips in its trip system only if the remaining OPERABLE APRM's meet the requirements of Specification 3.1.B.1 and no control rods are moved outward during the calibration or test. During this short period, the requirements of Specifications 3.1.B.2, 3.1.C and 3.10.C need not be met.

d.

The IRMs shall be inserted and OPERABLE until the APRMs are OPERABLE and reading at least l

2/150 full scale.

e.

Offgas system isolation trip set at 52,000 mRum/hr. Air ejector isolation valve closure time delay shall not exceed 15 minutes.

f.

Unless SRM chambers are fully inserted.

Not applicable when IRM on lowest range.

1 g.

i h.

One instrument channel in each trip system may be inoperable provided the circuit which it operates in the trip system is placed in a simulated tripped condition. If repairs cannot be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i

the reactor shall be PLACED IN THE COLD SHUTDOWN CONDITION. If more than one instrument channel in any trip system becomes inoperable, the reactor shall be PLACED IN THE COLD -

SHUTDOWN CONDITION. Relief valve controllers shall not be bypassed for more than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (total i

j time for all controllers) in any 30-day period and only one relief valve controller may be bypassed at a

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time.

i.

The interlock is not required during the start-up test program and demonstration of plant electrical 4

output but shall be provided following these actions.

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Not required below 40% of turbine rated steam flow.

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OYSTER CREEK 3.1-16 Amendment No.: 75,108,110,171,184 1

a

3.6 Radioactive Efiluents Apilicability: Applies to the radioactive efiluents of the facility.

3 Obiective: To assure that radioactive material is not released to the environment in an uncontrolled manner and to assure that the radioactive concentrations of any material released is kept as low as is reasonably achievable and, in any event, within the limits of 10 CFR part 20.1301 and 40 CFR Part 190.10(a).

Specification:

3.6.A. Reactor Coolant Radioactivity The specific activity of the primary coolant except during REFUEL MODE shall be limited to: Less than or equal to 0.2 microcuries per gram DOSE EQUIVALENT (D.E.) I-131.

Limiting Condition for Operation

1. Whenever an isotopic analysis shows reactor coolant activity exceeds 0.2 uCi/ gram DOSE EQUIVALENT (D.E.) I-131, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Additional analyses shall be done at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the specific activity of the primary coolant is restored to within its limit.

2. If the reactor coolant activity is greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 4.0 microcuries per gram D.E. I-131, be in at least SHUTDOWN CONDITION within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3. Annual Reporting Requirement The results of specific activity analyses in which the reactor coolant exceeded the limits of Specification 3.6.A shall be reported on an annual basis. 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 until after the radiciodine activity is reduced to less than tL: limit; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after radiciodine activity was reduced to less than the 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 until after the radiciodine activity is reduce to less than the limit; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and, (5) The time duration when specific activity of the primary coolant exceeded the radiciodine limit.

If there are consecutive. thermal power changes by more than 15% per hour, take sample and analyze at least gne sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the change and at least once per four hours thereafter, until the specific activity of the primary coolant is restored to within limits.

OYSTER CREEK 3.6 1 Amendment No.: 48,108,126,166

3.'.C Restricting the quantity of radioactive material contained in the specified tanks provides assurance 6

that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would 3

be less than the limits of 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2 in the canal at the Route 9 bridge.

}

Retaining radioactive liquids on-site in order to permit systematic and appropriate processing is consistent with maintaining radioactive discharges to the environ.nent as low as practicable. Limiting the contents of each outside tank to 10 curies or less assures that even if the contents of a tank were released onto the ground and drained into the discharge canal, the potential dose to a member of the public is estimated to be less than I percent of the 500 mem/ year limit to the total body of a member j

of the public and only 1 percent of the corresponding 1500 mrem / year standard for a single organ.

In the highly unlikely event that every outside tank named in Specification 3.6.C were to contain 10

. curies and the contents of all were to spill into the discharge canal, the potential dose to a member of the public is estimated to be only about 2 percent of the 500 mrem / year limit to the total body and about 6 percent of the corresponding 1500 mrem / year standard.

l 3.6.D RELOCATED TO THE ODCM I

3.6.E Some radioactive material released from the plant under controlled conditions as part of the normal -

operation of the facility.. Other radioactive material not normally intended for release could be inadvertently released in the event of an accident. Therefore, limits in 10 CFR Part 20 apply to releases during normal operation and limits in 10 CFR Part 100 apply to accidental releases Radioactive gases from the reactor pass through the steam lines to the turbine and then to the main j-condenser where they are extracted by the air ejector, passed through holdup piping and released via the plant stack preferably aner treatment in the Augmented Offgas System. Radioactive materials release limits for the plant stack have been calculated using meteorological data from a 400 ft tower at the plant site. The analysis of these on-site meteorological data shows that a release of radioactive i

gases aRer holdup in the offgas system, would not result in a whole body radiation dose exceeding i

the 10 CFR 20 value of 0.1 rem per year.

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OYSTER CREEK 3.6-5 Amendment No.: 49,108,126,166

Whole body dose was calculated to determine the offgas system isolation trip setpoints for the Steam

• Jct Air Ejector (SJAE) radiation monitor using RAC Code from gamma dose due to cloud passage over the receptor and not cloud submersion in which beta dose could be additive. The Holland plume rise model with no correction factor was used in the calculation of the effect of momentum and buoyancy of a continuously emitted plume. The source terms for.this calculation assumes historical (i.e., 1989-1990) offgas isotopic composition, site specific meteorological conditions, plant specific offgas flow rates and takes credit for AOG operation 60 percent of the time.

These calculations have established that a dose rate of < 2,000 mrem /hr at the SJAE Offgas Radiation Monitor is within 10 CFR 20.1301(a)(1) limits, i.e., less than 100 mrem in a year.

o 1

3.6.F The purpose of Specification 3.6.F is to require that the concentration of potentially explosive gas mixtures in the Augmented OfTgas System be maintained below the flammability limit of hydrogen in air, although the AOG is designed to withstand a hydrogen explosion. Specification 3.6.F applies to the hydrogen concentration downstream of a recombiner during AOG operation. The AOG has j

2 redundant recombiners so that the recombiner in use can be isolated and purged with air in the event 4

hydrogen in it exceeds the specified limit.

3.6.G NOT USED J

3.6.H NOT USED 3.6.I RELOCATED TO THE ODCM j

4 3.6.J RELOCATED TO THE ODCM 3.6.K RELOCATED TO THE ODCM 3,6.L RELOCATED TO THE ODCM 3.6.M RELOCATED T THE ODCM 3.6.N RELOCATED TO THE ODCM i

1 4

OYSTER CREEK 3.6-6 Amendment No.: 49,108,166

4.6. R,ADIOACTIVE EFFLUENT Applicability: Applies to monitoring of gaseous and liquid radioactive effluents of the Station during release o effluents via the monitored pathway (s). Each Surveillance Requirement applies whenever the corresponding Specification is applicable unless. otherwise stated in an individual Surveillance Requirement. Surveillance Requirements do not have to be performed on inoperable equipment Obiective:

To measure radioactive effluents adequately to verify that radioactive effluents are as low as is reasonably achievable and within the limit of 10 CFR Part 20.

Specification:

A.

Reactor Coolant Reactor coolant shall be sampled and analyzed at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for DOSE EQUIVALENT l-131 during RUN MODE, STARTUP MODE and SHUTDOWN CONDITION.

B.

NOT USED.

C.

Radioactive Liauid Storage 1.

Liquids contained in the following tanks shall be sampled and analyzed for radioactivity at least once per 7 days when radioactive liquid is being added to the tank:

l

a. Waste Surge Tank, HP-T-3;

b. Condensate Storage Tank.

D.

Main Condenser Offgas Treatment RELOCATED TO THE ODCM.

E.

Main Condenser Offgas Radioactivity j

1.

The gross radioactivity in fission gases discharged from the main condenser air ejector shall be measured by sampling and analyzing the gases.

a. at least once per month, and

b. When the reactor is operating at more than 40 percent of rated power, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after an increase in the fission gas release via the air ejector of more than 50 percent, as indicated by the j

Condenser Air Ejector Offgas Radioactivity Monitor after factoring out increase (s) due to change (s) in the thermal power level.

F.

Condenser Offgas Hydrogen Concentration The concentration of hydrogen in offgases downstream of the recombiner in the Offgas System shall be monitored with hydrogen instrumentation as described in Table 3.15.2.

O.

NOT USED.

H.

NOT USED.

OYSTER CREEK 4.6-1 Amendment No.: 108,126,166

6.8.4 The following programs shall be established, implemented and ' maintained:

i

/ adioactive Emuent Controls Program R

' a.

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A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive emuent and for maintaining the doses to MEMBERS OF THE PUBLIC form radioactive emuent 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 i

i be taken whenever the program limits are exceeded. The program shall include the j

{

following elements:

1.

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including the surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2.

Limitations on the concentrations of radioactive material released in liquid emuents to the UNRESTRICTED AREA conforming to less than the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402.

3.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluent in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM.

4.

Limitations on the annual and quarterly doses and dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluent released to the UNRESTRICTED AREA conforming to Appendix I of 10 CFR 50, 5.

Determination of cumulative and projected dose contributions from radioactive emuent for the current calendar quarter and the 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 the 31 day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR 50,

.7.

Limitations on the dose rate resulting from radioactive materials released in gaseous emuents from the site to the UNRESTRICTED AREA shall be limited to the following:

a.

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

For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives grater than 8 days: Less than or equal to a dose rate of 1500 mRems/yr to any organ.

8.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous emuents to the UNRESTRICTED AREA conforming to Appendix I of 10 CFR 50, OYSTER CREEK 6-11 Amendment No.: 69,78,84,108,125,134,166

. 6.9 '.

, REPORTING REOUIREMENTS Ih addition to the applicable reporting requirements of 10 CFR, the following identified reports shall

- be submitted to the Administrator of the NRC Region I office unless otherwise noted.

6.9.1 ROUTINE REPORTS Startup Report. A summary report of plant startup and power escalation testing shall a.

be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating 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 specified details required in license conditions based on other commitments shall be included in this report.

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

b.

Annual Exoosure Data Report. Routine exposure data repons covering the operation of the facility during the previous calendar year shall be submitted prior to April 30 of each year. Reports shall contain a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) for whom monitoring is required receiv' g exposures greater m

than 100 mrem /yr. and their associated man rem exposure according to work and job functions (this tabulation supplements the requirements of Section 20.2206 of 10 CFR Part 20), e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the i

individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

c.

Monthly Operating Report. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis which will include a narrative of operating experience, to the Director, Office of Management and Program Control, U. S. Nuclear Regulatory Commission, with a copy to the Regional Office, no later than the 15th of each month following the calendar month covered by the report.

OYSTER CREEK 6-13 Amendment No.: 69, 78, 84,108,125,134,166

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' 6.,10 RECORD RETENTION

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• 6.10:1 The following records shall be retained for at least five years-l

?

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

a.

i b.

Records and logs of principle maintenance activities, inspections, repair and j

replacement of principal items of equipment related to nuclear safety.

c.

All Licensee Event Reports.

d.

Records of surveillance activities, inspections and calibrations required by these

)

technical specifications.

j e.

Records of reactor ats and experiments.

f.

Records of changes made to operating procedures.

i g.

Deleted.

i

h. ' Records of sealed source leak tests and results.

i.

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

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6.10.2 The following records shall be retained for the duration of the Facility Operating License:

i a.

Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

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b.

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

i c.

Records of facility radiation and contamination surveys.

d.

Records of doses received by all individuals for whom monitoring was required entering radiation control areas.

e.

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

f.

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

g.

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

h.

Records ofinservice inspections performed pursuant to these technical specifications.

i.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

j.

Records of reviews by the Independent Onsite Safety Review Group.

OYSTER CREEK 6-17 Amendment No.: 69,108,177,134,166

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

k.

Records of Environmental Qualification which are covered under the provisions for 4

~,

3 paragraph 6.14.

1.

Records of the service lives of all snubbers, including the date which the service life commences, and associated installation and maintenance records.

5 Records of results of analyses' required by the Radiological Environmental m.

Monitoring Program.

4 1

n.

Records of reviews performed for changes made to the OFFSITE DOSE i

CALCULATION MANUAL and the PROCESS CONTROL PLAN.

1-o.

Records of radioactive shipments.

i 6.10.3 Quality Assurance Records shall be retained as specified by the Quality Assurance Plan.

t 6.11 RADIATION PROTECTION PROGRAM 1

i Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

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6.12 (Deleted) i I

6.13 HIGH RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by Section 20.1601 of 10 CFR 20, each high radiation area in which the intensity of radiation at 30 cm (11.8 in.) is i.

greater than deep dose equivalent of 100 mrem /hr but less than 1,000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall i

be controlled by requiring issuance of a Radiation Work Permit (RWP).

NOTE:- Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are j

following plant radiation protection procedures for entry into high radiation areas.

I i

An individual or group ofindividuals permitted to enter such areas shall be provided with one or more of the following:

i a.

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

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a pre-set integrated dose is received. Entry into such areas'with this monitoring device may be made after the dose rate levels in the area I

have been established and personnel have been made knowledgeable of them.

J f

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

3 procedures) with a radiation dose rate monitoring device who is responsible for providing positive exposure control over the activities within the area and who will perform periodic radiation surveillance at the frequency in the RWP. The surveillance frequency will be established by the Director responsible for 4

radiological controls.

i OYSTER CREEK 6-18 Amendment No.: 69,100,108,134,166

6.13.2 Specification 6.13.1 shall also apply to each high radiation area in which the intensity of radiation is greater than deep dose equivalent of 1,000 mrem /hr at 30 cm (11.8 in.) but less than 500 rads in I hour at I meter (3.28 ft.) from sources ofradioactivity. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of operations and/or radiation protection supervision on duty.

6.14 ENVIRONMENTAL OUALIFICATION 1

A.

By no later than June 30,1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 " Interim Staff Position of Environmental Qualification of Safety-Related Electrical Equipment," December 1979. Copies of these documents are attached to Order for Modification ofI.icense DPR-16 dated October 24, 1980.

t B.

By no later than December 1,1980, complete and auditible records must be available and i

maintained at a central location which describe the environmental qualification method used l

for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, fu ther tested, or otherwise further qualified.

1 6.15 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluida during a serious transient or accident to as low as practicallevels. This program shallinclude the following:

l 1.

Provisions establishing preventative maintenance and periodic visual inspection requirements, and 2.

System leak test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequency of once every 24 months. The systems subject to j

this testing are (1) Core Spray, (2) Containment Spray, (3) Reactor Water Cleanup, j

(4) Isolation Condenser, and (5) Shutdown Cooling.

6.16 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

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

a.

Training of personnel, b.

Procedures for monitoring, and c.

Provisions for maintenance of sampling and analysis equipment.

• Areas requiring personnel access for establishing hot shutdown condition.

OYSTER CREEK-6-19 Amendment No.: 69,108,134,141,166