ML19320C711
| ML19320C711 | |
| Person / Time | |
|---|---|
| Issue date: | 07/02/1980 |
| From: | Minogue R NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML19320C708 | List: |
| References | |
| REF-10CFR9.7, TASK-CC, TASK-SE SECY-80-275B, NUDOCS 8007170604 | |
| Download: ML19320C711 (23) | |
Text
'
(7590-01]
h ENCLOSURE 5-1 0F SECY 80-275B s
PART 50 - DOMESTIC LICENSING OF PR000CTION AND UTILIZATION FACILITIES t'
1.
Paragraph (g) of Section 50.33 is revised to read as follows:
9 50.33 Centents of applications; general information.
k R
M M
M (g)
If the application is for an operating license for a nuclear power reactor, the applicant shall submit radiological emergency response plans of Stata and local governmental entities in the United Statas that are wholly or partially within the plume exposure pathway Emergency Planning Zone (EPI)1, as well as the plans of Stata governmerits wholly or partially within the ingestion pathway E?Z.2 Generally, the plume exposure pathway
(.
EPZ for nuclear pcwer reactors shall c:nsist of an area abcut 10 miles (16 Km) in radius and'the ingestien pathway EPZ shall consist of an area about 50 miles (80 Km) in radius.
The exact size and c:nfiguration of the EPIs surrcunding a particular nuclear pcwer reacter shall be deter-mined in relation to the emergen6f response needs and capabilities as they are affected by such local canditiens as demography, t pegraphy, land charactaristics, access routas, and local jurisdictional boundaries.
The size of the E?Z's also may be determined en a case-by-case basis for gas c:cled reac ces and for reac crs with an authorized =cwer level less
\\
than 250 MW thermal.
The plans for the ingestien pathway shall focus en
'F.mergency ?lanning Zenes (EPIs) are discussed in NUREG-0395, E?A 520/
1-78-016 " Planning Basis for the Development of Stata anc L: cal Gcvern-ment Radiological Emergency Rescense ?lans in Succer cf Lign: Watar Nuclear Pcwer Plants," Decamcer 1978.
)
If the State and local emercency rescense cians have been ersviousiv su:-
mitac to :ne NRC for inclusion in :ne facility cccxe:. :ne acc 1can neec J
only crevice tne accrecelate esf ersnca :o meet :nt s recut-ement.
h
[7590-01]
te the Director of Nuclear Reactor Regulation for approval within one year from the effective data of this rule.
Each licensee who is authorized to possess and/or cperata a research reactor facility with an authorized power level lass than 500 W thermal, under a license of the type speci-fied in i E0.21(c), shall submit emergency plans c:mplying with 10 CFR Part 50, Appendix E, to the Director of Nuclear Reactor Regulation for approval within two years frem the effective date of this anendment.
(s) Each licensee who is authorized to possess' and/or cperate a nuclear pcwer reactor shall submit to NRC within 50 days of the effective
=
data of this amendment the radiological emergency response plans of Stata and local governmental entities in the United States that are wholly or partially.witnin a plume exposure pathway Emergency Planning Zone (E?Z),
as well as the plans of State governments wholly or partially within an ingestion pathway EPZ.1'2 10 ccpies of the above plans shall be forwardeo to the Director of Nuclear Reactor Regulation with 3 c: pies to the Direct:r of the appropriata NRC regional office.
Generally, the plume exposure pathway E?Z for nuclear pcwer reactors shall consist of an area acout 10
~
miles (15 Km) in radius and the ingestion pathway EPZ shall consist of an area about 50 miles (80 Km) in radius.
The exact size and c:nfiguration of the E?Zs for a particular nuclear pcwer reacter shall be detarmined in relatien to the emergency response needs and cacabilities as they are affected by such local c nditions as demcgraphy, tepcgrachy, and land charactaristics, access reutas, and Iccal jurisdictional bcundaries.
The size of the E?Is also may be detarmined en a case-by-case basis for gas
'Energency Planning Zones (E?Is) are discussed in NUREG-0396; E?A 520/1-73-015
" Planning Basis for the Devsicpment of State and Local Gcvernment Raciciegica~
Energency Response ?lans in Sucper: cf Lignt Watar Nuclear ?cwer ?lants,"
Decemoer 1978.
2If the Stara and 1ccal emercancv rescense clans nave been creviousiv suc-21::ac c ne NRC for inclusion in :ne f act i1:v ccc:<at. One acclicant neec aniv crevice tne accrearlata reference' t: meet :nis recuirement.
[7590-01]
-\\
Enclosure B-2 of SECY 80-2758 4
[
All training, includine exercises, shall provide for formal criticues in order to [evaiente-the emergency p9sn s-effectiveness-and-t: : rrect a
weak-tress-thre gh-feedheck with emphasis-en-sched=ies7-iessien piens7 prteticaf-t tining-snd periedit examinatiens-] identify weak areas that need corrections and any weaknesses that are identified soall be corrected.
J 51a inc1:sure "5"
(7590-01]
Enclosure S-3 of SECY 80-275B p,
-['
2.
Provisiens shall be described for the yearly dissemination to the public, including the transient pcpulation, within the plum exposure pathway
!?I of basic emergency planning information, such as the methods and times required for public notification, and the protective actions planned if an accident occurs, and general information as to the nature and effects of radiation, and a listing of iccal broadcast stations that will be used for dissemination of information dur ng an amergency.
3.
A licensee shall have the capability to notify rescensible State i
and local governmental agencies within 15 minutas after declaring an emergency.
The licensee shall demenstrate that the Stata/lecal officials have the capability to make the public notification decision premptly on being informed by the licensee of an emergency candition.
By July 1, 1981, the Nuclear Power Reacter licensee shall demonstrata that the administrative and physical means for alerting and previding prempt instruct:ns to the puclic within the plume exposure pathway emergency planning rene have been established.
The design cbjective shall be te have the capability to essentially completa the initial notification of the public twthin the plume exposure pathway E?Z within accut 15 minutas.
The use of this notificat1on cacability will rance frem immediata noti-fication of the cublic (within 15 minutes of the time that State and local efficials are notified that a situation exists recuiring urgen-i j
action) to the mere likelv events where there is sucstantial time avaiiacie 47
[7590-01]
Enclosure B-4 of SECY 80-2753 m:
w cooled nuclear reactors and for reacters with an authorized pcwer level
- f less than 250 MW thermal.
The plans for the ingestien pathway EPZ shall fccus on such actions as are appropriata to protect the food ingestion pathway.
For operating pcwer reacters, the licensee's and Stata and local emergency response plans shall be implemented by Acril 1,1981, except,
as provided in Section IV, 0 3 of Appendix E, of this Part.
If, aftar Acril 1, 1981, the NRC finds that the Stata of emergency preparedness does not provide reasonable assurance that appropriata protective measures can and will be taken in the event.of a, radiological emergency and the deficiencies are not corrected within four months of that finding, the
)
\\
Commission wilt determine whether the reactor shall be shut dcwn until-such deficiencies are remedied or whether other enforcement acticn is acerceriata.
In determining whether a shut dcwn or other enforcement action is acerceriata, the Ccemission shall take into acccunt, amenq other factors, whether the licensee can demonstrata to the Ccmmissien's satisfaction that the deficiencies in the plan are not significant fer the plant in question, or that alternative ccmcensating acticns have been er will be taken prcmotly, or that there are c:her ccmpelling reascns for l
continued operation.
The NRC will base its finding on a review of the Federal Emergency Management Agency (FEMA) findings and determinations as to whatner Stata and local emergency plans are adecuate and cacable of being imolementac, and on the NRC assessment as to whether the licensee's emergency plans are 37 y.1.....
- l e 't
[7590-01]
for the'Stata and local covernmental officials to make a fudcment whether or not to activata the cublic notification svstam.
The responsibility for activating such a public notification system shall rsmain with the V
appropriata gov.ernment authorities.
1
)
~
o
)
s.,
2-w*
O 47a
[7590-01] -5 of SECY 80-2753 for reactors with an authorized pcwer level less than 250 MW thermal.
- {'
The plans for the ingestion pathway shall focus on such actions as are appropriate to protect the food ingestion pathway.
.3.
Section 50.54 is amended by adding five new paragraphs, (q),
(r). (s), (t), and (u).
5 50.54 Conditions of licenses.
n n
x a
n (q)
A licensee authorized to possess and/or cperate a nuclear ocwer ractor shall fellcw and maintain in effect amergency plans which meet the standards in 50.47(b) and the requirements in Appendix E of this Part.
6' A licensee authorized to cessess and/or ccerate a research reacter er a fuel facility sha'll follow and maintain in effect emercency clans which meet the recuirements in Accendix E of this Part.
The nuclear ccwer reacter licensee may make changes to these plans without Ccemission approval only if such changes do not decrease the effectiveness of the plans and the plans, as changed, continue to meet the standards of 50.47(b) and the requirements of Appendix E of this Part. The research reacecr licenses and/or the fuel facility licensee may make chances to these clans without Ccmmission accroval aniv if such chances do not decrease the effectiveness of the clans and the olans. as chancec, con-i tinue to meet the recuirements of Accendix E of this Part.
Preccsed changes that decrease the effectiveness of the accroved emergency cians shall not be imolemented without acclica:icn to and accreval by the 35 e1nene. ";"
n
~
(7590-01]
~
adequata and capable of being imolemented.
Nothine in this caracrach shall
.^
v be construed to limit the authority of the Ccmmission to take action under any other regulation or authority of the Ccmmission or at any time other
!;S '
than that scecified in this caracrach.
(t) A nuclear power reactor licensee shall provide for the develop-ment, revision, implementation, and maintanance of its emergency prepared-ness pregram.
To this end, the licensee shall provide for a review of its emergency preparedness program at least every 12, months by 6
.A%
L 4.
l
[
27a r a,- 1 a c o.. 6:"
[7590-01]
APPENDIX E--EMERGENCY PLANNING AND PREPAREDNESS FOR y
PRODUCTICN AND UTILIZMION FACILITIES 1 3,
I.
Introduction Each applicant for a ccnstruction permit is required by i 50.34(a) to include in its preliminary safety analysis report a discussicn of pre-liminary plans for ccping with emergencies.
Each applicant for an operating license is required by 5 50.34(b) to include in its final safety analysis report plans for ccping with emergencies.
This appendix establishes minimum requirements for emergency plans for use in attaining an accaptable state of emergency preparedness.
These plans shall be described generalTy in the preliminary safety analysis report t-and submittad as a part of the final safety analysis report.
The potantial radiological hazards to the public asscciatad with the operation of research and tast reactors and fuel facilities licensed under 10 CFR Part 50 and 70 involve censiderations different than those asscciated
'NRC staff has developed two regulatory guides:
2.6, " Emergency Planning for Research Reactors," and 3.a2, " Emergency Planning in Fuel Cycle Facilities and Plants Licensed Under 10 CFR Parts 50 and 70;" and a jcint NRC/ FEMA report, NUREG-0654; FEMA-REP-1, "Critaria for Precaration and Evaluation of Radiological Emergency Response Plans and Preparecness in Support of Nuclear Pcwer Plants - For Interim Use and Ccmment," January 1980, to provide guidanca in developing plans fer ccping with emergencies.
Ccpies e
of these dccuments are available at the Ccmmission's Public Occument Recm, 1717 H Street, NW., Washing;cn, D.C. 20555.
Ccpies of these documents may be purchased frem the Government P,rinting Office.
Informatien en current prices may be obtained by writing the U.S. Nuclear Regulatcry Ccmmission, Washingten, D.C. 20555, At:anticn:
Publications Sales Manager.
i I
i 39
[7510-01]
Commission.
The licensee shall furnish 3 copies of each proposed change for appreval; if a change is made without prior approval, 3 copies shall be submitted within 30 days after the change is made or proposed to the e
4 Director of the appropriate NRC regional office specified in Appendix 0, Part 20 of this Part, with 10 copies to the Director of Nuclear Reactor Regulation, or if acercoriata, the Director of Nuclear Material Safety and Safecuards, U.S. Nuclear Regulatory Cc= mission, Washington, D.C. 20555.
,(r)
Each licensee who is authorized to possess and/cr operate a research or test reactor facility with an authori:ed power level greater than or equal to 500 kW,undar a license of the type specified in i 50.21(c),
shall suhait amergency plans complying with 10 CFR Part 50, Appendix Et O
q 1
e 35a 1
[7590-01]
i
. -6 of SECY 80-2758 4
In deciding whether to permit reactor operation in the face of some. deft-ciencies, the Commission will axamine whether the deficiencies are signif-w' icant for the reactor in question or whether alternative compensatory actions have been or will be taken promptly or whether consistent with the public health and safety other compelling reasons exist for reactor operation.
Specifically, the regulation contains the following three major changes from past practices:
1..
In order to continue operations or to receive an operating license an applicant / licensee will be required to submit their emergency plans, as w' ell as State and local governmental emergency response plans to NRC.
The NRC will then make a finding as to whether the l.'
state of onsita and offsita amergency preparedness provides rsason-able assurance that appropriate prctective measures can and will be taken in the event of~a radiological emergency.
The NRC will base its finding on a review of the Federal Emergency l
Management Agency (FEMA) findings and detarmi' nations as to whether Stata anc local em'ergency plans are adequate and capable of being implementad, and on the NRC assessment as to whether the licensee's/ applicant's emer-gency plans are adequate and capable of being implementad.
Specifically:
a.
An Operating License will not be issued unless a favorable NRC overall finding can be made.
b.
Aftar Acril 1,1581, an operating plant may be recuired to shut down if it is detarmined that there are suen ceficiencies such-that a favorable NRC finding cannot be made or is no longer warrantad and the deficiencies are not corrsctad witnin a montns of that datarmination.
[7590-01]
with nuclear power reactors.
Consequently, the size of Emergency Planning Zones 2 (EPIs) for facilities other than power reacters and the degree to-which compliance with the requirements of this Section and Sections II, III,
.m
'a IV and V is necessary will be determined on a case-by-case basis.3 II.
The Preliminary Safety Analysis Report The Preliminary Safety Analysis Report shall contain sufficient information to ensure the compatiblity of preposed emergency plans for both onsite areas and the EPZs, with facility design features, sita layout, and sita location with respect to such considerations as access reutas, sur-rounding population distributions, land use, and local jurisdictional boundarie for the Emergency Plannir.g Zones (E?Zs) as in the case of nuclear ocwer reactors as well as the means by wnich the standards of 50.47(b) will be met.
'i??.s for power reactors are disecused in NUREG-0396; EPA 520/1-78-015
" Planning Basis for th Development of Stata and Local Government Radiological Emergency Response Plans in Support of Light Watar Nuclear Pcwer Plants,"
December 1978.
The size of the EPZs for a nuclear power plant shall be determined in relation to the emergency response needs and cacabilities as they are affected by such local cccditions as demograchy, t pograchy, land charactaristics, access reutas, and local jurisdictional boundaries.
The size of the E?Zs also may be detarmined on a case-by-casa basis for gas cooled nuclear reacters and for reacters with an authorized power level less than 250 W thermal.
Generally, the plume exposure patnway E?Z for nuclear pcwer plants with an authorized pcwer level greatar than 250 W thermal shall c:nsist of an area about 10 miles (16 b) in radius anc :ne ingestion pathway E?Z an area about 50 miles (20 b) in radius.
3Reculatory Guide 2.5 will be used as cuidanca for the ac:actability of researen anc test reactor emercancy resuonse clans.
[7590 01]
Enclosure B-7 of SECY 80-275B s.
capabilities will require clos's coordination and c:cperation between
~..
responsible Federal agencies, State government, and the nuclear i
industrf.
An orderly and esmprehensive approach to this effort makes it necessary that onsite responsibilities be clearly identified with
~
NRC and the nuclear-industr/ while deferring offsita responsibilities to State government with appropriate FEMA versight and assistance.
In addition to these c:mments, two petitions for fulemaking were i
filed in reference to the proposed rule.
(Mthe:gh-the petitions were '
denied ] The c:mments made by the petitioners in support of their petition 7
were considered in developing the final rule.
The Commission has placed the planning objective from NUREG-0654;
's.
FEMA-REP-1 " Criteria for Preparatic_n and Evaluation of-Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants for Intarim Use and C mment" January 1980, into the final regula-tions.
Ccmments received c:ncerning NUREG-0654 were available in developin'g the final ' regulation.
The Ccmmission notas that the planning objectives in NUREG-0654 were largely drawn from NUREG-75/111, " Guide and Checklist for Development and Evaluation of State and Local Government Radiological Emergency Response Plans in Support of Fixed Nuclear Facil-ities" (Decemcer 1,1974) and Supplement 1 thereto dated March 15, 1977, which have been in usa for some time.
The approximately 50 public comment letters received on NUREG-065J-were not critical of the preposed planning cojective.
The Ccmmission also notes that at the May 1,1980 ACRS caeting, the Atemic Indusuial Forum representative enc:uraged the use of the planning object v
.m i
n
[7E90-01]
G.
MAINTAINING EMERGENCY PREPAREDNESS Provisions to be employed to ensure that the emergency plan, its implementing procedures, and emergency, equipment and supplies are main-
- ~,
tained up to date shall be described.
w H.
RECOVERY Criteria to be used to determine when, following an accident, reentry of the facil:ty would be appropriate or when operation could be resumed shall be described.
V.
Implementing Procedures No less than 180 days prior to scheduled issuance of an operating license or license to cessess nuclear matarial, 3 c: pies each of the applicant's detailed implementing prece'dures for its emergency plan shall be submitted to the Director of the apprcpriate NRC Regional Office with 10 copies to the Director of Nuclear Reactor Regulation or if accroariata the Director of Nuclear Material Safety and Safecuards.
In cases where a decision on an operating license is scheduled less than one year after the j
effective date of this rule, such implemanting precedures shall be submit:ad as soon as practicable but before full cower coeration is authorized.
Prior to March 1.198L licensees who are authorized to operate a nuclear power facility shall submit 3 c pies e
52
[7590-01]
l -8 of SECY 80-2758 and offsita agencies.
That information shall be sufficient to provide assuranca of ecordination among the supporting groups and between them and the licensee.
The plans submitted must include a description of the elements set out in Section IV for the Emergency Planning Zones (EPIs) to an extant sufficient to demonstrate that the plans provide reasonable assurance that appropriate measures can and will be taken in the event of an emergency.
IV.
Content of Emergency Plans The appifcant's emergency plans shall contain, but not necessarily be limited to, information needed to demonstrata comoliance with (the objectives-of-EO-4Hbh-ine uding] the [feiiewing] elements set forth below. i.e. organization for ccping with radiation energencies, assess-ment action, activation of emergency organization, notification precedures, emergency facilities and equipment, training, maintaining emergency preparedness, and recoverf.
In addition. Nuclear cewer reacter acclicants' emercency resconse olans shall contain informatien needed to demonstraca ecmoliance with and will be evaluatad usine the standards described in Sec-tien 50.47(b). 4 The nuclear ocwer reactor applicant shall also provide an analysis of the time required to evacuate and the taking cf cther protectives actions for various sectors and distancas within the plume exposure pathway E?I for transient and permanent peculaticns.
i
- These cojec-ives are acdressed by scacific criteria in NUREG-0554; FEMA-RE?-l titled "Critaria for Preparaticn anc Evaluation of' Racic-Icgical Emergency Rescense Plans and Precarecness in Succort of Nuclear l
Pcwer Piants for in arim Use and Comment," Januarj 1980.
l t
.91
[7590-01'J i
1 emergency shall be described.
This shall include a description of special-j ized initial training and periodic retraining programs to be provided to each of tne following catagories of emergency personnel:
l' n.
Directors and/or coordinators of the plant emergency organization.
b.
Personnel responsible for accident assessment, including control reem shift personnel.
c.
Radiological monitoring taans.
d.
Fire centrol teams (fire brigades).
e.-
Repair and damage control teams.
f.
First aid and rescue teams.
g.
Medical support personnel.
l h.
Licensee's headquartars support personnel.
i.
Security personnel.
j.
In addition, a radiological orientation training pregram shall be made available to local services personnel, e.g., local Civil Defense, local law enforcament personnel, local news media persons.
The plan for Nuclear Pcuer Reactors shalT describe provisions for the cenduct of an emergency preparedness exercisa enca a year.
This exercise is intanded to test the adequacy of timing and c:ntant of implementing preca-dures and methods, to tast emergency equipment and c:mmunicatien networks, to test the public notification systam, and to ensure that emergency organization personnel are familiar with their duties.
Such previ; ions shall specifically include periodic participation by offsite persennel as described above as well as c her Stata anc local governmental agencias.
50
(7590-01]
4 G.
MAINTAINING EMERGENCY PREPAREDNESS s
Provisions to be employed to ensure that the emergency plan, its implementing precedures, and emergency equipment and supplies are main-
~
tained up to data shall be described.
H.
RECOVERY Criteria to be used to determine when, follcwing an accident, reentry of the facility would be appropriata or when operation could be resumed shall be described.
V.
Implementing Precedures No less than 180 days prict to scheduled issuance of an operating licanse or license to cessess nuclear material, 3 copies each of the 1
applicant's detailed implementing precadures for its emergency plan shall be submitted to the Director.cf.the apprcpriata NRC Regicnal Office with 10 copies to the Director of Nuclear Reactor Regulation er if acercoriata the Director of Nuclear Material Safety and Safecuards.
In cases where a decision en an operating license is scheduled less than ene year aftar the effective data of this rule, such imclementing precedures shall be submittad as seen as practicable but before full pcwer cceration is authorized.
Prior to March 1,1981, licansees who are authori:ed to cperata a nuclear pcwer facility shall submit 3 copies 52
J
[7590-01]
4 with nuclear power reactors.
Consequently, the si:e of Emergency Planning
~
Zones * (EPIs) for facilities other than power reactors and the degree to whjch compliance with the requ:rements of this Section and Sections II, III, IV and V is necessary will be determined en a case-by-case basis.3 II.
The Preliminary Safety Analysis Report The Preliminary Safety Analysis Report shall contain sufficient information to ensure the compatiblity of preposed emergency plans for both onsite areas and the EPIs, with facility design features, site layout, and site location with respect to such considerations as access reutas, sur-rcunding population distributions, land use, and local jurisdictional boundaris for the Emergency Planning Zones (EPZs) as in the. case of nuclear ecwer
.t
~
reactors as well as the means by which the standards of 50.47(b) will be met.
'EPIs for power reactors are disecused in NUREG-0396; EPA 520/1-78-015
" Planning Basis for th Develcpment of State and Local Government Raciological Emergency Response Plans in Support of Light Water Nuclear Pcwer Plants,"
December 1978.
The si:e of the EPZr for a nuclear pcwer plant shall be datarmined in relation to the emergency responsa needs and capabilities as they are affected by such 1ccal conditiens as demograpny, tccograpny,
'and charactaristics, access routes, and local jurisdictional boundaries.
T;te si:e of the EPIs also may be determined on a case-by-case basis for gas cooled nuclear reactors and for reac crs with an authori:ed ccwer level less than 250 W thermal.
Generally, the plume exposure pattway EPZ
'for nuclear pcwer plants with an authori:ed pcwer level greatar than 250 W thermal shall censist of an area abcut 10 miles (15 b) in racius and the ingestion pathway EPZ an area about 50 miles (80 b) in radius.
3 Regulatory Guide 2.5 will be used as guidance for the acceptability of research and test reactor emergency response plans.
f
[7590-01]
4 for reactors with an authorized power level less than 250 MW thermal.
The plans for the ingestion pathway shall focus on such actions as are appropriate to protect. the feud ingestion pathway.
3.
Section 50.54 is amended by adding five new paragraphs, (q),
h (s), (t), and (u).
5 50.54 conditions of licenses.
n n
(q) A licensee authorized to possess and/or operate a [; red:ction and stiii:stien-feciifty except rescereh-eecters] nuclear ecwer racter shall follow and maintain in. effect emergency plans which meet the standards in 50.47(b) and the requirements in Appendix E of this Part.
i A licensee authorized to cessess and/cr coerate a research reactor or a fuel facility shall fc11cw and maintain in effect emercency clans which mee't the recuirements in Accendix E of this Part.
[The pred::tien-end etifi:stien-faciiity] nuclear ccwer reactor licensee (except-esear-5 reseter] cay make changes to these plans withcut Ccmmissien approval only if such changes de not decrease the effectiveness of the plans and the plans, as changed, c:ntinue to meet the standards of 50.47(b).and the requirement: cf Appendix 5 of thic Part. The research reactor licensee and/or the fuel facility licensee may make chances to these clans without Ccmmission accreval cniv if such chances do not dec ease the effectiveness of the clans anc the clans, as chanced. con-tinue to meet the recuirements of Accendix E cf this Part.
Preccsed changes that decrease the effectiveness of the approved emergency plans --.
shall not be imolementad without acplication to and acpreval cy ne 35
~
1 Ai (7590-01]
Commission.
The licensee shall furnish 3 copies of each proposed change for approval; if a change is made without prior appreval, 3 copies shall be submitted within 30 days after the change is made or proposed to the Director of the appropriata NRC regional office specified in Appendix 0, Part 20 of this Part, with 10 copies to the Director of Nuclear Reactor Regulation, or if accroariata, the Director of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
(r)
Each licensee who is authorized to possess and/or operate a research or test reactor facility with an authorized pcwer level greater than or equal to 500 kW,under a license of the type specified in 3 50.21(c),
shall submit energency plans ccmplying with 10 CFR Part 50, Appendix E, e-35a 1