ML19317G812

Amend 2 to License DPR-54,revising App a & App B to Tech Specs Re Administrative Controls.Tech Specs Encl

ML19317G812
Person / Time
Site:	Rancho Seco
Issue date:	12/31/1975
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19317G810	List: ML19317G809 ML19317G812 ML19317G815 ML19317G819
References
NUDOCS 8004010640
Download: ML19317G812 (37)

Text

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UNITEo STATES NUCLEAR REGULATORY COf.*?.'ISSION W ASHINcTofJ, o.

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 2 License No. DPR-54 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The applications for amendment by Sacramento Municipal Utility District (the licensee) dated December 12, 1974 and October 3, 1975, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this mnendment can be conducted without endangering the health and snfety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; and D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

2.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license mnendment and Paragraph 2.C. (2) of Facility License No. DPR-54 is hereby amended to read as follows:

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..s "(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license. The licensee shali operate the facility in accordance with th, Technical Specifications, as revised by issued changes thereto through Change No.

2."

3.

This license amendment becomes effective 30 days after the date of its issuance.

FOR 'IBE NUCLEAR REGULATORY C0hMISSION trtI=I !!g15Y Robert W. Reid, Chief Operating Reactors Branch #4 Division of Reactor Licensing

Attachment:

Change No. 2 to the Technical Specifications 1

Date of Issuance:

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' A'ITACHMENT TO LICENSE AMENDMENT NO. 2 Cl!ANGE NO. 2 TO'Ti!E TECllNICAL SPECIFICATIONS FACILITY OPERATING LICENSE.40. DPR-54 DOCKET NO. 50-312 Remove-Pages Insert Pages 1-5 6 1-6 1-5, 1-Sa, 4 1-6 3-29 6 3-30 3-29 6 3-30 3-33 6 3-33a 3-33 6 3-33a 4-47 6 4-48 4-47 6 4-48 6-1 6 6-2 6-1 Figure 6.2-1 Figures 6.2-1 6 6.2-2 6-3 6-27 6 6-20 2

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^ TECIINICAI. SI ECIFICATIO;;S DEFI!!IT10;;S D.

All automatic containment isolation valves are operable or cloued in the safety features position.

E.

The containment leshage satisfics Specification 4.4.1, and no known channes have occurred.

1.8 REPORTABLE OCCURRENCE Any of the following:

(1)

FailureofthelcactorProtectionSyntemorothersystemn.ubject-to limiting safety-system settings to initInto Lhc rcquired pro-tective function by the tine a monitored parameter reaches the cetpoint specified as the liuiting safet/-nyntem setting in t.bc Technical Specifications or failure to complete the required protective func~ ion.

l (2)

Operation of the unit or affceted systems when any parameter or operation subject to a limiting condition for operation in Jecs conservative than the least conservative aspect of the liuit ing condition for operation established in the Technical Specifica-tions.

(3)

Abnorr.11 degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary contaimnent.

(4)

Reactivity anomalies involving disagreement with the predicted

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value of reac^.ivity balance under steady state conditions i

during power operation greater than or equal to 1.0',ac/e; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the Technical Specifications; short term reactivity increases that correspond to a reactor period of less than 5 seconds or, if suberitical, an unplanned reactivity insertion of more than 0.5%Ae/e; or occurrence of any unplanned criticality.

(5)

Failure or malfunction of one or more components wlich prevents or could prevent, by itself, the fulfillment of the functional i

requirements of systen:(s) used to cope with accidents analyzed j

in the SAR.

(6) personnel crror or-procedural inadequacy which prevents or could prevent, by itacif, the fulfillment of the functional requirc-ments of systen(s) required to cope uit.h accidents analyzed in the SAR.

l (7)-

Conditionn arining from natural or manmade events that, as a direct result of the event, require plant shutdown, operation of

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safety systems, or other protet.tive measures required by Technical Specifications.

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(8) rrrors dit: covered in the trannient or accident analynen or in tin-nethoda used for such analyne:, an described Ju the naret y analyni:.

report or in the banen for the Teclutical Specificatienn Ihat have or could have pernitted reactor operation in a manner Jet n con-servative than annuued in the anaJynen.

(9)

Performnce of ctructuren, nyctern, or cor.ponentn that requiren reuedial act. ion or corrective ricanures to prevent operation in a nanner }ecs cohnervat ive than that arner.:ed in the accident analynen in the safety analysin report or Technical Specification banen; or discovery during, plant life of conditienn not specifi-cally considered in the safet y analynin report er Technical Speci-fications that require remedini action or corrective r::acuren to prevent the c::intenec or developnent of r.n unnafe condition.

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1.9 Tn's pn!nons i

- A time period covering 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, three chif ts equally dividing j

1.9.1 Shift a 24-hour tirac pericJ.

1.9.2 lb_i ll - A tir.c period within a 24-hour span frou 0000 to 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> frou 1:anday through Sunday.

1.9.3 1.'ce!:1y-A tiac period fron lionday through Sunday spaced to occur 52

,, tines a year.

r IPOORQUALIT THIS DOCUMENT CONTAINS i

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RANOHO SECO UNIT 1 TECHNICAL S?ECIFICATIONS '

Definitions-

~ 1.9.4 1:onthly --A' time period from the first to last' day of a' calendar month-spaced to occur 12 times a year.

- 1.9.5 Quarterly.- A time"perfod of three. calendar months spaced to' occur four times;a year..

i" 1.9.6' semi-Annuni'- A time' period from January 1 and July 1 covering the I

subsequent sir montps.

1.9.7 Biannually - A time' period of 24 calendar months spaced to occur once j

in two years.

1.10 SAFETY s

Safety as used in these Technical Specifications shall mean nuclear safety and shall encompass all systens and conponents that have or any have an effect on-l~

the health and safety of the general public.

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TABLE 3.5.1-1 (Continued)

INSTRUMENTS OPERATING CONDITIONS (C)

(A)

(B)

Operator Action if Minimum Operable Minimun Degree Conditions of Columns A Functional Unit CWds d I'.edundancy and B Cannot be Met Safety Features

• b.

Re:ictor Building pressure Bring to hot shutdown instrument chan,nels 2

1 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

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Manual pushbutton 2

1 Bring to hot shutdown m

@2 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> o

n 2.

Low pressure injection 5g l> c a.

Reactor coolant pr,cssure 2

1 Bring to hot shutdown ro instrutnent channels within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Qm m

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b b.

Ranctor Building pres-Bring to hot shutdown sure instrument channels 2

1 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> I r-0%

.c.

Manual pushbutton 2

1 Bring to hot shutdown pOq within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> a ga n -,

3.

Reactor Building spray pump p f3 e2 a.

Reactor Building pres-Bring to hot shutdown n

sure instrument channel 2

1, within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> o

a.

b.

Manual pushbutton 2

1 Bring to hot shutdown p

within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> p

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• If minimum conditions are not met within 48 heurs af ter hot shutdown, the unit shall be placed in a cold shutdoun condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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s TA3LI 3.3.1-1 (Cencinded),

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INSTRU:2NTS OFIRATING CCNDITIONS (A)

(3) 4 Mini =un Operable Enimun Degrec

. Operator Action iR Cenditiens of Functioncl Unit Channels of Kcd=dancy Colum s A e d 3 Ccnnot Sc Met l

e Scfety Features *

4.. Reactor Building sprcy velve a.

Eccctor Building pres-2 1

BrinS to hot shutdeva

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within 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> g

sure instruncat ch5nnel I,

2 1

Brins to hot shutdcrn I'

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[.,3 Process Instrumentation 2'

N.A.

Bring to hot shutdern

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?rcssurirc: Level.

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• If mini =um conditions are not net within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter hot shutdown, the unit shall be placed in

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Ei~i a cold shutdown condition within en cdditional 24 licurs.

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?m RAT'CHO SECO UmT 1 TECHiliCAL SPECINCATIONS Limiting Conditions for Operation -

D.

Uhenever the reactor is.hrought to hot shutdown pursuant to~

3.5.2.4a(3) or 3.5.2.4c above, cubsequent reactor operation is permitted for the purpose'of measurement, testing and correc-tive action provided the thermal power and the power rangc'high-

. flux setpoint allowahic for the reactor coolant pump combina-tion ~are restricted by a reduction of 2; percent of maximum allowable power for each 1 percent tilt.'1 E.

-Quadrant power tilt shall be. i.Atcred on a' minimum frequency of once every two hours during power operation above 15 percent of rated power.

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3. 5. :' 'i Control Rod Positions A.

Technical Specification 3.1.3.5 (safety rod withdrawal) does not prohibit the exercising of individual nafety rods as required by tabic 4.1-2 or apply to inoperabic safety rod limits in Technical Specification 3.5.2.2.

B.

Operating rod group ov'erlap shall bc 25 percent +5 percent between tua sequential groups, except for physics tests.

C.

Except for physics tests or exercising control rods, the con-trol rod withdrawal limits are specified on figure 3.5.2-3.

If the control rod position limits are exceeded, corrective neasuren shall be taken immediately to-achieve an acceptable control rod ponition. Acceptable control rod positions shall then be attained within two hours.

D, Except for physics tests, power shall not be increased above the power 1cvel cut-off of 94 percent of the maximum allowabic power Icvel unless one of the following conditions is satisfied:

(1)

Xenon reactivity is within 10 percent of the equilibrium value for operation at the maximum allowable power level and asymptotically approaching stability.

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-(2)

Except for xenon free start-up, when 3.5.2.5d(l) applies, the reactor has operated within a range of 89 to 94 per-cent of the maximum. allowable power for a period exceed-ing 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in the soluble poison control mode.

L5.2.6 Reactor power' imbalance shall be monitored on a frequency not to exceedLtwo hours during power operation above 40 percent rated power.

Except-for physics tests, imbalance shall be maintained within the envelope defined.by figure 3.5.2-2.

If the imbalance is not within the envelope' defined by figure 3.5.2-2,-corrective measures shall be taken to' achieve an.acceptabic imbalance.

If an acceptable imbalance is not achieved within two hours, reactor power :

shall be reduced until. imbalance limits are set.

2 3-33

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9 llANClio SECO UNIT 1

• 'f-TECilN1 cal. SPEC 1FICATIONS Limiting Conditions for Operat f.on 3,5.2.7 The control rod drive patch panels shall he 3nched at all times wit h limited access to be authorized by the superintendent or his designated reprenent:itive. l

__ Danes The power 'nbalance envelope defined in figure 3.5.2-2 is based on 1.0CA analyser which have defined-the maximum J incar heat rate (nee figure 3.5.2-3) unch that.the ma:< imum clad tenperature will not exceed the Interim Acceptance Criteria.

Operation out91de that would "aune of the power imbalance envelope alone does not constitute a situation the Interim Acceptance Criteria to be exceeded should a 1.0CA occur.

The power imbalance envelope represents the boundary of operation limited by the Interim Acceptance Criteria only if the control rods are at the position limits an defined by figure 3.5.2-1 and if a 4 percent quadrant power tilt exists.

Additional conservatism is introduced by application of:

A.

Nucicar uncertainty factors.

B.

Thermal calibration uncertainty.

C.

Fuci densification effects.

D.

Hot rod manufacturing tolcrance factors.

'The 30 percent overlap between successive control rod' groups is allowed since the worth of a rod is Jower at the upper and lower part of'the stroke.

Control rods are arranged in groups or banks defined as follows:

Group Function 1

Safety 2

Safety 3

Safety Safety 4

5 Regulating 6

Regulating Regulating 7

8 APSR (axial power shaping bank)

Control rod groups are withdraun in sequence beginning uith group 1.

Group _5 is The normal overlapped 25 percent with groups 6 and 7, which operate in parallel.

position at pouer is for groups 6 and 7 to be partially inserted,

'The minimum availabic rod worth provides for achieving hot shutdown by reactor e

trip at any time assuming the highest worth control rod. remains in the full out position. (1)

Inserted rod groups during power operation will not contain singic rod worths greater than 0.65 percent Ak/k. This value has been shown to be safe by the (2)

A single innerted cafety analysis of the hypcthetical rod ejection accident.

c:ntrol rod worth of 1.0 percent Ak/k at beginning of life, hot, zero power w:uld result in the same trannient peak thermal power and therefore the same

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environmental conscquences 'as a 0.65 percent Ak/k ejected rod worth at rated

.- power. -

3-33a

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TECittilCAli ;PEC11'1 CAT 10:15 4.') 4 sal'ETY SYSTE:3 IP n!:AUf.1C. Sf:UP,nEnG.

Ajm),f enhil i t,y, Applien.to all hydrahlic nnubber,n inntalled on nafety rc3ated systemn.

O! )ect ive 3

To verify that the hydraulic cnubbern uill perform their denign function.

,fgeci fi ca t i on

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1.

Thone hydraulic anuhbers accensible during p3 ant operation cha31 bc inspected for proper reservoir oil level and evidence of Icahene

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monthly.

Those hydraulic nnubbers not accencib)c during plant operation ll chall he innpected for proper reservoir 3cvel and evidence of-]cahanc

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quarterly.

Any unita nhouing evidence of oil leahanc chall he din-h assenbled and cauce of J eahanc determined.

If the caune is deternined j

to be neal degradation, all unita c::poned to a nimilar or harcher 4

atnosphere shall be dinnsnembled and scain and fluid replaced in accordance 5'th the nanufveturcr's inntrucrioun, i

2.

Af t er the fif t.h year of operation, at 3 cant one jinit containing cthelene propy3cne non]c and one unit containiiq.,polyurethanc-scals, which are exposed to'the nant adverne environnent (: adiation and tecperaturen),

chall he dinannethled and ceal rateri:.1 physical properties evaluat.d.

If physical properties n'oted indicate neals are approaching-end.of uneful 1

1.if e, as reco:= ended by snubber manufacturer, all snals in units-in a nimilar alcoophere shal) he replaced not later than the ucxt refuM ing in t.crval.

In addition, if seal replacement in necessary, per above requirceents, sampic units from arcan having lens barnh environt.mnt shall be disant: cabled and need for t. cal replacement determined.

3.

If current tect progrann or operating experience proven that the continua-tion of this inspection progra:a in not required, this ocction of the

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Technical Specificationn (4.3 4) vill ~ be dcJeted.

Juntification.for this acticn ufil be submitted to the AEC in a npocial report.

11anin The useful-life of: the nea's and fluidn being used in :ot nou knoun.

This nurveillance program will monitor neal condition and ve.-ify ability of

.nuubhe'rc to: perform intended'denign' function.

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J RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 4.15 RADIOACTIVE Ma?i' RIM S SOURCES Applicability App 11cs to the radioactive materials source leakage test.

Objective i

To verify that the boundary materials to contain radioactive sources does not exceed allowable limits.

Specification 4.15.1 The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive naterial on the test sample.

If the test reveals the presence of 0.005 ulcrocuric or more of reuovabic contan-ination, it shall imediately be withdrawn f ro:a use, decontauf nat<:,

and repaired, or he disposed of in accordance with Comnission regulations.

Scaled sources are exempt fron such leak t;csts uhen the source contains 300 microcuries or less of beta and/or ganna emitting caterial or 10 microcuries or icss of alpha cnitting material.

4.35.2 Tests for leakage an.1/or contanin., tion shail be perforced by ib; licenace or by other persons specifically authorized by the Cormission or an agreement state, as follous.:.

' Each scaled courec, except startup sources subject to core flux, a.

containing radicactive material, other than hydrogen 3, with a half-Jife greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at inter-vals not to exceed six months, b.

The periodic 3cak test required does not apply to sealed sources that are storc'd and not being used.

The sources excepted from this test shall be tested for leakage prior to any use or trans-fcr to another user unless they have been leak tested within six conths prior to the date or use or transfer. 'In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer, scaled sources shall not be rut into use until tested.

Startup sources shall be leak tested prior to being subjected c.

to core flux.. If any repair or naintenance is perforced on the startup source se 1 boundary, and additional rctest shall be-perfo r=ed.

Bases The objective of this speciffcation is to assure that leahage from byproduct, source, and special nuclear radioactive material sources does not exceed allouable-licies.

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4-48

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6.0 Al).'lli:1STI:ATI VC CD':T!:of.S 6.1 1:ESPO::ST):1LITY 6.1.)

The Plant Superint.endenf chall be renponnibic for overall f acilit y operat ion and shall deletpit e in writing the nucce:.nion to thin responnibility durfug hic abnence.

6.2 011GA':1%ATIO::.

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6.2.1 The offnite organization for faeility management. and technical support chall be au shoun on figurc 6.2-1.

e FACT 1, TTY ST/.FF 6.2.2 The Facility organization shall be as r.hown on Figure 6.2-2 and:

a.

Each on duty nhif t shall he cor.: posed of at leant the uinimum shift crcu compacition chown in Table 6.2-1.

3 b.

At 3 cant one licensed Operator shall be in the control roo, when fuel is in the reactor.

At least two licensed Operatorn nhall be present in the control c.

room during reactor start-up, ra.heduled reactor shutdown and during recavery from reactor trips.

d.

An individual i,ualified in radiation protection proceduren chall be on site when fuel is in the reactor.

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ALL CO!!E ALTEllATIO!!S af ter the initial fuel loading chall be c.

directly supervised by either a if cenned Senior llenctor Operator or Senior 11cactor Operator limited to Fuel llandling who has 'no other concurrent renponsibilitics during this operation.

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TECllNICAL SPECIFJCAT10;iS TA):LE 6.2-1 S111FT CPLU PERSC: DEL AMD LICEMSE REQUIRE 'E!!TS***-

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PIACTOR'M0DE COLD OTl!ER 'J11 AN.

PJ.1:Cif0 SECO J0!! TITLE COLD S11UTD:f::1 S1RTTD0'.':!

1-SL 1 - SL Shift Supervisor 4

Sr. Control Moon Operator or 2 - L*

1-L Control Roo:a Operator Auxilidry Operatur or 1

1 Equipuent Attendant.

Equipennt Attendant or 1

Pca cr P3 ant He3pcr Mininn::t Total Personnel 3

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00nc licensed operator when the reactor is chutdcun greater than 1%

AM/K.

crc,3 in abrent or

' *In the event that any mother of a minimum shif t 11ncapccita*.cd due to 131nens or injury, a qualified replacement shall be designated to report onsite uithin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

SL - AEC Senior Licensed Operator L - AEC Liccused Operator

• • • Until such a time-as the ntartur *:csts and warranty run are corp 3 cted,

nne examinations have successfully and sufficient " hot" operator.I' completed to provide the shif t ncaffing as indicatrid on figure _6.2-1, five personn, includ-cach operatiut; shif t shall censist _ of at least ing at Icast one licensed senior reactor. cperator, one licenacd reactor operator,' and one or more senior-staff penbers fron either the Plant-Staff, qualified members oi-'the Generation 'Ent,ineering Staff, or !!SSS vendor's staff or connultants, uho, by; virtue of -

their Ltraining and experience cua_ provide compercut technical cupport This staff member w131 for. the startup and power ascension' program.

not be required when the reactor in shtitdown hy snore than 1% A!'/K nor uhen the full compliment of three licensed operatorn is available.

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Ab._il_l_l:I STI:ATI VI: CO:!TP0f.S 6.3 FACILITY STAFF Ot:A1.T,1]ICAT10:lfi 6.3.1 rach member of tho' operating ntaff shall meet-or exceed t.he minin.um qualifications of AI!SI !!)S.1-1971 for couparabic ponitions.

1 6.4

~ Tl!A11111 G '

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6.4.3 A retraining and replace:::ent training program for the operating i

staf f tahall be maintained under the direct. Ion of t he Training Supervicor l

and t: hall ccet or exceed the requirements and reco:.mendat Jons of Section 5.5 of A!!S1 n18.1-1971 and Appendix "A" of 10 CFR Part $5.

~

l 6.5 REVIF.U At:1) AUl)TT

,6_. 5.1 Pl.A::T nEVT1:U Comf TTrE (PnC)

FUl:CT10::

6.5.1.1 The Plant Review Co:=nittee shall function to advise the Plant Superintendent on all matters 'clated to nucicar safety.

COMPOSITIO:1

~

l 6.5.1.2 The P3ani Revicu Comittee shall be composed of the:

Chairman:

Technical Ascistant Member:

Ascistant Superintendent Nuclear Plant Operations l

Member:

Assistant Superintendent Technical Support.

Member:

Maintenance Supervisor Member:

Chemical and Radiation Suluc.v1=or Other membern as the Plant Superintendent may appoint from time to tinc.

ls 6-3 4

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A1):111:1r.TRATIVE CD::THOI.S A1. ten!!ATTS 6.5.3.3 Alternate incebern shall.bc appoint ed in uriting by 1.hc Plant Super-intendent t o serve on a temporary hanin; however, no more than tuo alt ernat en chall participate in PRC act.ivii.ics at any cine titae.

)!P.ETTI C Pni:011C? CY

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6.5.1.4 The PRC nhall ucet. at leant once per calendar i.:onth and an convened by the PRC Chairman.

,UORU:i Q

l 6.5.1.5 A Quoruu of the PRC r. hall consist of ti. Chairman and Luo ucmbern including alternaten.

l l

1:ESPONSi r.TT.1 TIES i

6. 5.1. 6 Tiic Mont Review Co:miit Lee.shall be renponnibic for' pcvicu of 1) all procedtare:. required by Specification 6.8 and n.

changen thereto, 2) any oth:r proponed procedures or changen t.hcreto as deteruined by the Plant Superint.cndent to affect nuc1 car safety.

b.

Revicu of all propoced tests aid experirecnts that affect nucicar safety.

Revicu of'all proposed changes to the Technical Specificationn.

c.

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d.

Revicu of all proposed changen or modifications to plant systems.

or equipment that affect nuc1 car safety.

1 Investigation of all violations of the Technical Specificationn

.c.

and nhall preparc and forward a report covering evaluation and

^

recommendations to prevent reentrence to'the P3 ant Superintendent and'to the Chairman of the 11anagement Safety Revicu Committee.

Revicu of facility operationn to detcet potential cafety.hazardn.

f.

Performance of special revicu:: and invectigationn'and reports g.

thercon an' requented by the Chairman of the 14anagement. Saicty Revicu Committee.

l 6-4 m.

. a ;*

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/dh!IllTSTEATIVE CO.!;TROI.U nnsponsir.11.1TTr.S (coneinned)

I h.

Revicu of the Plant Security P1nn and inipicmention ptoceduren nnd chall nuhoit recon:acuded changes to the Chairman of the Ifanagement Safety Revieu Co:amit Lee.

1.

Revicu of the Emergency: Plan.and impicmentinn proceduren and chall anhni.t reconmended changen to the Chairman of the llanagement Safety nevicu CoccItiec.

/.UTHORITY 6.5.1.7 Tbc Plant Revicu Co:maittee chall:

Recom:nend to the Plant Superintendent uritten approval or n.

dinapproval of itcun considered under 6.S.1.6(a) through (d) above.

Render determinat.ionn in siriting with regard to whether or

h.

• not cach item connicered under 6.5.1.6(a) through (c) above conutit utes an unrevicued caf ety question.

Provide immediate uritten notiff ention to the Chairman of t.hc

c..

lianancment Saf ety nevieu Conmit tee of disagreement between. thu

.' PRC and the Plant Superintendent; hv.inver, the Plant Superin-tendent r. hall have renponsibility for resolution of cuch din-agreements purcuant to 6.5.3.1 above.

ECConDS_

The Plant nevicu Committee chall maintain written ninuten of each 6.5.1.8 necting and copiec chall be provided to the Plant Superintendent and the Chairman of the 1:anagement Safety nevicu Committec.

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_Iti:CTIO:!

The !!anar,cment Safety licef eu Cormitt ec r.ha11 ' function to provide 6.5.2.1

' independent rc.riew and.nudit of decignat.ed activitirm in the arcan of:

a nucicar pouer plant operationn n.

2 b.

nucicar cuginecrin:1 chemistry and radiocheraintry c.

~

d.

uctallurgy'

$notrumentation and control c.

f.

rad'iologien) cafety Occhanien1 and elect.rical engineering g.

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. CO';POS1T10:: -

6.5.2.2 :Tlic !!bic nhall be componed of the:

Annintant Ccueral !!ananer and Chief En;;1ucer - Chairman

- Technical AnninLant - !;ecrctar/

!!anager, Engineering Depart nent Ar nintant. General : tanager, Operations llanat.nr,1:uclear Operat ionn

- Supervining Muclear Eny,ineer Itanager, Generat.f on Engineering -

Quality Annurance Director Quality Arinurance Engineering A1.TER :ATES 6.5.2.3 Alternate members chall be appointed in writing by the ISRC Chairican to serve on a temporary banic; however, no reoro than two alternat.iven chall part'icipa:c in 1ISRC activitics at any one time.

CO:? SUI.TA1:TS 6.5.2.4 Connu3 tanto chall be utilized an det ertdncd by the liSRC Chairman to provide crport advice to the !!SRC.

1 EFT 11:C TRF.Oll'.I:CY 6.5.2.5 The ::SRC cha31 r:cet at least. once per calendar quarter during the initial year of facility operation follouing fuc1 loading and at Icast once per ci>: months thereaf ter.

' 30 hurt 6.5.2.6 A quorum of liSRC nhol) consist of the Chairman or.his designated alternate and a majority of the !!Snc menhern including alternates.

1:n more

.than a' minority of Llic. quorum chall 1,iave line responsibility'for operation of the facility.

6 0

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Ab:tininTnATtyn cnNTnnt.n -

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6. 5. 2. '/ The !!SRC chall review:

4 The safety evaluationn for 1) channen to proceduren, equipment

n. 'or nyuteun and 2) tcutn or experimenen ecmpleted under t.he provision of Section 50.59, 10 CFR, to verify that noch actionn did not constitu}:c an unrevieued cafety quention, b.

Proposed channen to proceduren, equipnent or nynteir; ubich favolve an unrevicued safety qucntion an defined in Section 50.59, JO CFM.

Proponed tents or experinenen which involve an unrevicued c.

safety question an defined in Section 50.59, 10 Cru.

d.

Proponed channen in Technien) Specificationn.or licennen.

c'.

Violationn of applicahic ntatuten, coden, regulationn, ordern, Technical Specificationn, licc nne requiretrents, or of internal proceduren or instructions having nuclear safety ninnificance.

Significant operat.ing abnorr.nlitien or deviations from unrt,n1 f.

tiuclear nd expected periorinnec of plant; equipment that affect narety.

REPORTABLE OCCURRENCES, as defined in Section 1.8 of these g.

Technical Specificctions.

h.

Any indication of an unanticipated deficiency in nome anpect of denign or operation of saf ety related structuren, nystems, or components.

R'. ports and necting ninutes of the Plant Review Committee.

1.

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AD:!!!1TSYl!ATTVC CO:*TI:0I.S AU

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6.5.2.8 Auditn of facility activitien nhall be performed under the cognizance of the 1:SRC. - Ther:c audita chall encompans:

a.

The confornance 'of facility operation to'all provinf ons contained wit hin the Technical Specificationn and applicable licence conditionn at Icast once per year.

b.

The performance, training and qualificationn of the entire facility staff at leant once per year.

c.

The results of all act.Joan taken to correct deficienciec occurring in facility equipment, ctructuren, syntent. or met. hod of operation that affcet nuclear cafety at 1 cant once per ni>: months, d,.

The performance of.all activities required by the tluality Acnurance Progran to incet t he criteria of Appendix "15",

10 Crli 50, at leant once per uro yearn.

The racility Eucrgency Plan and iuplementit a procedut es at c.

1 cast once per txo yearn.

f.

The racility Security Plan and SEplementing proceduren at least once per tuo years.

g. - Any of her area of f acility operation conside' red appropriate.

by the liSRC or the General !!anager.

AUTl!On1TJ 6.5.2.9 The 1ttnC chall report to and advise the General 14anager on those arcac of responsibility cpecified in Section 6.5.2.7 and 6.5.2.8.

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o Alt!!!!)STPATIVC CfE T!*.ff!.S

1:1:C0ltDS 6.5.2.10 Recordn of 1: Site activitren chall he prepared, approved, and distributed as indJented below:

!!1nutcu of each itSitC incering chall be prepared, approved n.

and forvarded to Ihe Cencral !!anager ulthin 14 dayn-follouing each veeting.

b.

itcport n of revievn enco:npanned by Sect Jon 6.5.2.7 c, f, g, and h shove, sha)) be prepared, approved and forwarded to the General !!anager uit.hin 14 days f ollcuing completJon of the review.

Audit reports ence:apanced by Section 6.S.2.8 above, shall c.

be forwarded to the General : tat.ager and to the r.innagertent posit ionc renp<,nnibic f or t he arcan audit ed within 30 dayn after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The fo))o.dng acticmn shall be taken in the event of a REPORTABLE

'OCCURRP.::Ci :

3 The Co:rainnion uhall be notified and/or a report submitted a,

~

pursuant to the requirer.icntu of Specification 6.9.

b.

Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the pnC and submitted to the !!SRC and the P3 ant Superintendent.

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6.7 SArirrY I._1!!_lT VIDI AT,1,0g 6.7.1 The follouing actionn nhall be tal:en in the event a Safety Linit in violated:

The provinionn of*30 CFR 50.36 (c) (1) (i) shall he conplied

~

n.

vith immediately.

The S.ifety Linin violation nhn11 he reported to the Plant Super-b.

intendent, the Chalinan of the liSRC and t o the Comminuf on imued -

S.atc3 y.

A Safety Liuit Viniation Report chall be prepared.

The report t

c.

chall be revicued by the Pl:C.

This report shall dencribe (1) applicabin circur:tancen preceding,the viointion. (2) ef fects of the vjolation upon f acility component s, nyntemn or ntructuren, and (3) corrective acetion t ahen to prevent recurrence.

d.

Thn Safety Limit VJolation Report shall be nuhmitted to the ComnJntinn, the 1:S!:C and the PJant Superintendent within 10 dnyn of the violation.

6.8 PROCEDURES 6.8.1 h'ritten procedures shall be established, implemented and cain-tained covering the activities referenced below:

The applicable procedures recommended in Appendix "A" of a.

Regulatory Guide 1.33, November 1972.

b.

Refueling operations.

c.

Surveillance and test activitics of safety related equipment.

d.

Security Plan implementation, e.

Emergency Plan implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PRC and approved by the Plant Superintendent prior to implementation and reviwed periodically as set forth in each document.

'6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

Theiintent,of the original procedure in not altered.

n.

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b.

The change in approved by two members of the plant nanagement staff,at Jeant one of whou holdn a Senior Reactor Operator's Licence on t he unit af fected.

The channe 'is docunented, revic ted by the PRC, and approved

~

c.

by the Plant Superintendent within 7 dayu of implementation.

6.9 REponT11:0 nrottlurMr.::TS i ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 Infortntion to be reported to the Com:nin:: ion, in addition to the reports ter;uired by Tit le 10, Code of Federal 1:enulationn, shall he in accordance uit h the Rey,ulator'; Ponit Jon in Revinion 4 of Regulatory Guide 1.3 6, " Reporting of Operat.ing Inf ornt?t ion - Appendix "A" Technical lipecifi-cationn."

SPECIAL REPO_RT_S Special reportu nhall be submitted to the Director of tite Renulatory 6.9.2 Operations Regional OClice within the Linc period r.pecified for cach report.

Thenc report a chall be cuhmitted covering the activitics identified belou purt.uant to the requirements of the app).icabic reference specification:

A.

Stnrtup Report A cummary report of unit utartup and power ccenlation testing-and an evaluation of the results from these test programs chall be submitted within 60 days following commencenent of commercial pouer operation.

The test resus.ts chall be compared uith denign predictions and specifications.

15.

A Reactor P,utiding structural integrity report shall be nuhmitted within 90 days of completion of each of the follouing tents cover'ed by Technical Specification 4.4.2 (the integrated leak rate test is covered in Technical Specification 4.4.1.1).

.1 Annual Inspection

.2 Tendon stress surveillance

.3 End anchorage concrete surveillance

.4 Liner plent curveillance

- C.

. Inservice Inspection Program.

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AD:11MT :Tl:ATTVE CD:: TROL.S 6.10 RECORD Hl.TENTION 6.10.1 Tho' follot:Ing records shall be retained for at least five years:

Recordn and logn o[ facilit.y operation covering tiue interval a.

at cach poter Icycl.

b.

Records and logn of principe.1 maintenance activitica,-innpcctionn, 2 epair and replacement of principal iLens of equipment related to nucicar safety.

c.

REPORTABLE GCCURRENCE Reports, d.

Recordn of nurveillance activitics, ing.pectionn and calibrations required by thenc Technical Specifications.

Ecccrdn of reactor tents and experirents.

c.

f.

Records of changen nr.de t o Operating precedures.

2 C.

Recorda of radioactive shipments.

h.

Records of scaled souce 1er.h tests and resultn.

i.

Records of annual physical inventory, of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the racility Operating License:

Record and drawing changen reficcting facility design modifi-n.

cations nado to systems and equipment described in the Final Safety Analysis Report.

W

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.An..M_1 :1 S..T!: A_TI.V..M. Cn.:.:.TI:0.!..S._.

.b.

Recordu of'ncu and irradiated fuel invent ory, - fucJ t rannfer:

and asnenbly burnup hintoric;s.

c.

Records of facility radiation and contamination curveyn.

d.

Recordn of radiatilan cxposure for all ind tviduals entering radiation control areas.

c.

Records.of naccoun and liquid radioactive natorial relcaned to the environn.

-f.

Recorda of trannient or operational cyclen for thone faci 3ity componente denigned for a limited number of transicatu or cycles..

g.

Records of training and qualification for current members of. t.hc plant operating staff.

h. _ Recorda of in-service inspections performed pursuant. t o thene Technical Specifications.

1.

Records of Quality /scolirance acti.itica required by the QA llanual.

j. ' Records of revicun perf ort:cd f or changen vide to proceduren or equiptnnt or revicus of testa and experiuents parcu :nt to 10 CFR 50.59.

h.

Recordsofnyctingsof1.hcPRCandtheMSKC.,.

_6.11 RA11IATION PROTECTION PROCRA'1 Procedures for pcrnonnel radiatio,n protection shall be. prepared consistent uith the requirenents of 10 CFR Part 20 and.nhall be approved, nnintained and adhered to for all operations invoiving personnel radiation exposure.

6.12 RESPIRATORY PROTECTION PROGRAM AL1,Ok'ANCE 6.12.1:

Pursuant to 10 CFR 20.103(c) *(3) and (3), allowance irny be made for the usc' of renpiratory protective equip =cnt 'in conjunction with activitico authorized by the operating license for thin facility in deter-

~ mining ubether individuals in rentricted arcan arc cxposed' to concent.rationu

~

in excens of the limits specified in Appendix E, Tabic I, Column 1, of 10 CFR 20, subject to the follouing conditions and limitations.

The Jimita provided in Section 20.103 (a) and (b) shall. not be u.

' exceeded-6 -

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- AD'1T!!ISTRATTVP. CO::T!:01.S '

A1.1.OUA1, CF. '(Coa 1 inyel,)l h.' If t@c radioactive ~ unt.crial in of noch form t. hat. -intahe_ through

.tho' skin or other additional. route is.]ihely, individu:1 esposuren to; radioactive mat qrial r, hall be controlled no that t he. radioact Ive content. of any crit ical organ f ron all routen of int.ahe averaged over 7 connecutive days docn not exceed Lhat which would. renult*

from inhaling nuch radioactive mterial for 40 honrn at; the pnr-tincut ~ concentrat' ion valuen provided in Appendix D, Table. I,- Coluna 1,.of 10 CFn 20.-

a For radioactive eaterials designated Sub" in the " Toot ope" column c.

of Appendix li, Tabic 1, Column 1 of 10 CFn 20, the concentration value specified r.ha.11bc hased upon enpocure to the natorial an 1

an external radiation nource.

Individual expecuren.to thena-nat-crials shall be accounted for an part of the limitation,on individ-ual donc in !i20.101. ' These materia]n cha31 be subject to applicahic proccan and other engineering contro1n.

2 PROYCCTIG:: pn0CM" in all operationn in which adequate limitation of the inhalation of 6,12.2 radioactive naterial by the use of proccan or other engineering controls in impracticabic, the licennec may pernit an individ6al in a restricted aren to to linic t.hc inhalation of airborne une renpiratory protective equipment radioactive material, provided:

The limits specified in 6.12.1 above, are not execeded.

a.

b.. Respiratory protective equip:ent is nelected and used so that

_ the peak concentrations of airborne rcdioactive natcrini inhaled by an individual wearing the equipment do not execed the pcrt.in-ent concentration valuen specificd in Appendix B, Tabic T, Coltuun li_of 10 CFn 20.

For the purponen of this nubparagraph, the-concentration of. radioactive material that in inhaled when ren-pirators arc' worn may be determined by dividing the" ambient. air-borne concentration by the protcetion factor specified in Table If the 6.12-1 for'the renpirator protective equipment worn.

intake of radioactivity in later determined by other nensure-ments: to have been dif ferent t.han that initially estimated, the

~

'later quantit.y shall be used in evaluating the exposures.

~

The licensec advinen each.rcspirator uner that he may leave the arca at any time for relief from renpirator une in' case of equip-c.:

or any ment malfunction, physical or psychological discomfort,

.other.condit. ion that might enune reduction in the protection afforded t.hc wearer.

The licennec'maintainn'a:rcspiratory protective program adequate

.'d,

to annure;that the requirementn above are met and incorporater.

b-15. -

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.,.-s AD!ill!1ST!!ATIVE CD':Tl:Ol.S Pitorl'.CT1_01: PI:0Gl:A:-t (Cent inued_)

pract.$ cen for renpiratory protection concint ent wi t h thouc recommended by t he A:ncrican !!at f onal St andardr. 'innt.itute ( A:'S1 -

' 7.8f t. 2-1969).

Such a progrnia nhall inc3nde:

.1 Air nauplinn and other nurveyn sufficient to identify the

. hazard, to evaluat e individual exponuren, and t o pernit proper belect.Joa of renpirat.ory prot ective equipment.

~

Uritt en procedures to annure proper nelection, nupervinion,

.2 and training of personnel uning cuch protective equipuent.

.3 Unitt.cn proceduren to annure the adequate fitting of ren-pirat orc; and the tecting of renpirat cry protective equip-nacnt for operability ir.rediately prior to ucc.

.4 Uritten proceduroc for unintenance t o acnure fu.1 cf fective-1 nesn of respirat cry protective equipment,. including innuance,

'c) caning and decontamination, inspection, repair, and storane.

.5 Uritt.cn operational and administrative proceduren for proper une of re ;pirat.oc / protect ive equip:.ent includ.ing provicionn for planned litaitationn on vorhing tiuen as necessitated by operational conditionn.

.6 Minaccays and/or whole bod counts of individuals (and other nurveys, as api.ropriate) to evaluate individual exposuren and to ar, senn protection act ually provided.

The licensee shall use equipment approved by the U.S. Entcau of c.

111nen under its appropriate Approval Schedules as net forth in Table 6.J2-1.

Equipment not. approved under U. S. Bureau of' 11inen Approval Schedules shall be ened only if the licennee has evaluated the equipment and can demonstrate by testing, or on the-basis of reliable test infc.rmation, that the material and

' perf orcance characteri<.ics 'of the equiptacnt are at 3 cast equal to those afforded by U. S. Bureau of !!inen approved equipment of the name type, as specified in Table 6.12-1.

f.

Uniccs otherwise nuthorized by the Commincion, the licennee chall no_t assign protection factors in execcs of those specified in Table 6.12-1 in cciccting and using respiratory protective equipment.

REVOCATION 6.12.3 The specifications of Section 6.12 chall be revoked in their entirety

~

upon adoption of the proposed change to 10 CFR; 20, Sect.:on 20.103, which would

-inahe such provisions unnecennary.

6-16.'

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J AD".11:1ST)

(i. ) 3 IITC11 RAlft AT10i! A1 l'A 6.13.1-In lien of t he " control device" or "alaria nignal", required by para-gra]>h 20.203 (c) (2)., of - 10 Cril 20:

Each llich Radiation Area in which the_ intensity of radiation 'in

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n.

_ greater t.han 3 00 tircui/hr but 3cus than 1000 nrem/br nhall he

, barricaded and conspicuonn),y }iont.ed an a 111gh Radlat:f on Area

~

- and ent:rance t.hetet o' shall be controlled ;by ing:uance of a:Radia-tion 1'ork -Permi t and any individual or group of individua)u permJ tted to ent er such arcan chall be pro. ided vith a radiation v

t-nonitoring device which continuoucly' indicat.cn the radiation dose -

rate in t.he' area.

b.

Each liigh luidiation Area in which the intencity of radiation-iri greater than 1000 mren/hr shall bc ;nbject to the provisionn of-p 6.13.3 (n) above, and in addition locked doors sha.11 be.provided to prevent unauthori::cd entry into nuch area and the keys cha31 he unintained under the adninistrative control of the Shift Supervinor on' duty.

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e, TABLE 6.9-1 i-PROTECTION FACTORS FOR RESPIRATORS _

GUIDES TO SELECTION OF EQUIPMINT 4

PROTECTION FACTORS PARTICULATES AN'D EUREAU OF MINES A??ROVAL SCHE 0;'LES*

~

VAPORS AND GASES FOR EQUIF ENT CAFASLE OF PRO *lIDING AT EXCEPT TRITIUM LEAST EQUIVALENT PROTECTICN FACTORS 3

• or schedule superseding for DESCRIPTION MODESI OXIDE ecuipment of type listed

,3 I.

AIR-PURIFYING RESPIRATORS 5

213 30 CFR 5 14.4(b)(4)

,Facepiece, half-cask 87 NP.,

21B 30 CFR 514.4(b)(3); 14F 30 CFR 13 4

7 NP 100 Facepiece, full l-g II. AT;!0 SPHERE-SUPPLYINu t

RESPIRATOR p

1.

Airline respirator.'

193 30 CFR 512.2(c)(2) Type C (i)

Facepiece, half-mask CF 100 193 30.CFR 5 12.2(c)(2) Type C (i) s Facepiece, full CF 1,000 193 30 CFR S 12.2(c)(2) Type C ~(ii)

C' Facepiece, full D

100 7

193 30 CFR 5 12.2(c)(2) Type C (iii)

Facepiece, full FD

- 1,000 S

G Hood CF 6

5 Suit CF 2.

Self-contained breathing apparatus (SCBA) 13E 30 CFR 5 ll.4(b)(2) (1) 7 D

100 Facepiece, ful1 Facepiece, full PD 1,000 13E 30 CFR 5 ll.4(b)(2) (ii)

Facepiece, full R

100 13E 30 CFR 5 ll.4(b)(1)

III. C0Y3INATION RESPIRATOR

. Protection factor 19B CFR 5 12.2(e) or applicable Any combination of air-for type and node Schedules as listed above purifying and atmosphere-of operation as supplying respirator listed above 1, 2, 3,

4, 5,

6, 7

[These notes Lre on the following pages]

.w

-o o r TAly.): 6. 9.1 (con i i n,up_d) 1-! ice the follouing nycholn:

CF:

continuoun flou D:

descand'

!!P:

nenative.prennure (ite., negat.fvc phanc during inhalation)

PD:

prennure. demand (i.e.,-always poniti.ve prennure)

. R:

recirculat-inn (cloned circuit) i 2 (a)

For purponen of t hin specification the protection factor in a ucanure of the degree of protection afforded by a renpirator, defined as t he ratio of the concentration of airborne radio-active u tterial outside the respi. rat ory prot.ective equipmnt to that inside t.he equipnent (unually inside the facepiece)

-under conditions of unc.

It in applied _ to tbc a::.bient air-borno concent ration to_ catinate the concent ration inhaled by the uearer according to the follouing forunla:

' Concentration Inhaled = Ambient _ Airborne Concentr7 tion Protection Factor (b)

The protection factors apply:

t (i) only for trained individuals nearing properly fitt ed l

respiratorn used and maintained'under nupervision in l

a ucil-planned respiratory protective prograu.

i (ii) f or air-purifying renpiratorn only uhan high ef ficiency

[above 99.9% re:r. oval ef ficiency by U. S. Bureau of Minen type diocty) phthalate (DOP) tent] particulate filtern and/or norhents appropriate to the hazard are used in atmospheren not deficient in oxygen.

-(iii) for atronphere-nupplying respirators only when supplied with adequate respirable air.

3 F.xcluding radioactive contaminants that present an absorption or cub-mornion hazard.

For tritium oxide approximately half of the intake

' occurn by absorpt ion through the chin no. that an overall protection factor of not more than approxiuately 2 is appropriate when atuonphore-nupplying respiratorn are used to protect anainst tritiu:a oxide.

Air-

_ purifying respiratorn are not reco:=nended for nuc against tritium oxide.

See also footnote 5, below, concerning supplied-air suitn and hooda..

4'Under chin type only.

Ilot recommended for une uhcre ir might be ponnibic for the ambient airbori.e concentration to reach instantaneoun valuesColumn greater than 50 timen the pertinent valuen in Appendix B, Tahic 1, 1 of 10 CFR Part 20..

. 6-19

^f

W-tap >I.r. ~ f. 9-1 ' (con: inocd)

I' Appropriat e protection.factorn mu:!t. he.det.cretined taking accotuit.' of

~

the der.ign of.the n. ult or hood and 'ils perneabilit y t o t he contaninant.

under conditi.onc of unc.

No prorcet-ion factor ~grenter then J.000~nhall

. be used 'except an aut horized by t he Co:::mi:. : ion.

~

I lhe approval schedulen current,1y available f or ' thin crpsipnent.

Erpiip-ucn t inun t he evaluated by tenting or on banin of avaiJahle tent infor-

. nation.

7 Only'for. shaven faces, s

JyTE 1:

l' rot cetion fact orn for rer.piratorn, au n:ay be approved by Ihe U.S. liurcou of.Minen accord.ing to approval nehedulen for respirators to protect againnt airbornu radionucliden, uay be used to the enthat that they do not execed the protcetion factors:

listed in thin Tahic.

The protection factorn in this Table may not be appropriate to circunstance:. where cheuical or.other respiratory hazards exint in addition to radioactive hazarda.

The celection and une of respiratorn for nuch circu:nntancen should take into account approva). of the U.S. Poureau of Minen in accor-dance uith itn apjilicable :,chedules.

EDTE 2: 1 adioactive conta:ainants f or which the concentration vaJucs in Appendix B, Table 1 of t his, part nre based on internal done-dire to inhalation may, in' addit ion, prer.unt external exposure hazards at. higher concentrationn.

Under such circuantances, li:ai ta t ions on occupancy inay have to be governed by external doce lisaitn.

e e

A r

6-20 9

4