ML20002A366
| ML20002A366 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/11/1975 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20002A365 | List: |
| References | |
| NUDOCS 8011140311 | |
| Download: ML20002A366 (22) | |
Text
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PARAGRAPH "11" 6.0 ADMINISTPATIVE CONTROLS Administrative controls are the written rules, orders; instructions, procedures, policies, practices, and the' designation of authorities and responsibilities by the management to obtain' assurance or safety and quality of operation and maintenance of a nuclear power reactor.
These controls shall be adhered to.
6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall safe and efficient facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 In all matters relating to the operation of the plant and to these Technical Specifications, the Plant Superintendent shall report to and be directly responsible to the tianager of Operations in the Yankee Atomic Electric Company.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 The Facility organizat. ion shall be as shown on Figure 6.2-2 and; a.
Each duty shift shall be composed of at least the minimum shift creu composition shown in Table 6.2-1.
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 roon during reactor start-up, scheduled reacter 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.
Operating crew personr.el trained in radiation protection procedures fill this requirement.
c.
All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Operator or Senior Operator Limited to Fuel llandling whc has no other concurrent responsibilites during this operation.
6-1 80n140 M
WESTBORO OFFICE OF THE YANKEE ATOMIC ELECTRICCOMPANY CNSDh
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Vice President Ela i
CD!
y Vice President ATO Assistant Vice President Assistant Treasurer Vice President Operations
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8 Computer Director ATO Director Manager of Manager of a
r Applications E@My f Engineering Security Operations 9
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I t-sal. Ctl.
I.21 a n t.
Enytl. Engr.
Reactor Engr.
Manager Construction Plant l-(Aud.Mgr.
Engin g
nager Manager Manager of Projects Manager Superir.tendent v
Asst. Const.
[
Manager J
Figdre 6.2.1 CORPORATE ORGANIZATION
i t;;a PIJJIT -
SUPERINTEiDENT llFD ASSISTANT m
PLA!!T SUPERINTalDENT
-C JE MAINTSIANCE OPERATIONS REACTOR INSTRUMENT &
CHDIISTRY &
p SUPERVISOR SUPERVISORS SUPERVISOR CONTROIS HEALTH PHYSICS E
SUPERVISOR SUPERVISOR 1
I I
o MAINTElANCi SHIFT REACTOR INSTRUMENTATION SUPERVISOR ENGINEERING
& CONTROLS ORGA!IIZATIGH l' CHDiIST FHYSICIST ASSISTANTS TECHNICIANS I
I i
CONTROL ROOM CHC4. & H. P.
OPERA'IDRS TECHNICIANS AUXIIJARY OPERATOP3 FIGURE 6.2.2 - FACILITY ORGANIZATION 1
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1 ADMII:ISTRATI'.*E C05TROLS TABLE 6.2-1 CONDITIONS MI :I!:U:1 SHIFI CRD.'
PERSO::::EL 6 L:CE:;5E NORMAL PLANT COLD OPERATION STARTUP S11UTDOWN REQUIPJ.ME:!S Shift Supervisor (1)
(l')
(1)
Control Roon Oparator (2)
(2)
(1)
Auxiliary Operator (2)
(2)
(1)
Extra Operater (1)
Senior Operat:rs License (1)
(1)
(1)
Reactor Operators License (2)'
(2)
(1) 1:ornal operatiens crew requirenetits shall suffice for a plant restart within four hours from a plant shudown for which the cause has been clearly established.
i 6.3 FACILIT'.' ST.'.?? QUALIFICATIO!!S
)
6.3.1 Each key supervisory member of the facility staff listed below shall r'et or exceed the minimun qualifications of ANSI N18.1-1971
]
for conparable positions.
a.
Plant Superintendent b.
Assistant Plant Superintendent c.
Cheaistry and llealth Physics Supervisor d.
Operations Supervisor c.
F.cactor Engineer f.
I'.sintenanc'e Supervisor p.
I-sment and Controls' Supervisor h.
Shift Supervisors 1.
E2alth Physicist' PODR ORIGIN
C C
ADMYNISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Coordinator and shall meet or exceed the r'equirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.5 REVIEW AND AUDIT 6.5.1 PIX!T OPERATION REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The Plant Operation Review Committeo shall function to advise the Plant Superintendent on all catters related to nuclear safety.
CO:iPOSIT10N 6.5.1.2 The Plant Operation Review Committee shall be composed of the:
Chairman:
Plant Superintendent Vice Chairman: Assistant Plant Superintendent Mer$ber:
Operations Supervisor Meriber:
Maintenance Supervisor Member:
Reactor Engineer Member:
Chemistry and Health Physics Supervisor Member:
Instrument and Control Supervisor Member:
Health Physicist ALTERNATES 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall be counted for a quorum at any one time.
6-5 9
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ADMINISTRATIVE CONTROLS en MEETING FREQUENCY 6.5.1.4 The PORC shall meet at 1 cast once per calendar nonth and as convened by the PORC Chairman or Vice Chairman..
QUORUM _
6.5.1.5 A qucrum shall consist of a ninimum of five people as
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follows:
The Chairman or Vice Chairman plus four members, or a.
b.
The Chairman and Vice Chairman plus three members.
RESPONSIBILITIES 6.5.1.6 The Plant Operation Review Committee shall be responsibic for:
Review of 1) all procedures required by Specification a.
6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety.
b.
Review of all proposed tests and c::periments that affect nuclear safety.
Review of all proposed changes to the Technical c.
Specifications.
d.
Review of all proposed changes to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical e.
Specifications and preparation of a report covering evaluation and recommendations to prevent reoccurences.
Such Report shall be submitted to the Manager of Operations and to the Chairman of "uclear Safety Audit and Review Committee.
f.
Review of facility operations to d'etect potential safety hazards.
Performance of special reviews and investigations g.
and reports thereon as requested by the Chairman o# the Nuclear Safety Audit and Review Committee.
h.
Review of the Plant Security Plan and imp'lementing procedures and shall submit reccamended changes to the Manager of Security.
6-6 o
O C
ADMINISTRATIVE CONTROLS 1.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Radiation Protection Manager.
AUTHORITY 6.5.1.7 The Plant Operation Pcview Committee shall:
a.
Recommend to the Plant Superintendent written approval or disapproval of items considered under 6.5.1.6 (a) through (d) above.
b.
Render determinations in writing with regard to uhether or not each item considered under 6.5.1.6 (a) through (e) above constitutes an unreviewed safety question.
c.
Provide immediate written notification to the Manager of Operations of disagreement between the P0xC and the Plant Superintendent; however, the.
Plant Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1.
RECORDS 6.5.1.6 The Plant Operation Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Manager of Operatiens and Chairman of the Nuclear Safety Audit and Review Committee.
6.5.2 NUCLE /J. SAFETY AUDIT ASD REVIEW COM'!ITTEC FUNCTICN 6.5.2.1 The Nuclear Safety Audit and Review Committee shall function to provide independent review and audit of all aspects of plant safety. Adequacy of this review and audit is nasured by the cross section of disciplines required of the Committee membership as described in
- Section 6.5.2.2.
COMPOSITION 6.5.2.2 The Committee shall consist of at least six (6) persons:
a.
Chairman b.
Vice Chairman c.
Four technically qualified persons who are not members of the plant staff.
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AD::INISTRATIVE CONTROLS d.
The Committee membership and its Chairman and Vice Chairman shall be appointed by the Yankee Atomic Electric Company Vice President or such person as he shall designate.
Qualifications:
Membership to the Committee requires tha't an individual possess forcal training and/or experience in at least one of the' following disciplines:
a.
Nuclear l'ouer plant Technology b.
Reactor Operations c.
Utility Operations d.
Power Plant Design c.
Reactor Engineering f.
Radiation Safety g.
Safety Analysis h.
Instrumentation and Control i.
Metallurgy ALTERNATES 6.5.2.3 NA CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSAR Chairman to provide additional expert advice, when needed, to the NSAR Committee.
liEETING FREQllENCY The Committee shall hold a minimum of two regularly 6.5.2.5 a.
scheduled meetings per year.
b.
Special meetings may be held when deemed necessary by Company management or by the Chairman of the Committee, or, in the absence of the Chairman, by the Vice Chairman.
2U02D1 6.5.2.6 A quorum shall consist of a minimum of five people as fo.llows :
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_ ADMINISTRATIVE CONTROLS i
i The Chairman or Vice Chairman plus four members, or n.
b.
The Chairman and Vice Chairman plus three members.
Those personnel from the organization reporting to the Manager of Operations shall always be in the minority.
REVIEU 6.5.2.7 The NSAR Committee shall revicw:
The safety evaluation for 1) changes to equipment a.
or systems and 2) tests or experiments completed under the provision of Section 50.59, 10CFR, to verify that such actions did not constitute an unreviewed safety question.
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b.
Proposed tests or exper1ments which involve an unreviewed safety question as defined in Section 50.59, 10CFR.
Proposed changes in Technical Specifications or c.
licenses.
d.
Violction of Technical Specifications and license requirements.
Unusual occurrences and incidents which are reportable c.
under the provisions of 10CFR20 and 10CFR50.
f.
Abnormal Occurrences, as defined in Appendix A, Section E.4 of these Technical Specifications.
Reports and meeting minutes of the Plant Operation g.
Review Committee.
h.
Perform special reviews and investigations and render reports thereon as requested by the Assistant Vice President of Operations.
AUDITS 6.5.2.8 The Nuclear Safety Audit'and Review Committee is responsible for auditing Quality Assurance activities that have a direct effect upon the operating plant.
In areas where oth'er groups normally conduct periodic audits, the Committee may 1) audit those audits;
- 2) perform an independent audit of the same areas; or 3) implement a combination of these methods.
6-9
h ADMINISTRATIVE CONTROLS In areas that are not otherwise audited, the Committee forms a subcommittee to carry out tl.e audit.
The subcommittee reports its findings to the Committee for review.
The Committee will review the results of the audit program at or prior to the next scheduled regular Committee meeting, and will make reconmendations, as are deemed necessary, to the Company Vice President.
Regularly scheduled audits will be performed by the Committee at 3 cast once per two years and will encompass, as a minimum, those areas listed below:
a.
In Plant Audit Program b.
Control Room Plant Operations Log Book c.
Plant Design Changes d.
Engineering Design Changes Action Taken on Material Purchase 6 Sarvice Requests e.
f.
Action Taken on Abnormal Occurrences g.
Action Taken on PORC Recoro.cndations h.
Action Taken in Response to NRC Enforcement Letters 1.
Action Taken on Porposed Changes to the FSAR and Technical Specifications.
AUTHORITY 6.5.2.9 The USAR Committee shall report to and advise the Company Vice President on thote areas of responsibility specified in Section 6.5.2.7 und 6.5.2.8.
RECORDS 6.5.2.10 Minutes of each NSARC meeting shall be prepared and forwarded to the Company Vice President within 20 working days following each meeting.
The meeting minutes shall include, where applicable, reports of reviews encompassed by Section 6.5.2.7; and reports of audits included in Section 6.5.2.8.
The minutes of each regularly' scheduled and special meeting of the Coenittee shall be approved no later than the l
next regularly scheduled Committee meetings.
6-10 l
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ADMINISTRATIVE CONTROLS 6.6 ABNORMAL OCCIERENCE ACTION For abnormal occurrence actions, reference Append,ix A, Section E.4 to Facility License DPR-3.
6.7 SAFETY LIMIT VIOLATIONS 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The provisions of 10 CFR 50.36 (c)(1.)(1) shall be complied a.
with immediately.
b.
The Safety Limit violation shall be reported to the Commission and Manager of Operations immediately.
A Safety Limit Violation Report shall be prepared.
The c.
report shall be reviewed by the Plant-Operation Review
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Committee.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systens or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Linit Violation Report shall be submitted to the Commission, the Nuclear safety Audit and Review Committee and the Manager of Operations within two uceks following the violation.
6.8 PROCEDURES 6.8.1 Uritten procedures and adainistrative policies shall be established, implemented and maintained that meet or exceed the requirencnts and recommendations of Section 5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of USNRC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 below.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the Plant Operation Review Committee and approved by the Plant Superintendent prior to implementation and reviewed periodically ac set forth in each document.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
The intent of the original procedure is not altered.
a.
h.
The change is approved by two menbers of the plant management staff, at least one of whom holds a senior Reactor Operator's License.
The change is docunented, reviewed by the Plant Operation c.
Review Committee and approved by the Plant Superintendent
t h.
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ADMINISTRATIVf CONTROLS 6.9 REPORTING P[EQUIREMENTS For reporting requirements, reference Appendix A, Section E to racility License DPR-3.
6.10 RECORD RETENTIO,N 6.10.1 The following records shall be retained for at least five years:
Records and logs of facility operation covering time a.
interval at cach power 1cvel.
b.
Records and logs of principal maintenance activitics, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
ABNORMAL OCCURRENCE Reports.
d.
Records of surveillance activities, inspections, and calibrations required by these Technical Specifications.
c.
Records of reactor tests and expericents.
f.
Records of changes made to Operating Procedures.
g.
Records of radioactive shipments.
h.
Records of scaled source leak tests and results.
- i. Records of annual physical inventory of all source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
a.
Record and drawing cha.sges reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of nca and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contamination surveys.
d.
Records of radiation exposure for all individuals entering radiation control areas.
Records of gascous and liquid radioactive material released c.
to the environs.
6-12
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ADMINISTRATIVE CONTROLS f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
Records of training and qualification for current members of, g.
the plant staff.
h.
Records of in-service inspections perforced pursuant to these Technical Specifications.
1.
Records of Quality Assurance activites required by the QA Manual.
- j. Records of reviews perforned for changes made to procedures or equipment or reviews of tests ^nd experiments pursuant to 10 CFR 50.59.
k.
Racords of-meetings of the (PORC) and the (NSARC).
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consictent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 RESPIRisTORY PROTECTION ' PROGRAM, (OPTIONAL)
ALLOUANCE 6.12.1 Pursuant to 10 CFR 20.'103(c)(1) and (3), allowance may be made for the use of respiratory protective equipment in conjunction with activities authoriced by the operating license for this f acility in determining whether individuals in restricted areas are exposed to concentrations in excess of limits specified in Appendix D, Table 1, Column 1, of 10 CFR 20, subject to the following conditions and limitations:
The limits provided in Section 20.103(a) and (b) shall a.
not'bc exceeded.
b.
If the radioactive caterial is of such form that intake through the skin or other additional route is likely, individual c::posures to radioactive material shall be controlled so that the radioactive content of any critical organ from all routes of intake averaged over 7 consecutive days does not execed that which would result from.
inhaling such radioactive material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> at the pertinent concentration values provided in Appendix D, Table 1, Column 1, of 10 CFR 20.
6-13
e ADMINISTPATIVE CONTROLS
'For radioactive materials designated "Sub" in the " Isotope" c.
column of Appendix B. Table 1 Column 1 of 10 CFR 20, the concentration value specified shall be based upon exposure to the material as an external rcdiation source.
Individual exposures to these' materials shall be accounted for as part of the limitation on individual dose in $20.101.
These materials shall be subject to applicable process and other engineering controls.
PROTECTION PROGRAM 6.12.2 In,all operations in which adequate limitation of the inhalation of radioactive material by the use of process or other engineer-ing controls is impracticable, the licensee may permit an individual in a restricted area to use respiratory protective equipment to limit the inhalation of airborne radioactive material, provided:
a.
The limits specified in 6.12.1 above, are not exceeded.
b.
Respiratory protective equipment is selected and used so that the peak concentrations of airborne radioactive material inhaled by an individual uearing the equipment do not exceed the pertinent concentration values specified in Appendix B, Table 1, Column 1, of 10 CFR 20.
For the purposes of this subparagraph, the concentration of radioactive material that is inhaled when respirators are worn may be determined by dividing the ambient airborne concentration by the protection factor specified in Table 6.12-1 for the respirator protective equipment worn.
If the intake of radioactivity is later determined by other censurements to have been different than that initially estimated, the later quantity shall be used in evaluating the exposures.
c.
The licensec advises each respirator uscr that he may leave the area at any time for relief from respirator use in case of equipment malfunction, physical or psychological discomfort, or any other condition that might cause reduction in the protection afforded the
- wearer, d.
The licensee maintains a respiratory protective program adequate to assure that the requirements above are ract and incorporates practicas for respiratory protections consistent with those rec.ommended by the American National Standards Institute (ANSI-ZSS.2-1969).
Such a program shall include:
6-14
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1 a ADMINISTRATIVE CONTROLS 1.
Air sampling and other surveys suffi-icnt to identify the hazard, to evaluate individual exposures, and to permit proper selection of respiratory protective equipment.
2.
Written procedures to assure proper seicetion, super-vision, and training of personnel using such protective equipment.
3.
Written procedures to assure the adequate fitting of respirators; and the testing of respiratory protective equipment for operability immediately prior to use.
4.
Written procedures for maintenance to assure full effcetiveness of respiratory protective equipment, including issuance, cleaning and decontamination, inspection, repair, and storage.
5.
Written operational and administrative procedures for proper use of respiratory protective equipment including provisions for planned limitations on working times as necessitated by operational conditions.
6.
Bionssays and/or whole body counts of individuals (and other surveys, as appropriate) to evaluate individual exposures and to assess protection actually provided.
The licensee shall use equipment approved by the U. S.
c.
Bureau of Mines / National Inrtitute for Occupation Safety &
Health (NIOSH) under its appropriate Approval Schedules as set forth in Tabic 6.12-1.
Equipment not approved under U.S. Bureau of Mines / National Institute for Occupation Safety & Health (NIOSU) Approval Schec.ules shall be used only if the licensee has evaluated the equipment and can demonstrate by testing, or on the basis of reliable test information, that the materir.1 and performance characteristics of the equipment are at least equal to those afforded by U.S. Bureau of Mines approved equipment, of the same type, as specified in Table 6.12-1.
f.
Unicss otherwise authorized by the Commission, the licensee shall not assign protection factors in excess of those specified in Table 6.12-1 in selecting and using respiratory protective equipment.
REVOCATION 6.12.3 The specifications of Section 6.12 chall be revoked in their entirety _upon adoprion of the proposed change to 10 CFR 20, Section 20.103, which would make such provisions unnecessary.
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AD:!INISTRATIE
- CT:TROLS 6.13 HICH PC IATION AREA (OPTIO:!AL) 6.13.1 n 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 intemity of radiation a.
is greater than 100 mrem /br but less than 1000 mrem /hr shall be barricaded and concpicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation L'ork Permit and any individual er group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
'c. ~Each High Radiation Area in which the intensity of radiation is greater than 1000 mrem /hr chall be subject to the provisions of 6.13.l(a) above, and in addition locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative centrols of the (Shift Supervisor) on duty.
P00R ORIGINAL
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TABLE 6.12-1 PROTECTICIi FACTCPS FOR RESPIRATORS PRoli Cff0N FAC10RS GUIDES TO SELECTIOT4 0F EQUlFMEtii PARilCULAIES AtiD BUREAU OF filNES APPROVAL SCHEDULES" VAPCRS AND GASES FOR EQUIP : Erit CAPABLE OF PROVIDIt'G AT EXCEPT TRITIU:1 LEAST EQUIVALEiii PROTECTIOri FACTORS (IIh DESCRIPTIOI1 I40 DES 1 OXIDE 3
- or schedule superseding for equipment of type listed I.
AIR-PURIFYIfiG RESPIRATORS Facepiece, half-mask 4,7 fiP 5
21B 30 CFR S 14.4(b)(4)
Facepiece, full 7 tiP 100 21B 30 CFR 514.4(b)(5); 14F 30 CFR 13
'raMa AT".05PHERE-SUPPLYIiiG M RESPIRAT0lt (I]?
i.
Airline respirator Facepiece, half-mask CF 100 19B 30 CFR S 12.2(c)(2) Type C(i) fkh Facepiece,' full CF 1,000 19B 30 CFR S 12.2(c)(2) Type C(i) r.r a Facepiece, full 7 0
103 19B 30 CFR S 12.2(c)(2) Type C(ii)
Facepiece, full PD le000 19B 30 CFR 5 12.2(c)(2) Type C(iii) 15 tif
, Hood CF 5
6
($
Suit CF 5
6 w
w, g:rQ 2.
Self-contained breathing arms apr:aratus (SCBA) h)
Facepiec~e, full 7 0
100 13E 30 CFR S ll.4(b)(2)(i) amen Facepiece, full PD 1,000 13E 30 CFR 5 ll.4(b)(2)(ii) gpys Facepiece, full R
100 13E 30 CFR S ll.4(b)(1)
CC"3It'ATIO 1 RESPIRATOR 4
Any con.bination of air-Protection factor for 19B CFR 5 12.2(e) or applicable purifying and atmosphere-type and mode of opera-schedules as listed above supplying respirator tion as listed above 1,
2, 3,
r, 5,
c ', 7
[These notes are on the following pages.]
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ADMINIRTRAir.'$ CONTROLS i
TABLE 6.12-1 (Continued) 4 I
See the following symbols:
t l
CT:
continuous flow-D: det:nd 4
l UP: negative pressure (i.e., negative phase during inhalation)
PD: pressure demand (i.e., always positive pressure)
R: recirculating (closed circuit) 4 9
-(a)
For purposes of this specification the protection factor is a j
censure of the degree of protection afforded by a respirator, defined as the ratio of the concentration-of airborne radioactive caterial outside the respiratory protective equipment to that inside the equip = ant (usually inside the facepiece) undcr conditions of use.
It is applied to the ambient airborne concentration to estinste the concentration inhaled by the* wearer according to the following fornula:
Concentration Inhaled = Ambient Airborne Concentration Protection Factor (b)' The pritection. factors apply:
(1) only for train:d individuals wearing properly fitted i
. respirators used and maintained under supervision in a i
vell-planned respiratory protective program.
(ii) fer air-purifying respirators only when high officiency (above 99.9 percent removal efficiency by U.S. Bure-of Mines type dicctyl phthalate (DOP) test) particulate filters and/or sorbents appropriate to the hazard are used in at=ospheres not deficient in oxygen.
4 I
(iii) for atmosphere-supplying respirators only when supplied with adequate respirabic air.
3Excluding. radioactive contaninants that present an absorption or submersion hazard.
Ter tritium oxide approximately half of the intake I
occurs by abcorption through the skin so that an overall protection factor of n:t nore than apprcximately 2 is appropriate when atmosphere-supplying raspirators are used to protect against tritium oxide.
Air-purifyingrespiragorsarenet recommended for use against tritium oxide.
See also fc:: note, below, ccacerning supplied-air suits and hoods.
1 i
l'nder chin type only.
Not recommende'd for-use where it might be possible for tha anbient airborne concentration to reach instantaneous values greater than 50 tirses the pertinent values in Appendix B, Table I, Colurn 1 of
- .0 CFR part 20.
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6-18 4
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ADMINISTRATIVE CONTROLS.
5Appropriate protection factors must be determined taking account of the design of the suit or hood and its permeability to the containment under conditions of use.
No protection factor preater than 1,000 shall be used except as authorized by the Commissio6.
6No approval schedules currently available for this equipnent.
Equipment
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cost be evaluated by testing or on basis of available test information.
7Only for shaven faces.
I SOTE 1:
protection factors for respirators, as may be approved by the U.S. Eureau of Mines according to approval schedules for respirators to protect against airbrone radionuclides, may be used to the extent that they do not exceed the protection factors listed in this Tabic.
The protection factors in this Tchle cay not be appropriate to circumstances where chemical or other respiratory hazards exist in addition to radioactive harcrds. The selection and use of respirators for such circunstances should take into account approvals of the U.S.
Eureau of Mines in accordance with its applicable schedules.
50TC 2:
Radioactive contaninants for which the concentration values in Appendix B, Table I of this part are based in internal dose due to inhalation nay, in addition, present external exposure hazards at high concentrations.
Under such circumstance limita ions en eccupancy may have to be governed by external dose limits.
t 4
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1 P90R BRICINA 6-19
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Standard Specification Number 6.2.2 d.
Added qualifying statement that operating crew personnel trained in radiation protection procedures fill this requirement.
Reason: Clarification of this statecent is required to be consistent with facility Organization and continuous shift coverage.
6.5.1.2 Added the position of Vice Chairman.
Reason: Provides needed flexibility to convene the Plant Operations Review Committee in the absence of the Chairman (i.e., Plant Superintendent).
6.5.1.3 Deleted "... shall participate in PORC activities..." and replaced with "... shall be counted for a quorum..."
Reason: On many occasions the participation of additional alternate menbers in PORC activities is desirable.
6.5.1.4 Added Vice Chaircan.
Reason:
Same as stated under 6.5.1.2.
6.5.1.5 Reworded to include the position of Vice Chaircan.
Reason:
Same as stated under 6.5.1.2.
6.5.1.7 c.
Deleted notification of the Nuclear Safety Audit and Review Committee.
Reason: The NSAR Committee is not a line canage=ent function within the Yankee Atomic Electric Cocpany corporcte structure.
Therefore, immediate notification is not required.
6.5.2 Nuclear Safety Audit and Review Cbemittee 6.6 To be subnitted at later date.
Reason:
Yankee Atomic Electric Company, Proposed Change 118, (reference 4) which specifically addresses this specification has,been pending Commission revice since December 1974.
Upon resolution of the Commission's position on Abnormal Occurrences, j
a submittal will be issued to incorporate i
same in the standardized Technical Specification j
hmu.
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h j
Standard I
Specification llumber 6.7.1 b.
Deleted reference to Chairman of the NSARC.
Reason: Same as stated under 6.5.1.7 c.
6.7.1 d.
Changed reporting requirements from 10 days to within two weeks following the violation.
Reason: Two weeks (10 working days) is a more reasonable time frame for the extensive evaluation and preparation of this report.
6.8.3 c.
Changed frequency of review and approval from 7 days to 30 days.
Reason: On a 7 day frequency combined with the number of minor changes required on a day-to-day basis the number of POPC meetings required would be unreason-able.
The 3J tay period is consistent with the frequency requirements of specification 6.S.1.4.
6.9 To be submitted at a later date.
Reason:
Same as stated under 6.6.
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I NRC DISTRIBUTION FOR PART 50 DOCK T MATERIAL l
r (TEMPORARY FORM) 8645 L
CONTROL NO:
^
FILE:
FROM: Yankee Atomic Elec. Co.
DATE OF DOC DATE RECD LTR TWX RPT OTHER Westborough, Mass. 01581 8-11-75 8-14-75 XX
~
E.P. Johnson XX ORIG CC OTHER SENTimC PDR, TO:
NRC 3 signed 37 SENT LOCAL PDR XX CLASS UNCLASS PROP 1NFO INPUT NO CYS REC'D DOCKET NO:
XXX 40 50-29 ENCLOSURES: Attachment A entitled " Tech Specs DESCRIPTION: Ltr notarized 8-11-75 requesting an Aedt to OL/DPR-3/ Tech Spec Change No.130 Paragraph "H" Administrative Controls".....
in order to request for Applicatnt to submit ar (40 cys enel ree'd) applicaton for amdt to its license that changes the administrative controls part of the Tech Attachment.B entitled " Exceptions Taken to th Specs & trans the following:
Standard Tech Specs Administrative Controls"d 1
(40 cys enc 1 rec'd).
PLANT NAME:
Yankee Rowe f ;,,[,,,.
. +..
FOR ACTION /INFORMATION DHL 8-16-75 BUTLER (L)
SCHWENCER (L) ZIEM ANN (L)
REG AN (E)
W/ Copics W/ Copics W/ Copies W/ Copies CLARK (L)
STOLZ (L)
DICKER (E)
LEAR (L)
W/ Copies W/ Copics W/ Copies W/ Copies PARR (L)
VASSALLO (L)
KNIGHTON (E)
SPIES W/ Copics W/ Copics W/ Copies W/ Copies KNiEL (L)
YURPLE (L)
YOUNGBLOOD (E)
Lpx W/. Copies
-W opies W/ Copics W/ Copies I
INTERNAL DISTRIBUTION QC,F I.L E)
TECH REVIEW _
DENTON LIC ASST A/T IN D.
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FNRC PDR SCHROEDER GRIMES R. DIGGS (L)
BRAITMAN.
GDGC, ROOM P 506A MACCARY GAMMILL H. GE ARIN (L)
SALTZMAN
&GOSSICK/ STAFF KNIGHT KASTNER E. GOU LBOURNE (L)
MELTZ CASE-PAWLICKl BALLARD P. KREUTZER (E)
GIAMBUSSO SHAO SPANG LER J. LEE (L)
PLANS _
MCDONALD M. RU3HER00K(1,)
BOYD STELLO
. E NVI R O_.
S. REED (E)
CHAPMAN MOORE (L)
HOUSTON MaetMMLtr) 6 //Wp(
DEYOUNG (L)
NOVAK MULLER M. SERVICE (L)
SKOVHOLT (L)
ROSS DICKER.
WS. SHEPPARD (L)
FG. COUPE GOLLER (L) (Ltr)
IPPOLITO KNIGHTON M. SLATER (E)
PETERSON P. COLLINS TEDESCO-YOUNGBLOOD H. SMITH (L)
HARTFIELD (2)
DENISE J. COLLINS EGAN S. TEETS (L)
KLECKER PEG OPR LAINAS OJECT LDR G. WI LLI AMS (E)
EISENHUT WIGGINTON l
WILE & REGION (2)
BENAROYA gtlark V. WILSON (L)
MIFC VOLLMER HARLESS R. INGRAM (L)
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EXTERN AL DISTRIBUTION
- LOCAL PDR Greenficid, Mass.
1 - PDR-SAN /LA/NY
- TIC (ABERNATHY) (1)(2)(10) - N ATIONAL LABS
.NSIC (BUCilAN AN)
- 1. - W. '3ENNINGTON, Rm E-201 GT 1 - BROOKHAVEN NAT LAB
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