ML20069B862
| ML20069B862 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/11/1983 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20069B861 | List: |
| References | |
| NUDOCS 8303170310 | |
| Download: ML20069B862 (9) | |
Text
AMENDMENT +B-@
LSCS-FSAR
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weekend, the Radiation / Chemistry Technicians report to the Shift Engineer in the absence of Radiation Protection Supervision of the site.
13.1.3 Qualifications of Nuclear Plant Personnel 13.1.3.1 Qualification Requirements The guidelines of Regulatory Guide 1.8 are generally followed by LSCS management for personnel selection and training.
For some positions, alternate qualifications are utilized based upon operating experience.
Table 13.1-1 lists plant staff positions and designates ANSI N18.1, 1971 equivalent titles l
13.1.3.2 Qualification of Plant Personnel The qualif.ications of the initial personnel on the LSCS staff holding key managerial.and supervisory positions are provided in +bo r6 sum 6s included in this chapter.
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as Juir yA 18, 71, ept t ind uals Tn raining l wi Jer wor r wh' qual ati ha be mon. r ed ord to t in t
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The LSCS technical specifications require that -Lhc aif-L c a -
a in rcliaticr protecticr y;;
i M"h r indicidual yclific 4 "c 2 r c a.
An individual shall be considered qualified in radia-ls$
tion protection procedures upon certification by the licensee c
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that he is capable of successfully accomplishing the following y
2 activities:
2-Conduct special and routine radiation, contamina-l$d a.
tion and airborne radioactivity surveys and gh evaluate the results.
3 5
E b.
Establish protective barriers and post appropriate w
radiological signs.
S c.
Establish means of limiting exposure rates and
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accumulated radiation doses, including the use of g 3 protective clothing and respiratory protection g
equipment.
ff d.
Perform operability checks of radiation monitors J
and survey meters.
(o Recommend appropriate immediate actions in the 2
e.
A J
event of a radiological problem and perform Qh necessary activities until the arrival of health (gg physics personnel.
8303170310 830311 PDR ADOCK 05000373 13.1-13 P
LSCS-FSAR AMENDMENT"99 kd3 1^?^-
f.
Conduct other routine radiological duties (e.g., Technical Specification survelliance items) as may be required on hackshifts or weekends.
I dividuals assign to a shift c w wh do not m t the ex-pel ence requirem s of ANSI N18.1 1, may p r rm radi tion hemistry a ivi ies for which, alificat' n ha bee demons rated pr vided -hat the res ts f ana ses pe o,ed by the divid al are r viewed b.
a a technician o
eets the r q irements of ANSI N18.1, 19 Section
.5.2, or a
upervis not 1 quir' g an NRC conse who me s th requireme t of ANSI N1
.1
- 1971, l
Sect 4.5.2, or c.
an ndi
- dual w neets he quirements f
SI N18.
19 Section
.4.3,
" Chemist l
and Radioc e 1stry."
TODY N&&
13.1-13a
FSAR Section 13.1.3.2 INSERT A
'The ANSI N18.1-1971 qualification requirements for Rad / Chem Technician may also be met by either of the following alternatives:
1)
Individuals who have completed the Rad / Chem Technician training program and have accrued one year of working experience in the specialty, or 2)
Individuals who have completed the Rad / Chem Technician training program, but have not yet accrued one year of working experience in the specialty, who are supervised by on-shift health physics supervision who meet the requirements of ANSI N18.1-1971 Section 4.3.2, Supervisor-Not Requiring AEC Licenses, or Section 4.4.4, Radiation Protection.
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C' FSAR Section 13.1.3.2 INSERT B All Radiation / Chemistry Technicians on the backshift shall be trained per the Rad / Chem Technician Training Program.
All such Technicians shall also have satisfactorily completed the following emergency response training:
(1)
Tasks to be performed during the first 60 minutes of a serious emergency on the backshift; (ii)
Post-accident sampling and analysis for the'first three hours of an emergency; (iii)
In-plant radiation surveys during an accident; (iv)
Use and interpretation of both portable and fixed area radiation monitoring equipment, such as the Eberline PING-3 and SAM-2; 1
(v)
Interpretation of critical _ effluent monitoring data for assisting the Shif t Engineer during the first hour of an accident (i.e.,
station vent monitor and standby gas treatment monitor);
(vi)
First aid and bioassay techniques; and (vii)
Use of respiratory equipment during emergency situations.
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ATTACHMENT'A --ENCLOSURE 2 i
4 Commonwealth Edison Company 1
Proposed Change to Technical Specifications i
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/O ADMINISTRATIVE CONTROLS v)
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Any deviation from the above guidelines shall be authorized by the Station Superintendent or his deputy, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Station Superintendent or his designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
D.
Qualifications of the station management and operating staff shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971.
The Rad / Chem Supervisor shall meet the requirements of radiation protection 3g er of Regulatory Guide 1.8, September, 1975.
ma E.
Retraining and replacement training of Station personnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971 and Appendix "A" of 10 CFR Part 55, and shall include familiarization with relevant industry operational experience identified by the 0NSG.
F.
Retraining shall be conducted at intervals'not exceeding 2 years.
G.
The Review and Investigative Function and the Audit Function of activities p) affecting quality during facility operations shall be constituted and g
have the responsibilities and authorities outlined below:
G 1.
The Supervisor of the Offsite Review and Investigative Function shall be appointed by the Director, Nuclear Safety.
The Audit Function shall be the responsibility of the Manager of Quality Assurance and shall be independent of operations.
a.
Offsite Review and Investigative Function The Supervisor of the Offsite Review and Investigative Function shall:
(1) provide directions for the review and investigative function and appoint a senior participant to provide appropriate direction, (2) select each participant for this function, (3) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) independently review and approve the findings and recommendations developed by personnel performing the review and investigative function, (5) approve and report in a timely manner all findings of non-compliance with NRC require-ments to the Station Superintendent, Division Vice President -
Nuclear Stations, Manager of Quality Assurance, and the Vice President - Nuclear Operations.
During periods when the Supervisor of Offsite Review and Investigative Function is unavailable, he shall designate this responsibility to an established alternate, who satisfies the formal training and experience for the Supervisor n
of the Offsite Review and Investigate Function.
The responsibil-(d ities of the personnel performing this function are stated below.
)
The Offsite Review and Investigative Function shall review:
LA SALLE - UNIT 1 6-3
ADMINISTRATIVE CONTROLS Offsite Review and Investigative Function (Continued)
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1)
The safety evaluations for (1) changes to procedures, equipment, or systems as described in the safety anal sis report and (2) tests or experiments completed under he provision of 10 CFR 50.59 to verify that such acti s did not constitute an unreviewed safety question.
Pr posed changes to the Quality Assurance Program descri ion shall be reviewed and approved by the Manager of Qu ity Assurance.
2)
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as d ined in 10 CFR 50.59.
3)
Proposed tests or experiments which inv lve an unreviewed safety question as defined in 10 CFR 56.59.
4)
Proposed changes in Technical Speci 1 cations or NRC operating licenses.
5)
Noncompliance with NRC requirements, or of internal procedures, or instructions having nuclear safety significance.
6)
Significant operating abnorrp lities or deviation from normal and expected perfor,mance of plant equipment that affect nuclear safety as referred to it by the Onsite j
Review and Investigativ,e Function.
7)
Reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to
/
the NRC.
8)
All recognized in.dications of an unanticipated deficiency in some aspect of' design or operation of safety-related structures, systems, or components.
/
9)
Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change.
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- 10) Review,and report findings and recommendations regarding all i,t' ems referred by the Technical Staff Supervisor, i
Station Superintendent, Division Vice President - Nuclear Sta'tions, and Manager of Quality Assurance.
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O SALLE - UNIT 1 6-4
Technical. Specifications Section 6.1.0 INSERT-The ANSI N18.1-1971 qualification requirements for Rad / Chem Technician may also be met by either of the following alternatives:
1)
Individuals who have completed the Rad / Chem Technician training program and have accrued one year of working experience in the specialty, or 2)
Individuals who have completed the Rad / Chem Technician training program, but have not yet accrued one year of working experience in the. specialty, who are supervised by on-shift health physics supervision who meet the requirements.of ANSI N18.1-1971 Section 4.3.2, Supervisor Not Requiring AEC Licenses, or Section 4.4.4, Radiation Protection.
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ATTACHMENT B Status of License Change Requests Change Request Description Status-NPF-11/82-14 Rad Effluent Tech Specs revision Submitted to of reporting, etc.
NRC 4-08-82.
Telecon 12/82 awaiting CECO resubmittal per agreement in telecon.
NPF-11/83-01 Add position of Project Manager Submitted to NRC 2-24-83.
NPF-ll/83-02 Revise CO2 tank level require-Submitted to ment NRC 2-24-83.
NPF-11/83-03 Delete license condition 2.C.(26)
Submitted to and revise Tech Spec Section 6.1.D NRC 3-11-83.
regarding RCT qualifications 6132N
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