ML19331D580
| ML19331D580 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/06/1980 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML19331D579 | List: |
| References | |
| NUDOCS 8009030243 | |
| Download: ML19331D580 (21) | |
Text
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O SECTION 6.0 ADMINISTRATIVE CONTROLS
- ~... - _
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2.1-1.
UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
e.
All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senier Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A Fire Brigade of at least 5 members shall be mafntained on site at all times." The Fire Brigade shall not include the two LACBWR Plant Operators necessary for safe shutdown of the unit or any other personnel required for other essential functions during a fire emergency.
" Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of Fire Brigade men:eers provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.
LAC 9NR 6-1
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Fiqure 6.2.1-1 OITSITE ORGANIZATION
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OPERATIONS SUPERVISOR /
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FIGURE 6.2.2-1 IAE Supervisor positions FACILITY ORGANIZATION
.. Responsible for Fire Protection Program
l TABLE 6.2.2-1 MINIMUM SHIFT CREW CCMPOSITIONW
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LICENSE APPLICABLE OPERATIONAL C_0NOITIONS CATEGORY
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- Does not include the licensed Senior Reactor Operatar or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.
- Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommoda'.e unexpected absence of on duty shift crew members provided immediate action is taken to restore the sr.t crew composition to within the minimum requirements of Table 6.. 2-1.
i LACBWR 6-4 r
ADMI';IST,RATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS F.3.1 Each member of the unit staff shall meet or exceed tne minimum qualifi-cations of ANSI N18.1-1971 for comparable positions, except for the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigades shall be maintained under the direction of the Operations Engineer and shall meet the requirements of Section 27 of the NFPA Code-1975, except for the frequency of Fire Brigade training sessions, which shall be held at least once per 92 days.
6.5 REVIEW AND AUDIT 6.5.1 OPERATIONS REVIEW COMMITTEE (0RC)
FUNCTION 6.5.1 The Operations Review Committee shall function to advise the Plant Superintendent on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Operations Review Car.mittee shall be composed of the:
Chairman:
Plant Superintendent Members; Operations Supervisor Mechanical Maintenance Supervisor Instrument and Electrical Supervisor Health and Safety Supervisor Assistant Superintendent Staff Engineers Shift Supervisors Training & Relief Supervisor ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the ORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in ORC activities at any one time.
LACBWR 6-5
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ADMINISTRATIVE CONTROLS MEETI M FREQUENCY 6.5.1.4 The ORC shall reet at least once per calendar month and as convened by the CRC Chairmn or his designated alternate.
QUORtM 6.5.1.5 The mininus quor m of the ORC necessary for the perfomance of the ORC responsibiilty and authority provisions of the Technical Specifications shall consist of the Chaiman, or his designated alternate, and four members, including a~sternates.
RESPONSIBILIYiES 6.5.1.6 The Operations Review Ccecittee shall be responsible for:
a.
Review of (1) all procedures recuired by specification 6.8 and changes thereto, (2) any cther procesed procedures or changes thereto as detemined by the Plant Superintendent to affect nuclear safety.
b.
Review of all proposed tests and experirants that affect nuclear sa fety.
c.
Review of all proposed changes to the /cpendix "A" Technical Specifi-cations.
d.
Review of all proposed changes or rodifications to unit systems or equip ent that affect nuclear safety.
e.
Investigation of all violations of the Technical SpePications including the preparation and forwarding of reports.A ertag evaluation and recomendations to prevent recurrence to the Assistanct General Manager-Power Group and to the Safety Review Comittee (SRC).
f.
Review of events requiring 24-hour written notification to the Ccmission.
9 Review of unit operations to detect potential nuclear safety h&Zards.
h.
Perforeance of special reviews, investigations or ardlyses and eports thereon as requested by the Plant Superintendent u SRC.
- i. Review of the Plant Security Plan and irplementing procedures ar.d shall submit recomended changes to the SRC.
j.
Review of the E, nerd
>v Pin and i=plenenting procedures and shall submit rectrnmended, s. A to the SRC.
k.
Review of the Facil'ty Fire Protection Program and irclenenting procedures at least once per Et conthc.
i 1.
Ensuring that an independent fire protection and loss prevention progran inspection and audit be perfor:ned at least once per 12 conths utilizing either qualified offsite licensee personnel or an outside fire protection fim.
l Ensuring that an inspection and audit of the fire protection and loss n.
preventien prograe be perfomed by a qualified outside fire consultant at least once per 36 onths.
LAts'a 6-6
ADMINISTRATIVE CONTROLS,,
AUTHORITY'
- 6. 5.1. 7 The Operations Review Committee shall:
a.
Recommend in writing to the Plant Superintendent approval or dis-approval of !tems considered under 6.5.1.6a through d above.
b.
Render determinations is writing with regard to whether or not E3ch item considered under 6.5.1.6a through e above constitutes an unreviewed safety question.
c.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Assistant General Manager-Power Group and the SRC of disagreement between the ORC and the Plant Supe-intendent; however, the Plant Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECOROS 6.5.1.8 The Operations Review Committee shall maintain written minutes of each CRC meating that, at a minimum, document the results of all ORC activities performed under the responsibility and authority provisions of these Tec.inical Specifications. Copies shall be provided to the Assistant General Mariager-Power Group and the SRC.
6.5.2 SAFETY REVIEW COMMITTEE (SRC)
FUNCTION 6.5.2.1 The SAFETY REVIEW COMMITTEE shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, d.
Metallurgy, e.
Instrumentation and control, f.
Radiological safety, g.
Mechanical and electrical engineering, and h.
Quality assurance practices.
LACBWR 6-7
i ADMINISTRATIVE CONTROLS COMP 051YION
- 6. 5. 2. 2 The SRC sha411 be composed of the:
Chairman:
Consultant Members:
Consultant Plant Superintendent Dairyland Power Cooperative (OPC) Environmental Department Manager Assistant General Manager-Power Group ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; hcwever, no more than two alternates shall participate as voting members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by tr.a SRC Chairman to provide expert advice to the SRC.
~
MEETING FREQUENCY 6.5.2.5 The SRC shall meet at least once per six months.
,UORUM 6.5.2.6 The ninimum quorum of the SRC necessary for the performance of the SRC review and audit functions of these Techr.ical Specifications shall consist of the Chairman, or his designated alter, ate, and at least 3 SRC members, including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW
- 6. 5. 2. 7 The Safety Review Committee shall review:
a.
The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or exoeriments completed under the provisions of Section 50.59, 10 CFR, o verify that such &_tions did not consti-tute an unreviewed safet> question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined fr Section 50.59, 10 CFR.
LACBWR 6-8
ADMINISTRATIVE CONTRO*.S REVIEW (Continued) c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Preposed changes to Appendix "A" Technical Specifications or this Operating License.
e.
Violations of codes, regulations, orders, Technical Snecifications, license requirements, or of internal procecures or instructions having nuclear safety significance..
f.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
g.
Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to tre Ccamission.
h.
All recognized indications of an unanticipated ceficiency in some aspect of design or cceration of safety related structures, syste:s, or components that could affect nuclear safety.
i.
Reports and reeting minutes of the Operations Review Committee.
AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cogni:ance of the SRC. These audits shall encompass:
a.
The conformance of unit operation to provisions contained within the Appendix "A" Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire unit staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the Operational 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 24 months.
LACBkR 6-9
~
AOMINISTRATIVE CONTROLS AUDITS (Centinued) f.
The Security Plan and isolementing procecures at least once per 24 months.
g.
The Fire Protection Prcgram anc implementing prececures at least once per 24 aonths.
h.
An indepencent fire protection and loss preventien regram inspecticn and aucit shall be perforsec at least once per 12 sentns utilizing either qualified offsite licensee perscr.nel or an cutsice fire protection firm.
1.
An inspection and audit of the fire protection and loss crevention program shall be performed by a qualified cutsice fire censultant at least once per 36 months.
j.
Any other area of unit operation censidered a:prepriate by the SRC or the CPC General Manager.
AUTHORITY 6.5.2.9 The SRC shall report to and acvise the CPC General Manager en those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.3.
RECORDS 6.5.2.10 Records of SRC activities shall te prepared, ap; roved and distributed as indicated celow:
a.
Minutes of each SRC meeting shall be prepared, a:: roved and forwarded to the OPC General Manager within 20 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the CPC General Manager within 20 days following completion of the review.
c.
Audit reports encompassed by Section 6.5.2.8 above, shall be fe<<arcec to the CPC General Manager and to the sanagement positions resp. sicle for the areas audited within 30 days after ccepletion of the auc LAC 3hR 6-10
l ADMINISTRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
b.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the ORC and submitted to the SRC and the Assistant General Manager-Power Group.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violatad:
a.
The unit shall be placed in at least HOT SHUT 00WN within two hours.
b.
The Safety Limit violation shall be reported to the Commission, the Assistant General Manager-P6wer Group and to the SRC within 24
- hours, c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the ORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the SRC and the Assistant General Manager-Power Group within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures reccamended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
LACEWR 6-11
ADMINISTRATIVE CONTROLS PROCEDURES'(Continu3d) d.
Security Plan implementition.
e.
Emergency Plan implementation.
6.8.2 Each procedure of 6.8.1 above, and enanges thereto, shall be reviewed by the ORC and approved by the Plant Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the ORC and approved by the Plant Superintendent within 14 days of implementation.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement, unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amencment 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 unit.
LAC 8WR 6-12 l
ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued)
- 6. 9.1. 2 The report shall address each of the tests identified in the Safeguards Report for Operating Authorization as required for the test program being conducted and shall 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 der.ign predictions and specifications.
Any corrective actions that wera required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of comercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events, i.e., initial criticality, completion of startup test program, and resumption or commencement of comercial power operation, supplementary reports shall be submitted at 'e0st every three months until all three events have been completed.
ANNUAL OPERATING RiPORT 1/
6.9.1.4 Annual reports covering the operation of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station, utility and other personnel, including contractors, receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,2_/ 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 estimates based on pocket dosimeter, TLD, or film badge measurements. 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 sour.es shall be assigned to specific major.. work functions.
1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
2/ This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20.
LACBWR 6-13 j
i
ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analy3is, U.S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, with a copy to the Regional Office of Inspection and Enforcement, to arrive no later than the 15th of each month following the cajendar month covered by the report.
REf0RTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.E and 6.9.1.9 below, including corrective acticas and measures to prevent recurrence, shall be reported to the NRC.
Supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 The types of events listed below shall be reportad within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within two weeks.
The written followup report shall incl;de, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
a.
Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.
b.
Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.
c.
Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
LACSWR 6-14 l
1 ACMINISTRATIVE CONTROLS PROMPT NOTIFICATICN WITH WRITTEN FOLLOWUP (Continued) d.
Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steacy state conditions during power operation greater than or equal to 1% delta k/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than C.5%
delta k/k; or occurrence of any unplanned criticality.
e.
Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional require-ments of system (s) used to cope with accidents analyzed in the Safeguards Report for Operating Authorization.
f.
Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accicents analyzed in the Safeguards Report for Operating Authorization.
g.
Conditions arising froz natural or man-made events that, as a direct result of the event require plant shutcown, operation of safety systems, or other p:otective measures required by technical specifi-cations.
h.
" Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
i.
Performance of structures, systems, or components that requires remedial action or corrective measures to prevent.peration in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the exist-ence or development of an unsafe condition.
THIRTY OAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circur' stances surrounding the event.
LACSkR 6-15
I ADMINISTRATIVE CONTROLS THIRTY DAY WRITTEN REPORTS (Continued) a.
Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
b.
Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
c.
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems, d.
Abnormal degradation of systems cther than those sr.ecified in 6.9.1.8.c above designed to contain radioactive material resulting from the fission process.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.
a.
Containment Testing, Specification 5.2.1.5.
b.
Fire detection instrumentation, Specification 4.2.17.1.
c.
Fire suppression systems, Specifications 4.2.18.1, 4.2.18.2, 4.2.18.3, and 4.2.18.4.
d.
Reactor Coolant System, Specifications 4.2.2.22.a.1, 4.2.2.22.b.1, 4.2.2.22.f, and 4.2.2.22.g.
e.
Reactor Vessel Material Surveillance Program, Specification 4.2.2.4.
f.
Inservice Inspection, Specification 5.3.
6.9.3 Unique Reporting Requirements a.
Semi Annual Effluent Release Report Paragraph (a)(2) of Part 50.36a, " Technical Specifications on Effluents from Nuclear Power Reactors," of 10 CFR Part 50 requires that a report be made to the Commission within 60 days af ter January 1 and July 1 of each year.
The report shall specify the quantity of each of the principal radionuclides released to unrestricted areas by liquids and gaseous effluents during the previous 6 months of operation. The information submitted shall be in accordance with Regulatory Guide 1.21 (Revision 1) dated June 1974 and Regulatory Guide 4.1 dated January 18, 1973.
LACBWR 6-16 P
ACHINISTRATIVE CONTROLS 6.10 RECORD RETENTION
+
In addition to the applicable rec'ord retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTA8LE OCCURRENCES submitted to the Commission.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of changes made to the procedures required by Specification 6.8.1.
f.
Records of radioactive shipments.
g.
Records of sealed source and fission detector leak tests and results.
h.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained fer the duration of the Unit Operating License:
a.
Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Safeguards Report for Operating Authorization.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of radiation exposure for all individuals entering radiaticn control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
LACShR 6-17 r
AOMINISTRATIVE CONTROLS RECGRD RETENTION (Continued) e.
Records of transient or ecerational cycles for these facility ccepc-nents identified in Table 5.7.1-1.
f.
Records of reacter tests and experieents.
g.
Records of training and qualification for current members of the unit staff.
h.
Records of in-service inspections perforced pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities recuired by the Cperational Quality Assurance Manual.
j.
Records of reviews perfornec for changes =ade to procedures er equip =ent or reviews of tests and experiments pursuant to 10 CFR 50.59.
~
k.
Records of ceetings of the ORC and tne SRC.
6.11 RADIATION PROTECTION PROGRAM Precedures for personnel radiation prctecticn shall be prepared censistent with the recuirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all cperations involving personnel radiation ex;csure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 =res/hr but less than 1000 mrem /nr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be centrolled by requiriag issuance of a Special Work Permit (SWP).* Any individual or group of individuals permitted to enter such areas shall be provided with or accc=panie<1 by one or more of the folicwing:
^heaitn Pnysics personnel or personnel escorted by Health Phys.ics personnel snall ce exeret frcm the SWP issuance recuirement during the ;erfor:ance of their assigned radiaticn arctection cuties, previded they cceply with a;:reved radiation protection procedures for entry inte hign ra:iation areas.
LACEWR e-16
ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integratrs the radiation dosa rate in the area ano alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been estab-lished and personnel have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This indi-vidual shall be responsible for providing positive control over the activities within the area and shall r--form periodic radiation surveillance at the frequency specified hv 'he unit Health Physicist in the Special Work Permit.
6.12.2 The requirements of 6.12.1, above, shall als; ;oply to each high,racia-3 tion area in which the intensity of radiation is greater than 1000 mrem /hr.
In addition, lccked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the acministrative control of the Shift Supervisor on duty and/or the unit Health Physicist.
)
LACBWR 6-19
O n es. m pg)* 863-00 i
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INVOICE FOR SERVICES AND MATERIALS p ECEIV ED 1
f UsIITED STATES 800 CLEAR REGULATeaY CotaSMICR WFN:E 08' C088TacLLEn
,2;n t1AmassGToes C.c.2sses
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9 Get. E.. j i
To: Dairyland Power Cooperation Dese 7/22/80 ATTN:
Mr. John P. Madgett General Manager F. G. B.:
2615 East Avenw South Lacrosse, Wisconsin 54601 Terms:
mes 30 Osys ACCESS PtRMIT NO.
UCENSE NO.
PURCMAM QROER DPR-45 QUANTITY T
AMOUNT OESCRWTION OF SERvlCES AND MATERIALS E
OmOERED SMIPPED Indenrtity fee on the above license for the one year period from August 28, 1980 through August 27, 1981.
$4,950.00
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54,950.00
=aaE cueCx ray Aete to u s Nucteaa necutarcar co= Mission **o uAit To Asova Acoasss
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