ML20024J349
| ML20024J349 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 10/05/1994 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | NRC |
| References | |
| NUDOCS 9410140105 | |
| Download: ML20024J349 (1) | |
Text
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l-8 k,
D DA/RYLAND h!
[k COOPERAT/VE LA CROSSE BOILING WATER REACTOR (LACBWR) e ROUTE 1, BOX 275.
GENOA. WISCONSIN 54632 e (608) 689-2331 TO:
AMC dadv.
CONTROLLED DISTRIBUTION NO. 5 !
FROM:
LACBWR Plant Manager October 5,1994 i
SUBJECT:
Chances to LACBWR Controlline Documents I.
The following documents have been revised or issued new.
TECHNICAL SPECIFICATIONS Amendment No! 68 to Possession-Only License No. DPR-45 for the La Crosse Boiling Water Reactor, dated September 27,1994, in response to DPC's application of November 5,1993, as supplemented by letter of August 3,1994.
This amendment revises the LACBWR TS in accordance with the requirements of revised 10 CFR Part 20. Also included are several minor editorial changes.
Instructions An instruction sheet is included for the revised TS pages.
The description of Amendment No. 68 may be filed in the front of your binder.
The Safety Evaluation may be placed at the back of your binder.
O The material listed above is transmitted herewith. Please verify receipt of all listed material, destroy superseded material, and sign below to acknowledge receipt.
O The material listed above has been placri in your binder.
O Please review listed material, notify your personnel of changes, and sign below to acknowledge your review and notification of personnel. [To be checked for supervisors for department specific procedures and LACBWR Technical Specifications.]
O The material listed above has been changed. [To be checked for supervisors when materials applicable to other departments are issued to them.]
/S/
DATE Please return this notification to the LACBWR Secretary within ten (10) working days.
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g, 9410140105 941005 PDR ADOCK 05000409
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PDR DAIRYLAND POWER COOPERATIVE ADMINISTRATION BUILDING
- P. O. BOX 817
- LA CROSSE, WISCONSIN 54601 * (608) 788-4000
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 68 TO POSSESSION-ONLY LICENSE NO. OPR-45 DOCKET NO. 50-409 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 2-2 2-2 2-3 2-3 2-4 2-4 4/5-41 4/5-41 4/5-43 4/5-43 4/5-46 4/5-46 4/5-51 4/5-51 4/5-52 4/5-52 4/5-56 4/5-56 6-7 6-7 6-10 6-10 6-12 6-12 6-14 6-14 6-15 6-15
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The Technical Specifications contained in Appendix A as revised through Amendment No. 68, are hereby incorporated in the license.
Dairyland Power Cooperative shall maintain the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION put4h John H. Austin, Chief low-level Waste and Decommissioning Projects Branch Division of Waste Management Office of Nuclear Materials Safety and Safeguards
Attachment:
Changes to the Technical Specifications k)
Date of Issuance: September 27, 1994 Iv t-
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_4j NUCLEAR REGULATORY UNITED t
STATES
.....,o WASHINGTON. O C COMMISSION
. 20555 0001 DAIRYLAND POWER COOPERATIVE DOCKET N0 50-409 (A CROSSE BOILING WAT AMENDMENT TO POSSESSI ER REACTOR ON-0NL Y LICENSE 1
The Nuclear Regulat ory Commission (the C Amendment No. 68 A.
The August 3 dated Noverber 5 amendment by Dairy appl ISensee)ication for
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requireme,nts1994, (LAC-13420) that:
,1993, (LAC-13320), asPower Cooperative (t Act, and of Chap)ter I; the Commission'sthe Atomic Energy A
, complies with the standardssupplemented e
ct of 1954 B.
regulations The facility will and as set for,th in 10 CFR(the amended application be amended, themaintained in regulat ions,ofas There is the Commission;provisionsconformity with C.
of the by this reasonable the Act, and and safety ofamendment can beassurance:
(i) that the conducted in the public conducted without endand (ii) t activities The issuance compliance w,ith the C D.
c ivities wangering the healthauthorized defense ommission's of this The issuanceand security or to the hamendment will not be i regulations;ill be G.
requirements have beenthe Commission'samendm Part 51 of of this nimical to the commo SpecificationsAccordingly, the li sa t is fied.regulationsaccordance e public; n with 10 CFR cense is and all applicable and paragraph 2.C. 2) of Pas indicated in theamended by changes to amended read as (follows:ossession-Only Li to attachmentto thithe Technical cense No. s license DPR-45 amendment is hereby
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i UNITED STATES 4
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2055 5 0001 O
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l OAIRYLAND POWER COOPERATIVE j
DOCKET NO. 50-409 LA CROSSE BOILING WATER REACTOR AMENDMENT TO POSSESSION-0NLY LICENSE Amendment No. 68 License No. DPR-45 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dairyland Power Cooperative (the 1 %ensee) dated Noverber 5, 1993, (LAC-13320), as supplemented August 3, 1994, (LAC-13420), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the-Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will be maintained in conformity with the l
application, as amended, the provisions of the Act, and I
regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; l
G.
The issuance of this amendment is in accordance with 10 CFR l
Part 51 of the Commission's regulations and all applicable i
requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Possession-Only License No. DPR-45 is hereby amended to read as follows:
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(s DEFINITIONS - (Cont'd)
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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 ARFA A CONTROLLED AREA shall be any area outside of the RESTRICTED AREA, but within the EXCLUSION AREA, access to which can bc limited by Dairyland Power Cooperative for any reason.
EFFLUENT RELEASE BOUNDAR,,1 The Dairyland Power Cooperative property line within the 1109 ft. (338m) radius EXCWSION AREA is the EFFLUENT RELEASE BOUNDARY.
(See Figure 1, Sec. 4.)
EXCLUSION AREA
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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 Surveillance Requirements shall correspond to the intervals defined in Table of Surveillance Frequency Notation.
FUEL HANDLINC FUEL 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 O!WR OF THE PUBLIC shall mean an individual in a CONTROLLED or UNRESTRICTED AKEA.
Nwever, an individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose.
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TS 2-2 Amendment No. 68
DEFINITIONS - (Cont'd)
O OFFSITE DOSE CAlfU1ATION. MANUAL (ODCM)
An OFFSITE DOSE CALCULATION MANUAL (ODCM) shall be a manual containing the methodology and parameters to be used for the calculation of offsite doses due to radioactive gaseous and liquid effluents and for the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints.
It shall describe the radiological environmental monitoring program.
l OPERABLE-OPERABILITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and i
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, l
component or device to perform its function (s) are also capable of performing their related support function (s).
l PROCESS CONTROL PROGRAM (PCP)
The PROCESS CONTR01. 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 g~
assure compliance with 10 CFR Part 20,10 CFR Part 61 and Federal and State I
regulations and other requirements governing the transportation and disposal of the radioactive waste.
REPORTABLE EVENT A REPORTABII EVENT shall be any of those conditions specified in Section 6.8.3.
A Licensee Event Report shall be submitted for REPORTABLE EVENTS.
RESTRICTED AREA l
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 in accordance with 10 Cnt 20.1901 and 20.1902. These RESTRICTED AREAS shall 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.
SOLIDIFICATION j
SOLIDIFICATION shall be the conversion of wet vastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK I
A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
TS 2-3 Amendment No. 68
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DEFINITIONS - (Cont'd)
STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of:
A test schedule for n systems, subsystems, trains or other f
a.
l designated components obtained by dividing the specified test I
interval into n equal subintervals.
l b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
i UNRESTRICTED AREA l
An UNRESTRICTED AREA shall be any area to which access is neither limited nor controlled by the licensee.
SURVEIIIANCE FREOUENCY NOTATION EQIATION FREOUENCY A)
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 />, i,
i At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D l
U At least once per 7 days.
M At least once per 31 days.
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Q At least once per 92 days.
I SA At least once per 6 months.
A At least once per 12 months.
R At least once per 18 months.
1 P
Completed prior to each use or release.
I N.A.
Not applicable.
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G TS 2-4 Amendment No. 68
i 4.7 RADIOACTIVE EFFLUENTS f3 (s,)
4.7.1 RADIOACTIVE LIOUID EFFLUENIS 1
4.7.1.1 INSTRUMENTATION LIMITING CONDITION FOR OPERATION r
The following radioactive liquid effluent monitoring instrumentation channels shall be OPERABLE, with their alarm setpoints set to ensure that the limits of Specification 4.7.1.2 are not exceeded.
a.
Liquid Radwaste Effluent Line Monitor or Turbine Condenser Cooling Vater Monitor, and b.
Liquid Radwaste Effluent Line Flow Meter.
The alarm setpoints for these monitors will be determined and adjusted using methodology in the Offsite Dose Calculation Manual (ODCM).
APPLICABILITY: At all times when releasing liquid radioactive effluents.
ACTION:
a.
With the Liquid Radwaste Effluent Line Monitor or Turbine Condenser
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Cooling Water Monitor channel alarm /trippoint setpoint less conservative
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than that required by the above specification, immediately suspend the release or declare the channel inoperable or change the setpoint so that it is acceptably conservative.
b.
With both channels not OPERABLE, or if both alarm setpoints are found to 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 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.
SURVEILLANCE REQUIREMENTS 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 CALIBPATION operations at the
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frequencies shown on Table 5.7.1.1.
TS 4/5-41 Amendment No. 68 L
4 RADIOACTIVE EFFLUENTS RADIOACTIVE LIOUID EFFIEENTS 4.7.1.2 CONCENTRATION s
LIMITINC CONDITION FOR OPERATION s
The concentration of radioactive material released in liquid effluents at any time to areas beyond the EFFLUENT RELEASE BOUNDARY shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table '2, Column 2, for radionuclides other than dissolved or entrained noble gases. For disgolved or entrained noble gases, the concentration shall be limited to 6 x 10~
uci/ml total activity concentration.
APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released beyond the EFFIDENT RELEASE BOUNDARY exceeding the above limits, without delay restore concentration to within the above limits.
SURVEILIANCE REQUIREMENTS l
5.7.1.2 The radioactivity content of each batch of radioactive liquid waste 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 maintained within the limits of Specification 4.7.1.2.
O TS 4/5 43 Amendment No. 68
p(j RADIOACTIVE EFFLUENTS 4.7.2 RADIOACTIVE CASEOUS EFFLUENTS 4.7.2.1 INSTRUMENTATION 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 The stack ensure that the limits of Specification 4.7.2.2 are not exceeded.
noble gas instrumentation alarm setpoint will be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY: As shown in Table 4.7.2.1 ACTION:
With a *adioactive gaseous. effluent monitoring instrumentation channel l
a.
alarm and/or trip setpoint less conservative than that required by the j
above specification, declare the channel inoperable or change the setpoint so that it is acceptably conservative.
O b.
With less than the minimum number of radioactive gaseous effluent
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monitoring instrumentation channels OPERABLE, take the ACTION required I
by Table 4.7.2.1.
Exert best efforts to return the instruments to OPERABLE status within 30 days, and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report, pursuant to 6.8.1, why the inoperability was not corrected in a timely manner.
SURVEILIANCE REQUIREMENTS i
l 5.7.2.1 Each radioactive gaseous 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 in Table 5.7.2.1.
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TS 4/5-46 Amendment No. 68
RADIOACTIVE EFFLUENTS RADIOACTIVE CASEOUS EFFLUENTS 4.7.2.3 DOSE. NOBLE GASEE y
LIMITING CONDITION FOR OPERATION 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);
During any calendar quarter, to $ 5 mrad for gamma radiation and a.
5 10 stad for beta particle radiation; and b.
During any calendar year, to $ 10 mrad for gamma radiation and f 20 mrad for beta particle radiation.
APPLICABILITY: At all times.
ACTION:
With the calculated air dose from radioactive noble gases in gaseous
'N 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 gaseous 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.
SURVEILIANCE REQUIREMENTS 5.7.2.3 Dose Calculations: Cumulative dose contributions shall be determined in accordance with the ODCM at least quarterly.
l TS 4/5-51 Amendment No. 68 m
RADIOACTIVE EFFLUENTS RADIOACTIVE CASEOUS EFFLUENTS
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4.7.2.4 DOSE. RADIONUCLIDES OTHER THAN NOBLE CASES
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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):
During any calendar quarter to S 7.5 area to any organ, and a.
b.
During any calendar year to 515 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
With the calculated dose from the relea.se of H-3 and all radionuclides in particulate 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 during each subsequent quarter is within 7.5 arem and for the calendar year -
is within 15 mrem to any organ.
SURVEILIANCE REQUIREMENTS 5.7.2.4 Do's'e Calculations: Cumulative dose contributions shall be determined in accordance with the ODCM at least quarterly.
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O Amendment No. 68 TS 4/5-52 c.
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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 RELEASE BOUNDARY from gaseous effluents from LACBWR will be The within the annual dose limits of 10 CFR Pact 20 for unrestricted areas.
annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B Table 2, Column 1.
These limits provide reasonable l
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 2 of 10 CFR Part 20.
For individuals j
I who may at times be within the EFFLUENT RELEASE BOUNDARY, the occupancy of the individual will be sufficiently lov to compensate for any increase in the atmospheric diffusion factor above that for the EFFLUENT RELEASE EOUNDARY.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individaal at or beyond the EFFLUENT RELEASE BOUNDARY to 5 500 mrem / year to the total body or to 5 3000 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.
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4/5.7.2.3 Dose. Noble Cases This specification is provided to implement the requirements of Sections II.B, III. A. and IV. A of Appendix I,10 CFR Part 50.
The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I 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. Radionuelides Other Than Noble Cases 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 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 VASTE 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
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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 Amendment No. 68
ADMINISTRATIVE CONTROLS - (Cont'd)
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1 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 1.
Changes to the Decommissioning Plan.
6.5.2.8 AUDITS Audits of facility activities shall be performed under the cognizance of the SRC.
These audits shall encompass:
The conformance of facility operation to provisions contained a.
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.
The results of actions taken to correct deficiencies occurring in c.
facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 12 months.
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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.
The Emergency Plan and implementing procedures at least once per e.
12 months.
f.
The Contingency Plan, the Security Plan and implementing procedures, at letst once per 12 months.
g.
The Fire Protection Program and implementing procedures at least once per 24 months.
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 the Offsite Dose Calculation Manual and the Process Control Program and implementing procedures, at least once per 12 months.
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k.
Any other area of facility operation considered appropriate by the i
SRC or the General Manager.
TS 67 Amendment No. 68 l
ADMINISTRATIVE CONTROLS - (Cont'd) i
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6.7 CONTPOL OF MAINTENANCE ANP 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 Components 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.
6.8 REPORTING REOUIREMENTS 6.8.1 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.
U 6.8.1.1 Reports required on an annual basis shall be submitted by March 1 of each year and shall include:
A tabulation on an annual basis of the number of station, utility a.
end 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), waste processing, and fuel handling. The dose assignment to various duty functions may be 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 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.
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i TS 6-10 Amendment No. 68 L.
4 ADMINISTRATIVE CONTROLS - (Cont'd)
O 6.8.3.2 Each REPORTABLE EVENT shall be reviewed by the ORC and the Licensee j
Event Report shall be submitted to the SRC and Ceneral Manger, 6.8.3.3 The following types of events are REPORTABLE EVENTS:
Any violation of or condition prohibited by Technical a.
Specifications.
Any deviation from Technical Specifications authorized by b.
Serious degradation of nuclear fuel.
c.
d.
Loss of CONTAINMENT INTECRITY when it is required to exist.
Any event or condition that resulted in the plant being in an 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, Any event or condition that resulted in the plant being in a g.
condition not covered by normai or emergency procedures.
f ['
h.
Any natural phenomenon, other external phenomenon, or event such as
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fire, toxic gas release, or radioactive release, that posed an actual threat to plant safety or significantly hampered site personnel in the performance of duties necessary for plant safety.
i.
Any event or condition that resulted in unplanned and unexpected manual or automatic actuation of the Emergency Diesel Generators or Containment Isolation.
I J.
Any airborne radioactivity release that exceeded 2 times the i
applicable concentrations of the limits specified in Appendix B, Table 2 of 10 CFR Part 20 in unrestricted areas, when averaged l
over a time period of one hour.
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k.
Any liquid effluent release that exceeded 2 times the limiting f
combined effluent concentrations in Appendix B. Table 2, o f 10 CFR Part 20, at the point of entry into the receiving water (i.e.,
EFFLUENT RELEASE BOUNDARY) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one i
hour.
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TS 6-12 Amendment No. 68
I ADMINISTRATIVE CONTROLS - (Cont'd) f.
Records of training and qualification for current members of the facility staff, Records of in-service inspections performed pursuant to these g.
Technical Specifications.
j l
h.
Records of reviews performed for changes made to procedures or l
equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
1.
Records of meetings of the ORC and the SRC.
l 6.10 MDIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent j
with the requirements of 10 CFR Part 20 and shall be approved, maintained and l
adbered to for all operations involving personnel radiation exposure.
6.11 HIGH RADIATION AREA 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 intensity of radiation, at 30 cm from the radiation source or surface that the radiation penetrates, i.: greater than 100 mrem /hr but less than 1000
(
mrem /hr shall be barricaded and conspicuously posted as a high radiation area
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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:
A radiation monitoring device which continuously indicates the a.
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 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, A health physics qualified individual (i.e., qualified in radiation c.
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 Health Physics personnel or personnel escorted by Health Physics 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 j
areas.
U i
TS 6-14 Amendment No. 68
ADMINISTRATIVE CONTROLS - (Cont'd) l' 6.11.2 For each area with radiation levels greater than 1000 mrem /hr at l
30 cm (but less than 500 Rad /hr at 1 meter) from radiation source, or from j
any surface penetrated by the radiation, the control of Specification 6.11.1 j
l shall be implemented, and also I
j (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:
-l Maintaining the locked door keys under administrative control a.
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 l
in that area.
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U TS 6-15 Amendment No. 68
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t UNITED STATES 0
S NUCLEAR REGULATORY COMMISSION
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2E WASHINGTON, D.C. 20555-.0001
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i September 27, 1994 l
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS RELATED TO AMENDMENT N0. 68 TO POSSESSION-0NLY LICENSE NO. DPR-45 j
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR DOCKET NO. 50-409 l
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1.0 INTRODUCTION
By letter of November 5,1993 (LAC-13320), as supplemented by letter dated l
August 3,1994, (LAC-13420), Dairyland Power Cooperative (the licensee) submitted a request for changes to the La Crosse Boiling Water Reactor (LACBWR), Technical Specifications (TS) appended to Possession-Only License No. DPR-45. The proposed amendment is required in order that the licensee be in compliance with the recent revision to 10 CFR Part 20 (56 FR 23360).
In addition, some editorial changes to correct oversights from previously approved amendments are required. The August 3,1994, supporting material did p/
not alter the previous determination of no significant hazards considerations.
s, 2.0 fvaluation The licensee has revised the TS to modify references in order to be consistent with the revised 10 CFR Part 20, Standards for Protection Aaainst Radiation, and will retain the same overall level of effluent control required to meet the design objectives of Appendix I to 10 CFR Part 50.
The proposed TS changes and evaluations follow:
1.
lhe licensee proposes to revise several definitions in TS Section 2 in accordance with those provided in 10 CFR 20.1003. The list of definitions consists of controlled area, member of the public, restricted area, and unrestricted area.
The changes are administrative in nature to incorporate the corresponding new 10 CFR Part 20 definitions and are acceptable.
2.
The licensee proposes to provide a proper reference to a table in 10 CFR Part 20 Appendix B in accordance with the above mentioned revision of 10 CFR Part 20.
The change is administrative in nature to incorporate the proper reference to the revision of 10 CFR Part 20.
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3.
The' licensee proposes to delete several references to 10 CFR Part 20 that are no longer applicable. The deleted references consisted of the issuance date of the former Part 20,10 CFR 20.106(b), and Maximum Permissible Concentration as mentioned.in Note 1 of Appendix B to 10 CFR Part 20.
The changes are administrative to delete outdated Part 20 l
references in accordance with new 10 CFR Part 20 and are
. acceptable.
4.
The licensee proposes to revise TS 6.5.2.8, Audits, item j, Radiation Protection Program, to indicate an audit once per twelve i
months in accordance with 10 CFR 20.1101(c).
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This change is administrative in nature to incorporate the corresponding revised 10 CFF Part 20 audit frequency and is acceptable.
5.
The li:ensee proposes to.ielete the referenc: to 10 CFR 20.407 and incorporate the reference to Regulatory Guide ~ (RG) 1.16.
The specific deleted reference,"This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20," is located in Section 6.8.1, wherein there is the statement, "In addition to the l C applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted...";
therefore, no reporting requirements were deleted, but the applicable RG was incorporated.
This change is administrative in nature to remove a reference to 10 CFR Part 20 and to incorporate the appropriate RG and is acceptable.
6.
The licensee proposes to revise Section 6.11, HIGH RADIATION AREA,-
in accordance with the new 10 CFR Part 20, Subpart G, " Control of Exposure From External Sources in Restricted Areas."
This change is administrative in nature in order to incorporate requirements in the new 10 CFR Part 20 and is acceptable.
7.
The licensee proposes several editorial changes to correct erroneous TS references and references to a Semi-Annual Effluent Report that has been changed to an Annual Report in a previous license amendment.
These changes are administrative in nature and are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Wisconsin State official was notified of the proposed issuance of the amendment. The State official had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that tne amendment involves no significant hazards considera-tion, and there has been no public comment on such finding (59 FR 618).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(2) and (9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commission's regulations; and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Stephen Koenick NMSS\\DWM\\LLDP Date: September 27, 1994 O