ML20059L627
| ML20059L627 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 11/05/1993 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20059L622 | List: |
| References | |
| NUDOCS 9311170237 | |
| Download: ML20059L627 (14) | |
Text
DEFINITIONS - (Cont'd) b.
The freight door is closed, c.
Each air lock is OPERABLE, d.
The containment leakage rates are within the limit, and The sealing mechanism associated with each penetration (e.g.,
e.
welds, bellows, o-rings) is OPERABLE.
CONTROLLED AREA A CONTROLLED AREA shall be any area outside of the RESTRICTED AREA, but within the EXCLUSION AREA, access to which can be limited by Dairyland Power Cooperative for any reason.
EFFLUENT RELEASE BOUNDARY The Dairyland Power Cooperative property line within the 1109 ft. (338m) radius EXCLUSION AREA is the EFFLUENT RELEASE BOUNDARY.
(See Figure 1, Sec. 4.)
EXCLUSION AREA The EXCLUSION AREA is defined as the area within an 1109 ft. (338m) radius from the centerline of the Containment Building. This was the area established per 10 CFR 100 as the EXCLUSION AREA for plant siting and operation.
FREOUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Survel..nce Requirements shall correspond to the intervals defined in Tabi..;f Surveillance Frequency Notation.
j FUEL HANDLING RJEL HANDLING shall be the movement of any irradiated fuel within the Containment Building. Suspension of FUEL HANDLING shall not preclude completion of movement of the fuel to a safe conservative position.
MEMBER OF THE PUBLIC MEMBER OF THE PUBLIC shall mean an individual in a CONTROLLED or Uh1ESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose.
TS 2-2 9311170237 931105 I
PDR ADOCK 05000409
- 4 4
P PDR qy.
DEFINITIONS - (Cont'd) 0FFSITE DOSE CALCU1ATION MANUAL (ODCM)
An OFFSITE DOSE CALCUIATION MANUAL (ODCM) shall be a manual containing the I
methodology and parameters te be used for the calculation of offsite doses due to radioactive gaseous and liquid effluents and for the calculation of
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gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints.
j It shall describe the radiological envirormental monitoring program.
OPERARTI-OPERABILITY subsystem,. train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and A system, when all necessary attendant instrumentation, controls, a normal or an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
PROCESS CONTROL PROGRAM (PCF)
The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive vastes based on demonstrated processing of actual or simulated solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20, 10 CFR Part 61 and Federal and State regulations and other requirements governing the transportation and disposal of the radioactive waste.
REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section A Licensee Event Report shall be submitted for REPORIABLE EVENTS.
6.8.3.
j RESTRICTED AREA A RESTRICTED AREA is an area for which access shall be limited for the purpose of protecting individuals from radiation and radioactive materials.
RESTRICTED AREAS shall be designated by radiation control signs and markers These RESTRICTED AREAS shall in accordance with 10 CFR 20.1901 and 20.1902.
include the Turbine Building beyond the change room door, the Containment Building, the Vaste Treatment Building, and any other areas so marked by radiation signs and markers.
j SOLIDIFICATION SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
2-3 TS
DEFINITIONS - (Cont'd) i STAGGERED TEST BASIS 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.
b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
(
UNRESTRICTED AREA 1
An UNRESTRICTED AREA shall be any area to which access is neither limited nor l
controlled by the licensee.
SURVEILIANCE FREOUENCY NOTAT191{
NOTATION FREOUENCY j
S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
i Q
At least once per 92 days.
j SA At least once per 6 months.
A At least once per 12 months.
R At least once per 18 months.
P Completed prior to ach use or release.
N.A.
Not applicable.
TS 2-4
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e 4.7 RADIOACTIVE EFFLUENTS j
4.7.1 RADIOACTIVE LIOUID EFFLUENTS i
l 4.7.1.1 INSTRUMENTATION f
r LIMITING CONDITION FOR OPERATION l
The following radioactive liquid effluent mor.itoring instrumentation channels l
shall be OPERABLE, with their alarm setpoints set to ensure that the limits of Specification 4.7.1.2 are not exceeded, Liquid Radwaste Effluent Line Monitor or Turbine Condenser Cooling a.
Vater Monitor, and b.
Liquid Radwaste Effluent Line Flow Meter.
e The alarm setpoints for these monitors vill be determined and adjusted using j
methodology in the Offsite Dose Calculation Manual (ODCM).
APPLICABILITY: At all times when releasing liquid radioactive effluents.
I ACTION:
I With the Liquid Radwaste Effluent Line Monitor or Turbine Condenser.
i a.
Cooling Water Monitor channel alarm /trippoint setpoint less conservative l
than that required by the above specification, immediately suspend the release or declare the channel inoperable or change the sotpoint so that
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it is acceptably conservative, With both channels not OPERABLE, or if both alarm setpoints are found to l
b.
be less conservative than required, suspend release of liquid radioactive effluent without delay. Effluent releases may be resumed with neither activity monitor OPERABLE, provided that at least two independent samples are analyzed and that at least two technically qualified members of the staff independently verify the release rate calculations. If channels are not operable for more than 30 continuous days, explain in the next Annual Effluent Report pursuant to l
Specification 6.8.1.
With the flow meter not OPERABLE, effluent releases via this pathway may c.
continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.
SURVEILIANCE REQUIREMENTS i
5.7.1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown on Table 5.7.1.1.
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TS 4/5-41 l
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RADIOACTIVE EFFLUENTS RADIOACTIVE LIOUID EFFLUENTS 4.7.1.2 CONCENTRATION LIMITING CONDITION FOR OPERATION I
The concentration of radioactive material released in liquid effluents at at;y time to areas beyond the EFFLUENT RELEASE BOUNDARY shall be limited to the l
concentrations specified in 10 CFR Part 20, Appendix B Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.
For l'
disgolved or entrained noble gases, the concentration shall be limiteo to 6 x 10 uci/ml total activity concentration.
APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released beyond the EFFLUENT RELEASE BOUNDARY exceeding the above limits, without delay restore concentration to within the above limits.
SURVEILLANCE REQUIREMENTS l-5.7.1.2 The radioactivity content of each batch of radioactive liquid waste l
to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 5.7.1.2.
The results of pre-release analyses shall be used in accordance with the ODCM methodology to assure that the concentration at the point of release is maintaine d within the limits of Specification 4.7.1.2.
TS 4/5-43
i RADIOACTIVE EFFLUENTS 4.7.2 RADIOACTIVE GASEOUS EFFLUENTS 4.7.2.1 INSTRUMENTATION 4
LIMITING CONDITION FOR OPERATION The radioactive gaseous effluent monitoring instrumentation channels shown in Table 4.7.2.1 shall be OPERABLE with their alarm and/or trip setpoints set to 1
ensure that the limits of Specification 4.7.2.2 are not exceeded. The stack-noble gas instrumentation alarm setpoint will be determined and adjusted in accordance with the methodology and parameters in the ODCM.
j 6.EElICABILITY: As shown in Table 4.7.2.1 ACTION:
l a.
With a radioactive gaseous effluent monitoring instrumentation channel alarm and/or trip setpoint less conservative than that required by the above specification, declare the channel inoperable or change the l
setpoint so that it is acceptably conservative.
l b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION required i
by Table 4.7.2.1.
Exert best efforts to return the instruments to l
OPERABLE status within 30 days, and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to 6.8.1, why the l;
inoperability was not corrected in a timely manner.
I SURVEILLANCE REQUIREMENTS i
5.7.2.1 Each radioactive gaseous effluent monitoring instrumentation channel j
shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 5.7.2.1.
TS 4/5-46 I
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RADIOACTIVE EFFLUENTS PADI0 ACTIVE GASEOUS EFFLUENTS 4.7.2.3 DOSE. NOBLE CASES 1
)
LIMITING CONDITION FOR OPERATION 1
The air dose to a MEMBER OF THE PUBLIC due to noble gases released in gaseous effluents to areas beyond EFFLUENT RELEASE BOUNDARY shall be limited to the following, (See Figure 1 of this section):
l During any calendar quarter, to $ 5 mrad for gamma radiation and a.
$ 10 mrad for beta particle radiation; and i
b.
During any calendar year, to s 10 mrad for gamma radiation and 5 20 mrad for beta particle radiation.
APPLICABILITY: At all times.
ACTION:
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions which have been taken or will be taken to reduce the releases of radioactive noble gases in baseous effluents so that the cumulative dose during each subsequent quarter is within 5 mrad for gamma radiation and 10 mrad for beta radiation, and during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation.
I SURVEILLANCE REQUIREMENTS 5.7.2.3 Dose Calculations: Cumulative dose contributions shall be i
determined in accordance with the ODCM at least quarterly.
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TS 4/5-51 l
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RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENTS 4.7.2.4 DOSE. RADIONUCLIDES OTHER TRAN NOBLE CASES i
LIMITING CONDITION FOR OPERATION The dose to a MEMBER OF THE PUBLIC from H-3, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released to areas beyond EFFLUENT RELEASE BOUNDARY shall be limited to the following (See Figure 1 of this section):
I 1
a.
During any calendar quarter to 5 7.5 mrem to any organ, and b.
During any calendar year to 5 15 mrem to any organ.
i AFPLICABILITY: At all times.
[
ACTION:
With the calculated dose from the release of H-3 and all radionucliden in particulats form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions which have been taken or will be taken to reduce these releases in gaseous effluents during remaining quarters so that the cumulative dose i
during each subsequent quarter is within 7.5 mrem and for the calendar year is within 15 mrem to any organ.
SURVEILIANCE REQUIREME! TIS i
5.7.2.4 Dose Calculations: Cumulative dose contributions shall be i
determined in accordance with the ODCM at least quarterly.
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TS 4/5-52 1
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RADIOACTIVE EFFLUENTS BASES - (Cont'd) 4/5.7.2.2 Instantaneous Dose Rate This specification is provided to ensure that the dose rate at any time at the EFFLUENT RE1 EASE BOUNDARY from gaseous effluents from IACBi4R will be withia the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, outside the EFFLUENT RELEASE BOUNDARY to annual average concentrations exceeding the limits specified in Appendix B. Table II of 10 CFR Part 20.
For individuals
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who may at times be within the EFFLUENT RELEASE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the EFFLUENT RELEASE BOUNDARY.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the i
EFFLUENT RELEASE BOUNDARY to 5 500 mrem / year to the total body or to 5 3000 l
mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding organ dose rate above background to an infant via the inhalation pathway to s 1500 mrem / year.
4/5.7.2.3 Dose. Noble Cases This specification is provided to implement the requirements of Sections i
II.B. III. A and IV. A of Appendix I,10 CFR Part 50.
The dose calculations in the ODCM implement the requirements in Section III. A of _ Appendix 1 that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.
4/5.7.2.4 Dose. Radionuclides Other Than Noble Cases l
This specification is provided to implement the requirements of Sections II.C, III. A IV. A and Annex of Appendix I,10 CFR Part 50.
The ODCM calculational methods specified in the surveillance requirements implement l
the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
4/5.7.3 SOLID RADIOACTIVE WASTE The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite. This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and applicable portions of 10 CFR Part 61.
TS 4/5-56
ADMINISTRATIVE CONTROLS - (Cont'd) i.
Reports and meeting minutes of the Operations Review Committee.
J.
Changes to the Contingency Plan and Plant Security Plan.
k.
Changes to the Emergency Plan.
1.
Changes to the Decommissioning Plan.
6.5.2.8 6MDITS Audits of facility activities shall be performed under the cognizance of the SRC. These audits shall encompass:
a.
The conformance of facility operation to provisions containcd within the Appendix "A" Technical Specifications and applicable license conditions at least once per 24 months.
b.
The performance, training and qualifications of the entire facility staff at least once per 24 months.
c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 12 months.
d.
The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B",
10 CFR 50, at least once per 24 months.
e.
The Emergency Plan and implementing procedures at least once per 12 months.
1 f.
The Contingency Plan, the Security Plan and implementing procedures, at least once per 12 months.
l g.
The Fire Protection Program and implementing procedures at least once per 24 months.
1 I
h.
An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 24 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
i.
The Radiological Environmental Monitoring Program and results at least once per 24 months.
j.
The Radiation Protection Program, including t.he Offsite Dose Calculation Manual and the Process Control Program and implementing procedures, at least once per 12 months.
k.
Any other area of facility operation considered appropriate by the SRC or the General Manager.
TS 6-7
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ADMINISTRATIVE CONTROLS - (Cont'd) 6.7 CONTROL OF MAINTENANCE AND TESTING ACTIVITIES 6.7.1 Maintenance operations and routine tests shall be performed in conformance with these specifications.
6.7.2 Maintenance operations shall be performed as authorized by the Shif t Supervisor. Maintenance involving the opening of systems containing radioactive materials shall be conducted under the surveillance of a Health Physics representative.
6.7.3 Co=ponents which have been repaired, replaced, or otherwise subjected to temporary or permanent modification shall be tested in accordance with procedures which are appropriate in view of the nature of the repair, replacement or modification, and in view of the condition of the system.
6.7.4 Key switches shall permit operational, maintenance, and test bypass of the safety instrumentation only with the approval of the Shift Supervisor.
l 6.8 REPORTING REOUIREMENTS 6.S.1 ROUTINE REPORTS 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.
6.8.1.1 Reports required on an annual basis shall be submitted by March 1 of each year and shall include:
a.
A tabulation on an annual basis of the number of station, utility j
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., plant operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), vaste processing, and fuel handling. The dose assignment to various duty functions may be I
estimates based on pocket dosimeter, TLD, or film badge measure-ments.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least
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80% of the total whole body dose received from external sources shall be assigned to specific major work functions. This tabulation is per the requirements of Regulatory Guide 1.16 Revision 4, August, 1975.
b.
A report containing a brief description of any changes, testing and experiments conducted under the criteria of 10 CFR 50.59, including a summary of the safety evaluations of them.
TS 6-10
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ADMINISTRATIVE CONTROLS - (Cont'd) l 6.8.3.2 Each REPORTABLE EVENT shall be reviewed by the ORC and the Licensee l
Event Report shall be submitted to the SRC and General Manger 6.8.3.3 The followin5 types of events are REPORTABLE EVENTS:
[
i Any violetion of or condition prohibited by Technical-l a.
Specifications.
i b.
Any deviation from Technical Specifications authorized by i
l t
Serious degradation of nuclear fuel.
c.
I d.
Loss of CONTAINMENT INTEGRITY when it is required to exist.
Any event or condition that resulted in the plant being in an l
e.
unanalyzed condition that significantly compromised plant safety.
?
f.
Any event or condition that resulted in the plant being in a.
l condition outside its design basis.
j i
g.
Any event or condition that resulted in the plant being in a
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condition not covered by normal or emergency procedures.
h.
Any natural phenomenon, other external phenomenon, or event such as l
fire, toxic gas release, or radioactive release, that. posed an i
actual threat to plant safety or'significantly hampered site l
personnel in the performance of duties necessary for plant safety, j
i.
Any event or condition that resulted in unplanned and unexpected manual or automatic actuation of the Emergency Diesel Generators or Containment Isolation.
J.
Any airborne radioactivity release that exceeded 2 times the applicable concentrations of the limits specified in Appendix B, Table II of 10 CFR Part 20 in unrestricted areas, when averaged over a time period of one hour.
k.
Any liquid effluent release that exceeded 2 times the limiting-combined effluent concentrations in Appendix B, Table II, of 10 CFR l
Part 20, at the point of entry into the receiving water (i.e.,
l EFFLUENT RELEASE BOUNDARY) for all radionuclides except tritium and I
dissolved noble gases, when averaged-over a time period of'one hour.
TS 6-12 l
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ADMINISTRATIVE CONTROLS - (Cont'd) f.
Records of training and qualification for current members of the facility staff.
g.
Records of in-service inspections performed pursuant to these Technical Specifications, h.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
t i.
Records of meetings of the ORC and the SRC.
6.10 RADIATION PROTECTION PROGRAM 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.
6.11 HIGH RADIATION ARE6 l
l 6.11.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each high radiation area in which the l
intensity of radiation, at 30 cm from the radiation source or surface that the radiation penetrates, is greater than 100 mrem /hr but less than 1000 i
mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Special Work Permit (SWP).* Any individual or group of individuals permitted to enter such areas shall be provided with one or more of the following:
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a A radiation monitoring device which continuously indicates the i
a.
radiation dose rate in the area.
i 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 levels in the area have been established and personnel have been made knowledgeable of them.
l t
c.
A health physics qualified individual (i.e., qualified in radiation i
protection procedures) with a radiation dose rate monitoring device and who is responsible for providing positive exposure control over the activities within the area and who will perform periodic radiation surveillance at the frequency which will be established by the Health and Safety Supervisor or applicable SWP.
l i
Health Physics personnel or personnel escorted by Health Physics i
personnel shall be exempt from the SWP issuance requirement during the performance of their assigned radiation protection duties, provided they are following plant radiation protection procedures for entry into high radiation
- areas, i
i TS 6-14
ADMI,NISTRATIVE CONTROLS - (Cont'd) 6.11.2 For each area with radiation levels greater than 1000 mrem /hr at 30 cm (but less than 500 Rad /hr at 1 meter) from radiation source, or from any surface penetrated by the radiation, the control of Specification 6.11.1 shall be implemented, and also (1) Each entrance or access point to the area shall be maintained locked except during periods when access to the area is required.
Positive control over each individual entry shall be by:
[
a.
Maintaining the locked door keys under administrative control of the Shift Supervisor on duty or the Health and Safety Supervisor.
b.
An approved SWP that specifies the dose rates in the immediate work areas and the maximum allowable stay time for individuals in that area, t
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i TS 6-15 I
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