ML20037B343
| ML20037B343 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/23/1973 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20037B341 | List: |
| References | |
| NUDOCS 8009150612 | |
| Download: ML20037B343 (29) | |
Text
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6.0 AD?flNISTRATIVE CONTROLS (Section I of present format technical specifications)
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6.1 Organization, Review, Investigation and Audit G.
The Revicw and Investigative Function and the Audit Function for facility operations A.
The Station Superintendent chall have shall he conntituted and have the responsi-overall full-time responsibility for bilitien and authoritics outlined below:
CD nafe operation of the facility.
During jj periods when the Station Superintendent 1.
The Offsite Review and Investigative es is unavailabic, he shall designate this Function and Audit Function shall be responsibility to the Ansistant Station supervised by th'c Superintendent of C}
Superintendent.
Nuclear and Fossil Systems.
(p)
B.
The portion of the corporate managenent a.
Offsite Review and Investinative N
which relates to the operation of this Function
(\\
atation in shown in Figurc 6.1.1.
N The Superintendent of Nuclear and C.
The normal functional organization for Fossil Systems shall:
(1) provide operation of the station shall be as direction for the review and investi-shown in Figure 6.1.2.
The shift manning gative function and appoint a senior for the station shall be as shown in participant to provide appropriate Figure 6.1.3.
direction, (ii) select cach parti-cipant for this function, (iii) review D.
Qualifications of the Dresden plant and approve the findings and recommend-management and operating staff shall meet ations developed by personnci performing minimum acceptable Icvels as described the review and investigative function, in ANSI N18.1, "Sc1cction and Training of and (iv) report all findings of Nuclear Power Plant Personnel", dated violations and provide recommendations Ibrch 8,1971.
to the Station Superintendent, Superin-tendent of Production Division "A",
E.
Retraining and replacement training of Manager of Production and that positicr; _
Station personnel shall be in accordance of corporate management that has with ANSI N18.1, " Select' ion and Training responsibility for nuclear activitics.
of Nuclear Power Plant Personnel", dated
}brch 8,1971.
The responsibilitics of the personnel perform'ing this function are stated F.
~ Retraining shall be conducted at intervals below:
not exceeding two years.
I-2
. _ = _ - - -
CORPORATE ORGANIZATION COMMONWEALTH EDISON COMPANY CORPORATE MANAGEMENT ADMINISTRATIVE FUNCTIONAL MANAGER OF PRODUCllON I
I I
1
-m SUPERINTENDENT OF SUPERINTENDENT OF SUPERINTENDENT OF NUCLEAR a FOSSIL PRODUCTION PRODUCTION SYSTEMS DIVISION "A" MAINTENANCE
~
I I
TECHNICAL SERVICES I
OUALITY ASSURANCE OFFSITE REVIEW STATION a INV ATIVE SUPERINTENDENT NUCLEAR POWER PLANT OVALITY ASSURANCE TECHNOLOGY g
pU C ON COORDINATORS ONSITE AUDIT REACTOR OPERATIONS g
OFFSITE AUDIT l~~~~~
FUNCTION UTILITY OPERATIONS l
FUNCTION I
___________j POWER PLANT DESIGN l
QUALITY ASSURANCE SUPER TEN ENT REACTOR ENGINEERING I
(SITE)
TRAINING l
RADIOLOGICAL SAFETY g
SAFETY ANALYSIS l
I I
INSTRUMENTATION 8 L---------------
TECH STAFF OPERATING MAINTENANCE CONTROL SUPERVISOR ENGINEERS ENGINEER g
METALLURGY ONSITE SHIFT CHEMISTRY REVIEW a ENGINEER ENVIRONMENTAL INVESTIGATIVE EFFECTS FUNCTION FIGURE G.I.I I-3
U ST.I. TICK OnG.'.NIZJ. TION CliART (THREE UldTS l'.T HOT SHUTDOWN OR POWER)
AD.7;NiSTRAT!VE
-- - - - FUN ~.~:O N AL l
SUPERINTENDENT j
!_,._____,,,,_.,,.,_, OUALITY ASSURANCE i
ENGINEER 1
1UD!T. U.'!OT;ON 1
1 SO 1, ASST. SUPER:NTENDENT 1
a i,
=
1 I
i TECH STAFF TRAINING OFFICE
!OPERATING.:
SUPERVISOR SUPERVISOR SUPERV.SN ENG:NEER 1
1
. " - ~ ~
So i
I
. _.j i
3 J
ONEITC REV:EW G INSTRUMENT Y
R tc
.'.M E.V.
THER *:iL NUCLEAR ENGINEER D
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CUPV.
ENG!NEER ENGINEER AT E.
! ENG;NEER l
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lj l 1
1 FUNCTION 1
D gggg7 S3!
)
iM 15 l
e M
i, f
ENGINEERS ENGINEERS D
'i i:==3 M
l s===3
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, ' ~.c r ;. ; ; <.- l l FohMAN FORkMAN P _ L MX\\.'X j
SO RAD PROT ENGINEERING FOREt/.AN
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4_,jl e f-MN 1
ASSISTANTS 1
i g===3 2
l 1S - '
I
. _ _ _ _. I I
O?ERATOR CLERKS r
~(.,
idt! tty NUCLEAR S-On Shif t FUEL STATION STA.OPER.
INSTRUMENT i-ANCLERS f/.EN O 4S RADMAN 0-Operator s License MECHANIC CLEC ECUIP.
SO-Senior Operator's License JANITORS U..'s t N T OPERATOR 13
- -The Fuci Handl.ing Forernon hos
(
73 o tirnited Senior Operator's ECUl?.
License. Requir d only during ATTEND.
fuel handling g
- -Shall coerate on E thore11 censed.
" r G.
' un'to 10r which is 1-4
TABLE 6.1.1 m
l~
H MINIMUM SHIFT MANNING CHART Condition Condition of No. of Fen in Each Position i
oC one Non -
Rad
_ _,,,,U n i t Second Unit Third Unit LSo*
Lo*'
Lic
, Men Cold Cold Shutdown shutdown 1
3 5
1 Cold
.;hutdown P.cfue l 1
3 5
1 COLD Cold Above cold Shutdoyin Shutdown 1
3 5
1
- t?IEDOWN R_efuel Refuel 2
3 5
y Befuel Above Cold Shbtdown 2
3 5
1 Above Cold Above Cold Shutopin Shutdown
_2-3 5
1 Re fu e]
Re fuel 2
4 5
1 P.EFUEL Re fuel
~Above Cold Shu tdown 2
4 5
l' Above Jold Above Cold Shutd.~, n Shutdown 2
4 S
1 A",OVE COLD ~
Above Cold Above Cold E:it'? C 0 W N Shutdown Shutdown 3
4 5
1 1
LSO
_ Licensed Senior Operator LO
- Licensed Operator NOI;-LIC
- Egt'ipraent Operators and !; n l:.'m int A.t r e nd an t s r
PAD MEN
- Itsriia tic'n l'rotect ion ?* 'n
' ?. 5. s 1 1. - r '-
.,n 3 ra M unita on h i t'h t b r '.-.sre not licen ud,
l
6.0 ANm!ISTMTIVE CONTROLS (6)
Review and report iindings (1)
Review and report findings and recomendations regarding and recommendations regarding all items referred by the proposed changes to the operating Technical Staf f Supervisor, licence of each unit, including Station Superintendent, and l
technical specifications, Superintendent of Production analyses, and reporta concerning Division. "A".
unreviewed safety questions, and the Safety Analysis Report for Offnite Audit Function _
,b.
oubmittal to the AEC.
The Offsite Audit Function shall bc
- (2)
Review and report findings and recommendations regarding reports directly superviced by the Superin-to be submitted to the AEC of tendent of-13ucicar and Fossil Systems or his designated alternate.
lic shall propor.ed modifications to plant systema or components involving appoint the auditors and approve the a proposed revision to the tech.
findings and reports of each sudit.
The audit functions nre itemized below:
nical specifications or an unreviewed safety question.
(1)
Perform, at Icast semiannually, (3). Advioc in matters considered to nudits of station operations
- involve unreviewed safety questions including records, logc, reports, tests, procedures, and changes or changes to the license, tech-
nical specificationo, or theeSafety thereto which may affect safety Analysio Report, or radiation caposure and verify that operations comply with the (4)
Investigate reported instances of terms, conditions, and intent of abnormal occurrences and violationo licenses or permits and other of technical specifications, including applicable regulations.
review of recommendations to prevent a reoccurrence.
Review and report (2)
Approve, review, and audit the recommendations regarding abnormal system of onsite audit of the occurrence reports submitted to the AEC.
station operations.
(5)
Review and report findings and recommendations regarding all changes to the Generating Stationa Emergency Plan prior to implementation of such change.
1-6 e
(3)
Report all findings of violations described in Specifications 6.1.C.l.a and recommendations and results of and b.
These procedures shall cover cach audit to the Station Super-the following:
intendent, the Superintendent of Production Division "A", Manager (1)
Content and method of submission of Production, and to that position of presentations to the Super-of corporate executive management intendent of Nuclear and Fossil that has responnibility for nuc1 car Systems.
activitics.
(2)
Use of committees and consultants.
c.
Authority (3)
Review and approval.
The Superintendent of Nucicar and Fossil Systems reports to the Manager of (4)
Detailed listing of items to be Production.
lic has the authority to reviewed.
order unit shutdown or request any other action which he deems necessary (5)
Revicw and approval of procedures to avoid unsafe plant conditions.
and checklists.to be used for cach audit of the facilitics.
d.
Records (6)
Hethod of (a) appointing personnel, (1)
Reviews, audits, and recommendations (b) perf orming reviews, investi-shall be documented with copics to gations and audits, (c) reporting the Superintendent of Production findings and recommendations of Division "A", and the S ta tion reviews, investigations and audits,
-Sup er in t end en t.
(d) approving reports, and (c) distributing reports.
(2)
Copics of documentation, reports, and correspondence shall be kept on (7)
Determining satisfactory completion
' file in the Superintendent of of action required based on Nuclear and Fossil Systems Of fice approved findings and recommen-and at the station.
dations reported by personnel Performing the review and investi-c.
Procedure Eative function and the auditing function.
Written administrative procedures shall be prepared and maintained for the functions 1-7
f.
Personnci shall be performed by personnel qualified an described for and (1)
The persons, including consultants, representing at least the dis-performing the review and investi-ciplines in (a), (b), (d), (f),
gative function and the audit and (g) below:
function, in addition to the Super-intendent of Nuclear and Fossil (a)
Nuc1 car Power Plant Systems, shall have expertise in
_Technolo gy, one or more of the following
"~' ~~ disciplines as appropriate for Graduate in engineering or the subject or subjects being a scientific discipline with reviewed, investigated, or 5 years' experience in audited:
technical or technical management positions relating (a) nuclear power plant technology to nuclear power plant design (b) reactot operations and/or operation.
(c) utility operations (d) power plant design (b)
Reactor Operations (c) reactor engineering (f) radiological safety Graduate in' engineering or a (g) reactor safety analysis scientific discipline with (b) instrumentation and control 5 years' experience in (1) metallurgy reactor operations of which at least 3 years have been and any other appropriate disciplines in supervision or management required by unique characteristics of nuclear power plant oper-ation.
of the facility.
(2)
Individuals performing the Review and Investigative Function and the Audit Function shall possess a minimum formal Graduate in engineering or a training and experience as listed below scientific discipline with for epch discipline. The audit function at least 5 years? cxperience in supervision of utility operations.
e 1-P
(d)
Power Plant Design (g) Reactor Safety Analynio Graduate in engineering or a Craduate in engineering or a ocientific discipline with scientific discipline with at at Icast 5 years of experience Icast 5 years of experience in technical or technical in nucicar engineering of manancment positions involving which at Icast-3 years have nuclear power plant design of been in technical or tedinical which at least 3 years are management positions that per-related to the system under form reactor safety analyses audit or investigation, of nuclear power plants.
(c)
Reactor Engineerina (h)
Instrumentation and Control Graduate in engineering or a Graduate in engineering or a scientific discipline with at scientific discipline with at least one year additional least 5 years of experience academic work in nuc1 car in instrumentation and control engineering and/or nucicar design or o*peration of which physics relating to nuc] car at least 3 years have been in power reactors.
In addition, technical or technical manage-at Icast 5 years of experience ment positions involving nuclear in technical or technical Power plant instrumentation management positions performing and controls.
nuclear power plant engineering or technical support for oper,
(i) !!ctallyn3y, ating nucicar power plants are required.
Graduate in metallurgical engineering or in mechanical (f) Radiological Safety _
cngineering with special' training in metallurgy and Graduate in engineering or a at least 5 years' cxperience ocientific discipline and 5 in technical or technical s
years of experience as a tech-management positions in the nical member or supervisor of metallurgical field including a radiation control organization at least 3 years' cxperience of which a't 1 cast 2 years have related to nuclear power been directly associated with plants.
an operating nucicar power plant.
1-9
2.
The Onsite Review and Investigative Function (2)
Review and report findings and and Audit Function shall be supervised by the recommendations regarding all Station Superintendent.
tests and experiments, proposed to be performed at the station,
_Onnite Review and Investigative Function which could involve hazards not n.
previously evaluated in the The Station Superintendent shall: (1)
Safety Analysis Report or which provide direction for the Revicu and require evaluation to determine Investigative Function and appoint the whether or not they are within-Technical Staff Supervisor as a senior the technical specifications, participant to provide appropriate direction, (11) select cach participant for this (3)- Review and report findings and function, (iii) review and approve the recor.2cndations regarding pro-findings and reconcendations developed by posed changes to the Technical personnel perforraing the Review and Specification, license, and Investigative Function, (iv) report all Safety Analysis Report, findings of violations, and provide recommendations to the Superintendent of (4)
Review and. report findings and Production Division "A" and the reco:?.cndations regarding pro-Superintendent of Nuclear and Fossil posed modifications to plant Systems, and (v) submit to the Offsite systems or equipment.
Review and Investigative Function for concurrence those items described in (5) Investigate reported instancea Specifications 6.1.C.l.a which have been of abnormal occurrences and approved by the Onsite Review and violc:fons of technical speci-Investigative Function.
fications and recommend corrective actions to prevent The responsibilitics of the personnel recurrences.
perforning this function are stated below:
(6)
Review plant operation and (1)
Review and report findings and maintenance logs to detect recommendations regarding all station potential safety hazards.
and company orders which affect operations.
(7) Perform special revicus and investigations and rendor reports thercon as requested by the Superintendent of Production Division "A" and the Superinten-dent of Nuclear and Fossil Systems.
k I-10
I b.
fbytte Audit Function intendent shall follow such recommen-a dations or sc]cct a course of action that The Onsite Audit Function shall be directly is more conservative regarding safe supervir.cd by the Station Superintendent, operation of the facility.
All cuch lie shall appoint the auditors and approve disagreements shall be reported immed-the findings and reports of each audit.
iately to the Superintendentn of Prod-The audit functions are itemized below:
uction Division "A" and Nuclear and Fossil Systems.
. (1) tbke at least quarterly audits of station operation including the review.
d.
Records of a representative sampic of records, logs, reports, tests, procedures and (1) Reports, reviews, investigations, audits!
changes thereto as well as other items and recommendations shall be documented which may affect nuclear safety and with copics to the Superintendents of radiation crposure and verify that the Production Division "A", Nuclear and station operation complies with the Fossil Systems, and the Station Superin-t e rms, conditions and intent of licenses tendent.
or permits and other applicable regulations.
All station docus.cnts (2) Copics of all records and docueentation discussed above and relating to the safe shall be kept on file at the station.
operation of the station shall be audited at least once cach calendar year.
8.
-Procedures - Written administrative procedures shall be prepared and maintained for conduct (2)
Report all findings of violations and of the Onsite Review and Investigative recommendations and results of each audit Function and Audit Function.
These procedures to the Superintendent of Production shall include the following:
Division "A" and the Superintendent of fluclear and Fossil Systems.
(1) Content and method of submiasion and presentation to the Station Superinten-
_ Authority - The Technical Staff Supervi::or is dent, Superintendent of Production c.
responsible to the Station Superintendent and Division "A", and Superintendent of shall make recommendations in all area:. of review, Nuclear and Fossil Systems, investigation, audit, and quality ansurance phasco of plant maintenance, operation and administrative (2) Use of committees.
procedures relating to facility operations and shall have the authority to req'uest the action (3) Review and approval necessary to ensure compliance with rules, regulations, and procedures when in his opinion (4) Detailed listing of itema to be reviewed.
such action is necessary.
The $tatien Super-I-11
(5)
Procedurer, for administration of the 1.
Normal startup, operation, and chutd:wn Quality Annurance Program, of the reactor and other systems and components involving nuclear safety of (6) Assignment of responsibilitics.
the facility.
F.
Personnel 2.
Refueling operations.
(1)
The personnel performing the Onsite 3.
Actions to be taken to correct specific Review and Investigative Function and and foreceen potentini malfunctions of Audit Function, in addition to the systems or components including responses Station Superintendent, shall consist to alarms, suspected primary system of persons having expertise in:
leaks, and abnormal reactivity changes.
(a) nuclear ~ power plant technology 4.
Emergency conditions involving potential (b) reactor operations or actual release of radioactivity -
(c) reactor engineering "Ccucrating Stations Emergency Plan" and (d) radiological and chemistry station emergency and abnormal procedures.
(c) instrumentation and control (f) mechanical and electric systems 5.
Instrumentation operation which could have an effect on the safety of the (2)
Personnel performing the Onsite Review facility.
and Investigative Function and Audit Function shall meet minimum acceptable 6.
Preventive and corrective maintenance icvels as described in ANSI N18.1.
operations which could have an effect on the safety of the facility.
(3)
The audits performed by the Onsite Audit Function shall be performed by personnel 7.
Surveillance and testing requirements.
representing at any time no less than four of the technical disciplines in 8.
Tests and experiments, specification 6.1.G.2.f(1).
9.
A procedure to ensure. safe shutdown of 6.2 Plant Operating Procedures the plant in the event of a flood desig-nated as a Probable Maximum Flood (PMF).
A.
Detailed written procedures including applicable checkoff lista covering items listed below shall be B.
Radiation control procedures shall be main-prepared, approved, and adhered to:
tain.cd and node available to all station perconnel. These procedures shall show per-
, missibic radiation exposure and shall be consistent with the requirements of 10 CFR 20.
This radiation protection program shall be
~
organized to meet the requirements of 10 CFR 20.
1-12
e I
I 6.0 ADMINISTRATIVE CONTR01.S 1.
Pursuant to 10 CFR 20.103(c)(1) and (3),
shall be subJcct to applicabic process allowance can be made for the use of and other engineering controls.
respira tory protective equipment in con-junction with activitics authorized by 2.
In all operations in which adequate the operating licenses for this plant in 8
limitation of the inhalation of radio-determining whether individuals in active material by the use of process restricted arcan are exposed to concentra-or other engineering controls is imprac-tionn in excess of the limits specified in ticabic, the licensee may permit an Appendix B, Tabic I, Column 1 of 10 CFR 20 individual in a restricted area to use subject to the following conditiens and respiratory protective equipment to limit i
limitations:
the inhalation of airborne radioactive material provided:
a.
The limits provided in Section 20.103(a) and (b) are not excccded.
a.
The limits Jn Specification 6.2.B.1 are not exceeded.
b.
If the radioactive material is of such form that intake through the skin or b.
Respiratory protective equipment is other additional ruute is likely, selected and used so that the peak individual exposures to radioactive concentrations of airborno radioactive material shall be controlled so that material inhaled by an individual the radioactive content of any critical wearing the equipment does not exceed organ f rom all routes of intake averaged the pertinent concentration values over 7 consecutive days does not excced specified in Appendix B. Table I, that which would result f, rom inhaling Column 1 of 10 CFR 20.
For the purpose such radioactive material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of this subparagraph, the concentration at the pcrtinent concentration values of radioactive material that is inhaled provided in Appendix B, Tabic I, when respirators are worn may be Column 1 of 10 CFR 20.
determined be dividing the ambient airborne concentration ~by the protectio factors in Tabic 6.2.1, appended c.
For radioactive materials designated "Sub" in the "Isotopc" column of to this specification, for the respiratory Appendix B Table I, Column 1 of protective equipment worn.
If the intake 10 CFR 20, the concentration value of radioactivity is later determined by specified is based upon expusure to other measurements to have been different from that initially estimated, the later the material as an external radiation source.
Individual exposures to these quantity shall be used in evaluating materials shall be aci:ounted for as the exposurcs.
part of the limitation on individual dose in Paragraph 20.101.
These materials 1-13
6.0 AININISTRATIVE CONTR_OLS c.
The licensee advises cach respirator (5) Written operational and admin-user that he may 1 cave the area at any intrative procedures for proper time for relief from respirator use in use of respiratory protective case of equipment malfunction, physical equipment including provisionn or psychological discomfort, or any for planned limitations on other condition that might cause reduction working times as necessitated.
in the protection afforded the wearer, by operational conditions, d!~ The licensec maintains a respiratory (6)
Bionssays and/or whole body protective program adequate to assure counts of individuals (and that the requirements above are met and other surveys, as appropriate) incorporates practices for respiratory to evaluate individual exposures protection consistent with thase recom-and to assess protection actually monded by the American National Standards provided.
Institute (ANSI-288.2-1969).
Such a program shall include:
e.
The liccasce uses equipcent approved by the U. S. sureau of Mines under its (1) Air sampling and other surveys appropriate Approval Schedules as set sufficient to identify the hazard, forth in Tabic 6.2.1 below.
Equipment to evaluate individual exposures, not approved under U. S. Bureau of to permit proper selection of Mines Approval Schedules may be used respiratory protective equipment, only if the licensec has evaluated the equipment and can denonstrate by (2) Written procedures to assure testing, or on the basis of reliabic proper selectica, supervision, test information. that the material and and training of personnel using performance characteristics of the such protective equipment.
cquipment are at least equal to those afforded by U. S. Bureau of Mines (3)
Written procedures to assure the approved equipment of the same type adequate fitting of respirators as specified in Tabic 6.2.1 below.
and the testing of respiratory pro,tective equipment for oper-f.
Unicss otherwise authorized by the ability immediately prior to use.
Commission, the licensec does not ass'ign protection factors in exccas (4) Uritten procedures for maintenance of those specified in Table 6.2.1 to assure full effectiveness of below in selecting and using respiratory protective equipment respiratory protective equipment.
Including issuance, cleaning, and decontamination, inspection, repair, and storage.
1-14
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TABLE 6.2.1 PROTECTION FACTORS FOR RESPIRATORS PROTECTION FACTORS i GUIDES TO SELECTION OF EQUIPMENT 5
PARTICULATES BUREAU OF MINES APPROVAL SCHEDULES
- 1!
AND VAPORS AND FOR EQUIPMENT CAPABLE OF PROVIDING AT DESCRIPTION MODES GASES EXCEPT LEAST EQUIVALENT PROTECTION FACTORS TRITIUM OKIDE
- or schedule superseding for equipment of type listed I.
AIR-PURIFYING RESPIRATORS Facepiece, half-mask 4/ 7/
NP 5
21B 30 CFR I 14.4(b)(4)
Facepiece, full 7_/
~-
NP 100 21B 30 CFR 5 14.4(b)(5); 14F 30 CFR 13 II.
ATMOSPliERE-SUPPLYING RESPIRATOR 1.
Airline respirator Facepiece, half-mask CF 100 19B 30 CFR 5 12.2(c)(2) Type C(i)
Facepiece, full CF 1,000 19B 30 CFR 5 12.2(c)(2) Type C(i)
Facepiece, full 7/
D 100 19B 30 CFR 5 12.2(c)(2) Type C(ii)
Facepiece, full PD 1,000 19B 30 CFR 5 12.2(c)(2) Type C(iii) 11ood CF 5/
6/
Suit CF 5/
6/
2.
Self-contained breathing _ (SCBA) apparatus Facepiece, full 7_/
D 100 13E 30 CFR 5 11.4(b)(2)(i)
Facepiece, full PD 1,000 13E 30 CFR 5 11.4(b)(2)(11)
Facepiece, full R
1,000 13E 30 CFR 5 11.4(b)(1)
III.
ColiBINATION RESPIRATOR Any combination of air-Protection factor for 19 B CFR S 12.2(c) or applicabic purifying and atmosphere-type and mode of opera-schedules as listed above supplying respirator tion as listed above 1/, 2/, 3/, 4_/, 5_/, 6/, 7/ - [Ihese notes are on the following pages]
s 1-15
{
(
-1/
See the following symbols:
CF:
continuous flow D: demand NP: negative pressure (i.e., negative phase during inhalation)
PD: pressure demand (i.e., always positive pressure)
R:
recirculating (closed circuit)
(a) For purposes of this specification, the protection f actor is a measure of the degree of protection
--2/
af forded by a respirator, defined as the ratio of the concentration of airborne radioactive material outside the respiratory protective equipment to that inside the equipment (usually inside the f ace-piece) under conditions of use.
It is applied to the ambient airborne concentration to estimate the concentration inhaled by the wearer according to the following formula:
n Air rn ncentration Concentration Inhaled = Am i Protection Factor (b) The protection factors apply:
(i) only for trained individuals wearing properly fitted respirators used and maintaine,d under super-vision in a well-planned respiratory protective program.
for air-purifying respirators only when high ef ficiency (above 99.9% removal efficiency by U. S.
(ii) Bureau of Mines type dioctyl phthalate (DOP) test] particulate filters and/or sorbents appropriate to the hazard are used in atmospheres not deficient in oxygen.
(iii) for atmosphere-supplying respirators only when supplied with adequate respirable air.
For tritium oxide 1
Excluding radioactive contaminants that present an absorption or submersion hazard.
approximately half of the intake occurs by absorption through the skin so that an overall protection factor
-m-of not more than approximately 2 is appropriate when atmosphere-supplying respirators are used to protect See against tritium oxide.
Air-purifying respirators are not recommended for use against tritium oxide.
also footnote S/, below, concerning supplied-air suits and hoods.
--4/
Not recommended for use where it might be possible for the ambient airborne concen-Under chin type only.
t ration to reach instantaneous values greater than 50 times the pertinent values in Appendix B; Table I, Column 1 of 10 CFR, Part 20.
I-16 s
5/
Appropriate protection factors must be determined taking account of the design of the suit or hood and its permeability to the contaminant under conditions of use.
No protection factor greater than 1,000 shall be used except as authorized by the Commission.
ft/
No approval schedules currently availabic for this equipment.
Equipment must be evaluated by testing or on basin of available test information.
7/
Only for shaven faces.
NOTE 1:
Protection factors for respirators, as may be approved by the U. S. Bureau of Mines according to approval schedules for respirators to protect against airborne radionuclides, may be used to the extent that they do not exceed the protection factors listed in this Tabic. The protection factors in this Tabic may not be appropriate to circumstances where chemical or other respiratory hazards exist in addition to radioactive hazards.
The selection and use of respirators for such circumstances should take into account approvals of the U. S. Bureau of Mines in accordance with its applicable schedules.
NOTE 2:
Radioactive contaminants for which the concentration values in Appendix B, Table I of 10 CFR Part 20 are based on internal dose due to inhalation may, in addition, present external exposure hazards, at higher concentrations.
Under such circumstances, limitations on occupancy may have to be governed by external dose limits.
I-17 s
6.0 ADlut!ISTPATIVE cottrROLS I
F.
Temporary changes to operating pro-These specifications with respect to the cedures described in Specification 3.
provisions of paragraph 20.103 shall be
,. 6.2. A above, which do not change the auperseded by adoption of proposed changes intent of the original procedure, may to 10 CFR 20, Section 20.103, which would be made with the coacurrence of two make this specification unnecessary, individuals holding Senior Operator Licenses.
Temporary changes to C.
Standing Orders to the operating staff shall electrical and mechanical maintenance require that the procedurca in Specifications procedures described in Specification 6.2.A and B above are to be followed in con-6.2.A above, which do not change the ducting activitiec identified in the order.
intent of the original procedures may be made with the concurrence of the D.
Work instructions or special test procedurca Mas ter Mechanic, liaintena'nce Yoreman',
~
for the operating or maintenance staff shall and the Senior Operator of the offected require that the procedures in Specifications unit.
Temporary. changes to instrument 6.2.A and B above are to be followed in maintenanc.c procedures described in conducting activitics identified therein, Specification 6.2.A above, which do not E,
All procedurca identified in Specification change the intent qf the original pro-6.2.A and any changes to those procedurcs chall cedures, may be made with the concurrence of the Instrument Engineer, Inntrument be reviewed and approved by the operating Foreman, and the Senior Operator of the Engineer and the Technical Staf f Supervisor in nreas of operation, fuel handling, or instrumenp affected unit.
Such changen shall be documented and subsequently reviewed, maintenance, and by Maintenance I:ngineer and the Technical Staff Supervisor in the arcas approved, and authorized as provided in of plant maintenance and plant inspection.
All Specifications 6.2.E above.
procedures identified in Speci[ication 6.2.B and any changes to those procedures shall be G.
Drills of the cocrgency procedures descri'l
, reviewed and approved by the Technical Staff in Specification 6.2. A.4 shall be conducteo
' N 'Supervioor and the padiological-Chemical quarterly. Theoc drilla will be planned no that during the courac of the year communi-f Supervioor.
The procedurca,and changes thereto e L
annt havo' authorization by the Station Superin-cation links are tested and outside agencied qg tendent before being impicmented.
i are contacted.
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y
- 6.0' $0MI?4ISTRATIE cot;TROLS 6.3 Action to be Taken in the Event of an Abnormal 2.
Records of principal maintenance and Occurrence'in Plant Operation activities, including inspection and repair, regarding principal i
Any abnormal occurrence shall be promptly items of equipment pertaining to reported to the Superintendent of Production nucicar safety.
Division "A" or his designated alternate.
The incident shall be promptly reviewed pursuant 3.
Records and reports of abnormal to Specification 6.1.G.2.a.'(5) and a separate and safety limit occurrences.
report for each abnormal occurrence shall be prepared in accordance with the requirements 4.
Records and periodic checks, of Specification 6.6.B.l.
inspection and/or calibratior.s performed to verify the Surveillance 6.4 Action to be Taken in the Ev at a Safety Limit Requirements (see Section 4 of these is Execeded Specifications) are being met.
All equipment failing to meet surveillance If a safety limit is exceeded, the reactor shall requirements and the corrective action be shut down innediately and reactor operation taken shall be recorded.
shall not be resumed until authorized by the AEC.
The conditions of shutdown shall be promptly S.
Records of changes made to the equipment reported to the Superintendent of Production or reviews of tests and experiments to Division "A" or his designated alternate. The comply with.10 CFR 50.59.
incident shall be reviewed pursuant to Specifi-cation 6.1.G.2.a.(5) and a separate report for each occurrence shall be prepared in accordance with Specification 6.6.B.l.
6.5 Plant Operating Records A.
Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least five years.
1.
Records of normal plant operation, including power levels and periods of operation at cach power level.
1-19
s R
, 6.0 AN!INISTRATIVE CONTROLS 6.
Records of radioactive shipments.
' 8.
Records of radiation exposure for-all plant personnel, including all contractors -
7.
Records of physic tests and other tests and visitors to the pla'nt in [ccordance -
pertaining to nuclear safety, with 10 CFR 20.
8.
Records of changes to operating procedurcs.
9.
Records of radioactivity in liquid and gaseous vastes released to the environment.-
9-Shift Enginects Iogs.
10.
Records of trcnsient or operational cycling E.
Records and/or logs relative to the following for'thosa components that have been designed itema shall be recorded in a manner convenient to operate' safely for a limited number of for review and shall be retained for the life transient or operational cycles.
of-the plant.
11.
Records of Individual staff necbers; 1.
Substitution or replacement of principal indicating qualifications, experience.
Items of equipment pertaining to nuc1 car training, and retraining.
safety.
12.
Inservice inspections of the reactor coolant 2.
Changes made to the plant as it is described system.
~
in the Safety Analysis Report.
- 13. Minutes of meetings and results of revicus 3.
Records of new and spent fuel inventory and audits performed by the of f-site and and assembly histories.
on-site review and audit functions.
4.
By-product material inventory records and source leak test results.
5.
Updated, corrected, and as-built drawings of the plant.
6.
Records o'f plant radiation and contamination surveys.
Recordo of ohf-site environmental monitoring 7.
curveya.
G I-20
6.0 ADMINISTRATIVE CONTROLS 6.6 plant Reporting Requirements following commencement or resumption of commercial power operation (i.e..
The following information shall be submitted initially following synchronization in addition to those reports required by of the turbo-generator to produce Titic 10, Code of Federal Regulations.
commercial power or resuming power production).
A.
Operation Reports 2.
First Year Operation Report Operation reports shall be submitted in writing to the Director of Licensing, A report shall be submitted within USAEC, Washington, D. C.
20545.
60 days after completion of the first year of commercial power operation as defined above. This report may be 1.
Startup Report incorporated into the semiannual A summary report of unit startup and operating report and shall cover the power escalation testing shall be following:
submitted following receipt of opera-an evaluation of ' unit performance ting licenses, following amendments a.
to the licenses involving a planned to date in comparison with design increase in power level, following predictions and specifications; the installation of fuel that has a different design or was fabricated b.
a reassessment of the safety by a different vendor, or following analysis submitted with the NSSS modifications that may have sig-license application in light nificantly altered the nucicar, thermal, of measured operating character-or hydraulic performance of the istics when such measurements facility. The report shall include indicate that there may be sub-a comparison of measured and pre-stantial variance from prior dicted values and describe any cor-analyses; rective action taken to obtain acceptable operation.
Startup reports c.
an assessment of the performance shall be submitted within 60 days of structures, systems and compo-nents important to cafety; 1-21
l 6.0. [LIRSj d ATIVE CONTROLS l
d.
a progress and status report on (3) changes in procedures which
- pny items identified as requiring I
vere necessitated by (1) and additional infornation during the (2) or which otherwise werc operating license review or dur-required to improve the safety ing the startup of the plant,
' of facility operations, including items ' discussed in the AEC's safety eva'luation, items on (4) results of surveillance tests which additional information was and inspections required by required as conditions of the license and items identified in these technical specifications, the licensce's startup report.
(5) the results of any periodic containment leak rate tests 3.
SemiannGal Operating Reports performed during the reporting
- period, Semiannual operating reports covering the previous six months operations (6) a brief summary of those shall be submitted within 60 days channes, tests and experiments af ter January 1 and July 1 of each requiring authorization frod year.
The first such period shall the Comnission pursuant to begin td th the date of initial 10 CFR 50.59(a), and criticality. These reports shall include the fol'.owing:
(7) any changes in the plant operating organization which a.
Operationr Summary involve positions which are designated as key supervisory A summary of operating expericnce personnel on Figure 6.1.2.
occurring during the reporting period that relates to the safe b.
Power Generation opera tion of the plant, including a summary of:
A summary of power generated during (1) changes in plant design, the reporting period including:
(1) gross thermal power generated (2) performance ch'aracteristics (in MWil)
~
(e.g., equipment and fuel per fo.rmanc e),
1-22 A
6.0 AtRIII!ISIRATIVE CONTROLS (2) groso elec.trical power generated d.
Maintenance (in NWH)
A discussion of corrective maintenance (3) net cicetrical power generated (excluding preventative maintenance)
(in Fant) performed during the reporting period on safety related systems and components (4) number of hours the reactor was
[nafoty related is defined in ANSI critien1 18.7-1972 (ANS-3 2, November 2,1972)];
For any malfunctions for which (5) number of hours the generator corrective maintenance was required, was on-line information shall be provided on:
(6) histogram of thermal power va time (1) the system or conponent involved, c.
Shutdowns (2) the cause of the en1 function, Descriptive material covering all outages occurring during the reporting (3) the results and effect on safe Period.
For each outage, information operation, chall be provided on (4) corrective action taken to prevent (1) the cause of the outage, repetition, (2) the method of shutting down (5) precautions taken to provide for the reactor; c.g.,
trip noto-reactor nafety during repair.
matic rundown, er manually controlled deliberate shut-
.e.
Changes, Testo and Experiments
- down, The report shall include a brief (3) duration of the outage. (in hours),
description and the summary of the safety evaluation for those changes, (4) rnit'otatua during the outage; testa,.and experiments carried out e.g., cold shutdown or hot without prior Commionion approval
- shutdown, pursuant to the requiremento of subocction 50.59(b) of the commiosion'a (5) corrective action' taken to pre-regulations.
vent repetition, if appropriate.
I-23.
l 6.0 Mtif tilSIltATIUE CO:nROI.S I
f.
P.adioactive Effluent Releases (c) Particulate Releases
{
A statement of the quantities of (1)
Total gross radio-radioactive ef fluents released f rom activity (8,y) released' the plant with data summarized on a (in curics) excluding monthly basis following the format background radioactivity.
of the USAEC Regulatory Guide 1.21.
(2)
Total gross alpha radio-activity released (in (1) Cascous Effluents curics) excluding back-ground radioactivity.
(a)
Gross Radioactivity Releases (3)
Total gross radio-(1)
Total gross radioactivity activity released (in' '
(in curics) primarily noble curics) of nuclides and activation gases released.
with half-lives greater than cight days.
(2)
Maximum gross radioactivity release rate during any (4)
Percent of technical one-hour period.
specification limit for particulate radio'-
(3)
Total gross radioactivity activity with half-(in curics) by nuclide lives greater than released, based on repre-cight days.
sentative isotopic analyses performed.
(2)
Liquid Effluents (4)
Percent of technical specifi-(a)
Total gross radioactivity cation limit.
(S,y ) released (in curies) excluding tritium and (b)
Iodinc Releases average concentration released to the unrestricted (1)
Total lodine radioactivity area.
(in curics) by nuclide released, based on repre-sentative isotopic analyses performed.
(2)
Percent of technical specifi-cation limit for I-131 released.
I-24 4
6.0 ArnITNISTRATIVE CONTR01.5 (b) Total tritium and total alpha -
g.
Solid Radioactive Waste radioactivity released (in curies) and average concentrat. ton (1) The total amount of solid released to the unrestricted area.
waste shipped (in cubic feet).
(c) Total dissolved noble gas (2) 'The total estimated radioactivity radioactivity released (in curics)
(in curies) involved.
and average concentration released to the unrestricted area.
(3)
The dates of shipment and dis-position (if shipped offsite).
(d) Total volume (in liters) of liquid waste released.
h.
Environmental Monitoring (c) Total volume (in liters) of dilution (1)
For each medium sampled during water used prior to-release f rom the the reporting period, e.g.,
- air, restricted area.
baybottom, surface water, soil, fish, include:
(f) The maximum concentration of gross radioactivity (8,y) released to the (a) Number of sampling locations, unrestricted area (averaged over the period of release).
(b) Total number of samples, (g) Total gross radioactivity (in curics)
(c) Number of locations at which by nuclide released, based on repre-levels are found to be sig-sentative isotopic analyses performed.
nificantly above local backgrounds, (h)
Percent of technical specification limit.
(d) Ifighest, lowest, and the average concentrations or levcis of radiation for the nampling point with the highest average and a
I-25 a-
6.0 AtHINISTRATIVE CONTROLS description of the loca-personnci (permanent and temporary) tion of that point with in the following exposure increments renpect to the site, for the reporting period:
Less than 100 mrem, 100-500 mrem, 500-(2)
If levels of radioactive materials 1250 mrem, 1250-2500 mrem, and in the environmental media as greater than 2500 mrem.
Tabulate
~
determined by the environmental the number of personnel receiving monitoring program indicate the more than 500 mrem exposure in the likelihood of public Intakco in reporting period according to duty excens of 1% of those that could
- function, i.e.,
routine plant sur-veillance and inspection (regular renuit from continuous annual exposure to the concentration duty), routine plant maintenance,
~
values listed in Appendix B, Table i.
special plant maintenance (describe II, Part 20, estimates of the maintenance), routine refueling likely resultant exposure to operations, special refueling operation individuals and to population (described operation) and other job groups, and assumptions upon related exposures.
Anually tabulate which estimates are based shall the number of personnel receiving be provided.
~
more than 2500 mRcm cad report major cause(s).
(3) If statistically significant
.i.
variations of offsite environ-D..Non-Routine Reports mental concentrations with timo are oboerved, correlation of 1.
Ib' normal Occurrence Reporta
- thene resulto with radioactive
..p.
tificati n shall be riade within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ef fluent relcanes shall be pro-by telephone.and teleg raph to the Director vided.
of the Regional Reguintory Operations Of f f *
(ce to Director of ' icensing) followed by'.
1..
Occupational Personnel Radiation
-written report within 10 days to the Director Exposure of Licensing (cc to the Director of the Regional Regulatory Operations Office) in the Tabulate the number of personnel event of the abnormal ottorrenceo na defined exposuren for plant operations in Section 1.0 of thcoe technical specifi-
. cations.- The written report on these abnorma i
1-26
6.0 ADMINISTRATIVE CONTR0lS
[
occurrences, and to the extent possible s.
Discovery of any substantial errors l
the preliminary telephone and telegraph in the transient or accident analyses, notification shall include the events leading or in the methods used for such up to and resulting from the occurrence, an analyses, as described in the Safety i
evaluation of the cause of the occurrence, Analysis Report or in the bases for and:
(a) describe, analyze and evaluate the technical specifications.
safety implications, (b) outline the measures taken to annure that the cause of the b.
Discovery of any substantial variance condition is determined, (c) indicate the from performance specifications contained corrective action (including any changes in the technical specifications or in made to the procedures and to the quality the Safety Analysis Report.
assurance program) taken to prevent repetition of the occurrence and of similar occurrences c.
Discovery of any condition involving a involving similar components or systems, and possible single failure which, for a (d) evaluate the safety implications of the system designed against assumed single incident in light of the cumulative experience failures, could result in a loss of the obtained from the record of previous failures capability of the system to perform its and malfunctions of similar systems and safety function.
components.
3.
Special Reports b.
Copies of all such reports shall be submitted to the Superintendent of Production Division Special reports shall be submitted in writing "A" and Nuclear and Fossil Systems for review within 90 days to the Director of Licensing, of any recommendations.
USAEC, Washington, D. C.
20545.
2.
Unusual Events Reports a.
In the event a redundant component Gmr system) covered by these technical A written report shall be forwarded within 30 days specifications is determined to be out of to the Director of Licensing, and to the Director service for periods longer than those of the Regional Regulatory Operations Office, in specified in other sections, it shall b.
the event of:
the subject of a special maintenance report. If this report requests approval to continue plant operation, it shall be I-27
s 6.0 ADMIMISTRATIVE__C0tiTROLS
}
submitted prior to expiration of the out of service time of the above.
The report shall describe I
(1) The nature of the problem and the r
specific steps to be taken to remedy the situation.
(2) An estimate of the time required to return the component (or system) to an operable condit' ion.
(3) The amount of component (or system) redundancy remaining or the avail-ability of other system (s) to perform the same function as the inoperable component (or system).
(4) Surveillance Requirements on the operable components (or systems).
b.
Any significant changes in the information supplied in Specifications 6.6.B.3.a(1), (2),
(3) or (4) shall be submitted as a report within seven days of discovery.
c.
Reports on the following areas shall be as indicated in Table 6.6.1.
e l
I-28 k
Abnormal Occurrence An abnormal occurrence means the occurrence of any plant condition that:
1.
Exceeds a Limiting Condition for Operation as established in Section 3 of the Technical Specifications, 2.
Causes any uncontrolled or unplanned release of radioactive material from the site, 3.
Results in one or more engineered safety features or plant protection system component failure which causes or threatens to cause the feature or component to be incapable of 0 7 performing its intended function as defined in the Technical Specifications or SAR, 4.
Results in abnormal degradation of one of the several boundaries which are designed to contain the radioactive materials resulting from the fission proccan, 5.
Results in uncontrolled or unanticipated change in reactivity of greater than 17, delta k/k, 6.
Results in observed inadequacies in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with the operation of the plant, or 7.
Causes conditions arising from natural or offsite manmade event that affect or threaten to affect the safe operation of the plant.
1-29
TABLE 6.6.2 Special Reports Area Reference Submittal Date a.
Containment Leak Rate Tests (1) 4.7.A Upon completion of each test b.
Summary Status of Fucl Performance 1.1 Bases After each refueling outage Notes:
1.
Each integrated leak rate test of the primary containment shall be the subject of a summary technical report including results of the local leak rate tests since the last report. The report as described in Appendix J to 10 CFR Part 50 shall include data, analysis, and interpretations of the results which demonstrate compliance in meeting the specified leak rate limits.
2.
Proposed Change to Appendix A dated May 17, 1973.
9 I-30 i