ML20045E163
| ML20045E163 | |
| Person / Time | |
|---|---|
| Issue date: | 06/19/1991 |
| From: | Norry P NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Beckjord E NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20044B465 | List: |
| References | |
| FRN-57FR33426, RULE-PR-70, RULE-PR-72, RULE-PR-73, RULE-PR-75 AD03-2-010, AD3-2-10, NUDOCS 9307010199 | |
| Download: ML20045E163 (29) | |
Text
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UNITED STATES
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aE NUCLEAR REGULATORY COT ~ ' SSION Bahadur
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WASHINGTON, D.C. 20555 gy o
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JUN 141991
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?M MEMORANDUM FOR: Eric S. Beckjord, Director
~,
Office of Nuclear Regulatory Research' FROM:
Patricia G. Norry, Director.
Office of Acministration
SUBJECT:
FINAL RULE ENTITLED " MINOR AMENDMENTS TO THE PHYSICAL PROTECTION REQUIREMENTS" The Office of Administration (ADM) concurs in the final rule that presents minor amendments to the physical protection requirements. We have enclosed a marked copy of the final rule that presents our comments.
-In order to assist you in preparing the list of documents centrally relevant -
to this final rule that is required by NRC's regulatory history procedures, you should place the designator "AD03-2" in the upper right-hand corner of.
each document concerning the rule that you forward to the Nuclear Document System.
We have forwarded a copy of the final rule to the Information and Records Management Branch, IRM, for their comment or concurrence concerning the paperwork management aspects of this rulemaking action.
If you have any questions concerning this matter, please have a member of your staff contact Alice Katoski (extension 27928) or Michael T. Lesar, Regulatory l
Publications Branch, ADM (extension 27758).
Pa G. 7 Director Office of Administration
Enclosure:
As stated i
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'9307010199.930512 PDR PR PDR 70 57FR33426 4
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NUCLEAR REGULATORY COMMISSION i
10 CFR PARTS 70, 72,.73, and 75 RIN: 3150-AD03
~
Minor. Amendments to the Physical Protection Requirements AGENCY: Nuclear Regulatory Commission.
ACTION:
Final rule.
4 1
SUMMARY
- The thciear Regulatory Commission (NRC) is' amending its-regulations' -
that cover the physical protection of'specialtnuclear' material..nThese?
~
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amendments will (1) add definitions for. common terms not currently defined but frequentlyused,(2) delete'a'ctiondatesthatnolonger. apply,?(3) correct!
outdated terms and cross references,.(4). clarify wording thatLis susceptible to differing interpretations, (5) correct typographical errors, and (6) make: other :
h minor changes. The amendments are the result of a systematic review of NRC'ls-safeguards. regulations.
. EFFECTIVE DATE:
[ Insert a'date thirty days-after publication ~in the Federal Register.].
Stanley.P. Turel,. Regulation Development L'
.FOR.FURTHER INFORMATION' CONTACT:
i
- Branch,. Division of Regulatory Applications, Office:of Nuclear Regulatory a
Research,~.U.S. Nuclear Regulatory Commission, Washington, DC. 20555,LTelephone" (301)492-3739, or.Priscilla Dwyer, Domestic Safeguards and Review Oversight Branch, Division of-Safeguards and Transportation, Office of Nuclear Material-1.
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' Safety and Safeguards, U.S.' Nuclear Regulatory Commission, Washington, DC.20555, Telephone (301)492-0478.-
. SUPPLEMENTARY INFORMATION:
The NRC Safeguards Interoffice Review Group has been conducting a systematic review of the Agency's safeguards regulations-and guidance documents-to_ identify areas in the regulations that are out of.date,_ inconsistent, or susceptible to differing interpretations.
In doing so,-the review group has also identified other areas in the regulations-where minor changes are warranted. The NRC published in the Federal Register on August 15,1989 (54: FR n 33570), proposed amendments consisting of minor corrections and_ changes to its regulations identified by the review group that cover the-physical-protection of special nuclear material. The comment period ended on September 29, 1989..
.The proposed changes are summarized here with a brief discussion.
1.
The substance of paragraphs (b), (c), and (d).of 10 CFR 73.40 is moved to Appendix C to 10 CFR Part 73 and combined with the safeguards contingency plan specifications already there. The requirement for having a. safeguards contingency plan is included in each of the sections of the regulations covering security requirements for the' specific class of affected licensees.
(il73.21,73.25,73.26,73.40,73.46,73.55,73.67).
2.
Definitions of the commonly used terms Category I, Category II, and Category III are added for reference purposes-to existing definitions in the' definitions' sections of 10 CFR Parts 70 and 73.
j
- A Category I quantity of material, if unirradiated, is e_quivalent to a formula quantity; a Category 11 quantity of material, if 'unirradiated, is Lequivalent to special nuclear material of moderate strategic significance; and
- a. Category III quantity of material, if unirradiated, is equivalent!to special:
nuclear material _of low strategic significance. The current regulationsLdoLnoti Linclude= these category designations", although they are frequently used, particularly in international safeguards, and appear in'some NRC' documents. _To;.
avoid possible confusion, definitions of.'these terms are being added to the definitions in parts 70 and 73.
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47590-01]A t-3.
Inconsistencies among the general auditing requirements for the safeguards contingency plans and physical security programs of Category I transportation and fuel cycle licensees are being removed.
The record retention period for results of audits is being made.at_three.
years.
Inconsistencies in both the content of audits and resultant actions are being eliminated.
4 An inadvertently omitted sentence that addresses access to vital areas [
atpowerreactorsisbeingreinsertedintoparagrap573.55(d)(7)toensurethat(
no erroneous views are held by licensees that the deletion of the sentence was a " signal" that vital areas could be " opened up" to "public sightseeing tours" or "open house visits" without close licensee oversight. Proper control over access to vital areas is already reflected in the security plans of licensees.
Moreover, the specific wording being reinserted was contained in 10 CFR Part 73' for a number of years preceding 1986.
Correcting this inadvertent omission does not signal any change in Commission policy or practice in this regard.
5.
A definition for the term " contiguous sites" is added to 10 CFR Parts 70 and 73. This definition of the term has been modified from that. presented in the proposed rule to eliminate a possible misunderstanding that the licensee would not be responsible for its contractor's security measures. Action dates that have passed are eliminated. The outdated term " industrial sabotage" is being replaced by the current term " radiological sabotage."
Incorrect references to parts of the regulations that.have been moved or deleted are being corrected.
Paragraph designations in references in other parts of the regulations to definitions in $70.4 are removed because those' designations were deleted in an amendment published in the Federal _ Register on April 28, 1989 (54'i FR14051). Several areas in the regulations are clarified where the wording was-susceptible to differing interpretations. The notification requirement for-changes to the safeguards contingency plan _that do not decrease the plan's effectiveness is revised to require that the original be sent to the NRC-head-quarters' office with a copy to the regional office instead of vice versa.
Finally, several typographical errors are corrected.
SUMMARY
.0F PUBLIC COMMENTS Letters of comment were received from three respondents:
two from nuclear power plant licensees and one from NUMARC, an umbrella organization of'the C
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f 17590-01]
nuclear power industry whose membership includes every utility responsible for constructing or operating a commercial nuclear power plant in the_ United States.
Copies of comment letters are available for public inspection and copying for a fee at the NRC Public Document Room at 2120 L Street NW. (Lower Levef, Washington,DC.
All three commenters addressed only the amendment that would restore the j
inadvertently omitted sentence in paragrap(73.55 (d), Access Requirements.
This sentence follows the requirement in paragrapfi 73.55 (d)(7)(1) that the licensee " Establish an access authorization system to limit unescorted access to vital areas during nonemergency conditions to individuals who require access in order to perform their duties."
It reads:
" Access to vital areas for the purpose of general familiarization and other nonwork-related activities may not be authorized except for good cause shown to the licensee." One commenter stated that the restrictions [ presumably made explicit by the ' inserted' sentence] should be withdrawn to allow tours with the provision of appropriate security measures to ensure plant safety...and that "This change would limit access to nuclear plant vital areas even when under escort." A second commenter asserted that the inserted sentence "needs clarification." The third commenter stated that it would be beneficial if a definition of " good cause" were provided by the Commission in the rule and if additional guidance were provided as to what constitutes nonwork-related activities.
With regard to the first comment, item 5 of the Supplementary Information published with the proposed rule, stated that the inadvertent omission of the subject sentence should not be construed as a "' signal' that vital areas could-be ' opened up' to 'public sightseeing tours' or 'open house visits' without close licensee oversight" [ emphasis added]. With regard to the second I A comment, further on in the supplementary information of the proposed rule, the NRC notes that " Licensees are assigned the responsibility for making final vital area access decisions in accord with the past practices and provisions under the approved security plans." Hence, the-NRC believes the sentence to be clear. With regard to the third comment, the NRC believes that " good cause" and "nonwork-related activities" are not new terms, having appeared in 6 73.55 before the-sentence was dropped.
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Environmental Impact: Categorical Exclusion The NRC has determined that this final rule is the type of action NW s
describedinthecategoricalexclusioninparagrapf51.22(c)(2 of-la-CER Eng D4L Therefore, neither an environmental impact statement nor an environmental assessment has been prepared for this regulation.
i
. Paperwork Reduction Act Statement This final rule does not contain a new or amended information collection requirement subject to the Paperwork Reduction Act of 1980 (44 U.S.C. 3501 et seq.). Existing requirements were approved under the Office of Management and Budget approval number 3150-0009 for Part 70, approval number 3150-0132 for Part 72, approval number 3150-0002 for Part 73, and approval number 3150-0055 for Part 75.
Regulatory Analysis These minor amendments impose no new restrictions or requirements, and therefore, have no significant impact. Accordingly, a regulatory analysis is-not considered necessary.
I Regulatory Flexibility Certification.
As required by the Regulatory Flexibility Act of 1980 (. 5 U.S.C. 605(b)),
the Commission certifies that this rule will not have a significant. economic impact on a substantial number of small entities. The amendments as promulgated are very minor in nature and care has been taken to ensure that the impact on any licensee is minimal.
In the matter of reporting certain changes to the security program, the amendments m.erely reverse who receives the original and who receives the copy. The other changes are of ar, administrative nature and therefore do not alter the current implementation of:the regulations by a licensee.
Backfit Analysis The NRC has determined that the backfit rule, 10 CFR 50.109, does not apply to this final rule. A'possible exception is the amendment to paragraph 5
Enclosure
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[7590.~01]
~ 73.55(d)(7), which restores a sentence that had been in.sertently dropped 'in an amendment to the regulations published August 4, 198o (51 FR 27817). A
.b'ackfit analysis published with the proposed rule on August 19, 1989.(54 FR 33570) concluded that.the restoration of this sentence would have an insignifi-cant effect on licensees, the NRC, the public,_ and facilities employees.
. W(,
- y 70,72,73,and75[y>
C;'
List of Subjects in 10 CFR Parts wev\\ Qb 4) 0 cedo\\ u$. *c" p
Part 70 gHazardous materials - transportation,pkup uclear materials, P N
and containers, fenalty', Radiation protection, Reporting and recordkeeping requirements, Scientific equipment,-Security measures, Special nuclear-material'.
Part 72 - Manpower training programs, Nuclear materials, Occupational; safety and. health, Repcrting and recordkeeping requirements', Security measures, Spent
. fuel.
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Part 73 gHazardous materials - transportation, Incorporation by reference, Nuclearmaterials,Nuclearpowerplantsandreactors,feaal+ykeportingand recordkeeping requirements, Security measures.
C h h.} j o M M.s, Part 75 41ntergovernmental relations, Nuclear materials, Nuclear power plants and reactors, Pena 4 N Reporting and recordkeeping requirements, Security--
measures.
For the reasons set out in the preamble and under the authority of~the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act ofs1974, as amended, and 5 U.S.C. 552 and 553, the NRC is adopting the followingL amendments to 10 CFR Parts 70, 72, 73,~and 75.
PART 70 -- DOMESTIC LICENSING OF SPECIAL' NUCLEAR MATERIAL 1.
The authority citation for Part 70 continues to. read as follows:
Authority: Secs. 51, 53, 161, 182, 183, 68 Stat. 929, 930, 948, 953,-954, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C. 2071, 2073, 2201, 6-Enclosure-m d
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[7590-01]
20A 2232,32282); secs. 201, as amended, 202, 204, 206, 88 Stat. 1242, as amended, 1244, 1245, 1246 (42 U.S.C. 5841, 5842, 5845, 5846).
Sections 70.1(c)and70.20a(b)alsoissuedunder-secs. 135, 141, Pub. L.97-425, 96 Stat. 2232, 2241 (42 U.S.C. 10155, 10161). Section 70.7,,also issued under Pub. L.95-601, sec. 10, 92 Stat. 2951 (42 U.S.C. 5851). Section.
70.21(g) also issued under sec. 122, 68 Stat. 939.(42 U.S.C. 2152)
.Section 70.31 also issued under sec. 57d, Pub. L.93-377, 88 Stat. 475 (42'U.S.C.
2077).. Sections 70.36 and 70.44 also issued under sec.184, 68 Stat. 954, as amended (42U.S.C.2234). Section 70.61 also issued under secs. 186, 187, 68 Stat. 955 (42 U.S.C. 2236, 2237)..Section 70.62 also. issued under sec. 108,.68 Stat. 939, as amended (42 U.S.C. 2138).
For the purposes of sec. 223, 68 Stat. 958, as amended (42 U.S.C; 2273);
56 70.3). I.'19(c), 70.21(c), 70.22(a), (b), (d)-(k), 70.24. (a) and (b),
Y 70.32(a)(3),(5),(6),(d),and(1),70.36,70.39(b).and(c),70.41(a),-70.42.(a)
Stat!948hsImendd(42U.S.C.2201(band (d),
- and (c), 70.56, 70.57,(b) -(cp#
7 7,-
issued under sec. 161b 70.20a (a) and (d), 70.20b (c) and (e), 70.21(c), 70.24(b), 70.32.(a)(6),'(c),
(d),(e),and(g), 70.36,'70.51-(c)-(g),70.56,-70.57'(b)and(d),and70.58 (a)-(g)(3)and(h)-(j)areissuedundersec.1611,68 Stat.949,asamended(42-U.S.C. 2201(1)); andSS70.5,70.9,70.20b(d)and(e), 70.38, 70.51 (b):and
~
(1), 70.52, 70.53, 70.54, 70.55, -70.58 (g)(4), (k) and (1), 70.59, and 70.60 (b)and(c)areissuedundersec.161o,68 Stat.950,asamended(42U.S.C.-
2201(o)).
2.
Section 70.4 is amended by adding a ' definition for " Contiguous sites" ~
in proper alphabetical sequence, revising the definition of " Formula quantity,"
revising' paragraph (2) of the definition " Plutonium processing and fuel fabrication plant," revising paragraph (1) of the definition "Special nuclear material ~of low strategic significance", and revising the definition of "Special nuclear material of~ moderate strategic significance" to read as follows:
'l-70.4 Definitions.
" Contiguous sites" means locations subject to the control,of a licensee,
'in close proximity to each other, and for the possession, use, or. storage of f
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special nuclear material where the licensee's same security _ measures,or organizational elements, including the alarm station and response personnel, are used to provide the capabilities necessary to satisfy applicable. security ~
l requirements.~
-" Formula quantity" means strategic special nuclear material.in any combination in a quantity of 5000 grams or more computed by the formula,' grams -
= (grams contained U-235) + 2.5 (grams U-233 + grams plutonium).
In unirradiated form this class of material is sometimes: referred to as a Category I quantity of material.
?
" Plutonium processing and fuel fabrication plant" ***
l (2) research and development activities involving any of the operations described in paragraph (1) of this definition except for research;and development activities utilizing. unsubstantial amounts of plutonium.
"Special nuclear material of low strategic significance".means:
(1) Less than an amount of special nuclear material'offmoderate strategic significance as defined -in paragraph (1) of the definition ofL strategic nuclear material of moderate strategic significance in this section, but more than 15 grams of uranium-235 (contained in uranium enriched to'20 percent or more in U-235 isotope) or 15 grams.of uranium-233 or 15 grams of plutonium or the combination of 15 grams when computed by the equat' ion, gram's = (grams contained U-235) + (grams plutomium) + (grams U-233); or (2) Less than 10,000 grams but more than 1000 grams of uranium-235 (contained in uranium enriched to 10 percent or more but less than 20 percent-in_the U-235 isotope); or (3)10,000 grams or more of uranium-235 contained in uranium' enriched above. natural but less than 10 percent in the U-235 Isotope.
In unirradiated-1 form this class of material is~sometimes referred.to.as a Category III. quantity:
of material.
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"Special nuclear material of moderate strategic, significance" means:
(1) Less than a formula quantity of strategic special nuclear material
- but more than 1000 grams of uranium-235 (contained in uranium enriched to 20 percent or more.in the U-235~ isotope) or more than-500 grams'of uranium-233 or-i
. plutonium or in a combined quantity of more than 1000: grams when computed by the equation, grams =(grams contained U-235)+2(grams'U-233+ grams plutonium); or
[(2)10,000 grams or more of uranium-235'(contained in uranium' enriched to 10 i
percent or more but less than 20 percent in the U-235 isotope).
In-unirradiated form this class of material is sometimes referred to as' aL l
Category 11 quantity of material.
.i t
3.
In $70.19, paragraph.(o)(2) is revised to read as follows:
$70.19 General' license for calibration or reference-sources.
(a) ***
(2) Any Government agency as defined in 670.4 that holds'a specifi.c license issued by the Commission or the Atomic Energy Commission that-y authorizes it to receive, possess, use, and -transfer byproduct material, source material, or special nuclear material; and
+-
4.
In 570.22, paragraphs (h)(1) and (k) are revised to read as follows:
4 6 70.22 Contents of applications.
(h)(1) Each application for'a license to. possess or use at any site.or-contiguous sites subject to control by the licensee a formula quantity of strategic special nuclear material as defined under 670.4 other than-a license-
.for possession or use of this material-in the operation of a nuclear reactor-licensed pursuant-to Part 50 of this chapter, must' include a physical security plan consisting of two parts.
Part ILmust address vital equipment, vital areas, and isolation. zones and must demonstrate how the' applicant plans to meet.
the requirements of 66 73.20,.73.40 73.45, 73.46, 73.50, 73.70, and 73.71 of this chapter in the conduct of the activity to be licensed, including the identification and description of-jobs as required by paragesp 11.11(a)ofc jo WA i
9 Enclosure
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[7590-01].
.j thi s--chapter.
Part II must list tests, inspections, and other means to demonstrate compliance with-such requirements.
(k) Each application for a license to possess or use at any site or t
contiguous sites subject to control by the licensee special nuclear material of moderate strategic significance or 10 kg or'more of special nuclear material of. -
low strategic significance as defined under S 70.'4, other than a license for
[
possession or use of this material in the operation of a nuclear power reactor :
licensed pursuant to.Part 50_of this chapter, must include.a physical security plan that demonstrates how the applicant plans to meet the requirements of paragraphs (d) (e), (f), and (g), as appropriate, of 5 73.67 of this chapter.
The licensee shall retain a copy of this physical security plan as a record for the period during which the licensee possesses the appropriate type and quantity.c,f special nuclear material requiring.this record under each license and each change to the plan for three years after the change.
5.
In $ 70.32, paragraph (c)(3) is removed and paragraph.(g) is revised to read as follows:
i 6 70.32 Conditions of11icenses.
(g) The licensee shall prepare and maintain safeguards contingency plan procedures in accordance with Appendix C to Part.73 of this chapter for bringing about the actions and decisions contained-in the Responsibility Matrix of its safeguards contingency plan. The licensee shall retain a copy of the safeguards contingency plan procedures as a record for_the period:during which the-licensee possesses the appropriate type and quantity of special nuclear material requiring this record under each license'for which the-procedures were
~
developed and each change to'the plan for three years from the' effective date
.of the change. The licensee may not make a change that would decrease the_
safeguards effectiveness of the first_four categories of.information (Background, Gener.ic Planning Base,' Licensee Planning Base, and Responsibility.
T Matrix) contained. in any' licensee safeguards contingency plan prepared pursuant '
2O-j. to'paragsphs 70.22(g), 70.22(j), 72.184, 73.20(c), 73.26(e)(1),' 73.46(h)(1)',
or 73.50(g)(1) of this chapter without the prior-approval of. the Commission. A licensee desiring to make such a_ change shall submit an application for an 10 Enclosure s
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. amendment to its license pursuant to 9 70.34 The licensee may make changes to the licensee safeguards contingency plan without prior Commission approval if
'the changes do not decrease the safeguards effectiveness of the plan. The licenseeifdihmaintaineachchangetotheplanmadewithoutprior,approvalas a record during the period for which possession of a' formula quantity.of special nuclear material is authorized under a license and retain the.
superseded material for three years from the effective date of the change and shall furnish a report containing a description of each change within 60 days after the change is made to the Director of Nuclear Material Sefety and Safeguards, with'a copy to the Regional Administrator of the appropriate NRC Regional Office as specified e. Appendix A to Part 73.of this chapter.
PART 72 -- LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT:
NUCLEAR FUEL AND HIGH-LEVEL RADI0 ACTIVE WASTE 6.
The authority citation for Part 72 continues to read as.follows:
Authority: Secs. 51, 53, 57, 62, 63, 65, 69, 81, 161', 182, 183, 184, 186, 187, 189, 68 Stat. 929, 930, 932, 933, 934, 935, 948, 953, 954, 955, as amended,sec.234,83 Stat.444,aymended(42U.S.C.2071,12073,2077,:2092, 2093,'2095,2099,2111,2201,2232,62234,2236,2237,2238,2282);sec._274, Pub. L.86-373, 73 Stat. 688, as amended (42 U.S.C. 2021); sec. 201, as amended, 202, 206, 88 Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846); Pub. L.95-601, sec. 10, 92 Stat. 2951 (42 U.S.C. 5851); sec. 102, Pub. L.91-190, 83 Stat. 853 (42 U.S.C. 4332); secs. 131, 132, 133, 135, 137, 141, Pub. L.97-425, 96 Stat. 2229, 2230, 2232, 2241, sec. 148,' Pub.--L.
100-203, 101 Stat. 1330-235 (42 U.S.C. 10151, 10152, 10153, 10155,.10157,.
10161,10168).
Section 72.44(o) also issued under secs.142(b) and 148(c)', (d),' Pub. L.
100-203,101 Stat.1330-232,1330-236-(42.U.S.C.10162(b),.10168(c),(d)).
Section 72.46 also' issued under sec. 189, 68, Stat. 955 (42 U.S.C. 2239); sec. 134, Pub. L.97-425, 96 Stat. 2230 (42.U.S.C. 10154). Section.72.96(d) also I
issued under'sec.-145(g), Pub.
L'. 100-203, 101 Stat. 1330-235 (42 U.S.C..
~10165(g)). Subpart J also issued under secs. 2(2),2(15),2(19),117(a),
2203, 2204, 2222, 2244,.(42 U.S.C..
141(h), Pub. L.97-425, 96 Stat. 2202, d c k M 4 a d d /W iu f M a'A 10101,10137(a),10161(h)),
'#5 A
at My99 SW. 2MC(42 USC 10/55)"*Cl 4W NfSU' W (4 M,C,/0/9e),
11 Enclosure
[7590-01]
For the purposes-of sec. 223, 68 Stat. 958, as amended (42 U.S.C. 2273);
5672.6,72.22,_72.24,72.26,72.28(d),72.30,72.32,72.44(a),.(b)(1),(4),
(5), (c), (d)(1), (2), (e), (f), 72.48(a), 72.50(a), 72.52(b), 72.72(b), (c),
72.74(a),(b),72.76,72.78,72.104,72.106,72.120,72.122,72.124,,72.126, 72.128,72.130,72.140(b),(c),72.148,72.154,72.156,72.160,72.166,72.168,.
72.170, 72.172, 72.176, 72.180, 72.184, 72.186, are issued under sec. 161b, 68 Stat.948,asamended(42U.S.C.2201(b));sf72.10(a),(e),72.22,72.24, 72.26, 72.28, 72.30, 72.32, 72.44,(a),(b)(1), (4), (5), (c), (d)(1),(2),(e),
(f), 72.48(a), 72.50(a), 72.52(b), 72.90(a)-(d), (f), 72.92, 72.94, 72.98, 72.100, 72.102(c), (d), (f), 72.104, 72.106, 72.120, 72.122, 72.124, 72.126, 72.128,72.130,72.140(b),(c),72.142,72.144,72.146,72.148,72.150,72.152, 72.154, R.156, 72.158, 72.160, 72.162, 72.164, 72.166, 72.168, 72.170, 72.172, 72.176, 72.180, 72.182, 72.184, 72.186, 72.190, 72.192, 72.194 are issued under sec.161i, 68 Stat. 949, as amended (42 U.S.C. 2201(i)); and $6 72.10(e),
72.11,72.16,72.22,72.24,72.26,.72.28,72.30,72.32,72.44(b)(3),(c)(5),
(d)(3),(e),(f),72.48(b),(c),72.50(b),72.54(a),(b),(c),72.56,72.70, 72.72,72.74(a),(b),72.76(a),72.78(a),72.80,72.82,72.92(b),72.94(b),
72.140 (b), ( c), (d), 72.144(a), 72.146, 72.148, 72.150, 72.152, 72.154 (a),
(b),72.156,72.160,72.162,72.168,72.170,72.172,72.174,72.176,72.180, 72.184, 72.186, 72.192nare issued under sec. 1610, 68 Stat. 950, as amended.(42 y
U.S.C.2201(o)).
( qg,; y (f), n, ; m, 7 p p y n, 4 m g,
7.
In S 72.184, paragraph (a) is revised to read as follows:
5 72.184 Safeguards contingency plan.
(a) The requirements of the licensee's safeguards contingency plan for dealing with threats and radiological sabotage must be as defined in Appendix C to Part 73 of this chapter.- This plan must include 8ackground, Generic Planning Base, Licensee Planning Base, and Responsibility Matrix, the first four categories of information relating to nuclear facilities licensed under Part 50 of this chapter.
(The fifth category of information, Procedures, does j
nothavetobesubmittedforapproval.)
PART 73 -- PHYSICAL PROTECTION OF PLANTS AND MATERIALS.
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[7590-01]
8 '. The authority citation-for Part 73 continues to read as follows:
Authority: Secs. 53, 161, 68 Stat. 930, 948, as amended, sec.'147, 94 Stat. 780 (42 U.S.C. 2073, 2167, 2201); secs. 201 as amended 204, 88. Stat.-
1242, as amended, 1245 (42-U.S.C. 5841, 5844).
i Section 73.1 also issued under secs. 135,'141, Pub. L.97-425, 96 Stat.
2232, 2241, (42 U.S.C. 10155, 10161). Section 7?.37(f) is also issued under.
sec. 301, Pub. L.96-295, 94 Stat. 789 (42 U.S.C. 5841 note). Section 73.57 is issued under sec. 606, Pub. L.99-399, 100 Stat. 876 (42 U.S.C. 2169).
For the purposes of sec. 223, 68 Stat. 958, as amended (42 U.S.C. 2273);
.sh 73.21, 73.37(g), and 73.55 are issued under sec. 161b, 68 Stat. 948, as-amended (42 U.S.C. 2201(b)); %$ 73.20,'73.24, 73.25, 73.26, 73.27, 73.37,.
f 73.40, 73.45, 73.46, 73.50, 73.55, and 73.67 c.re issued under sec.161i, 68 I
Stat. 949, as amended (42 U.S.C. 2201(i)); and sg 73.20(c)(1), 73.24(b)(1),.
73.26(b)(3), (h)(6), and (k)(4), 73.27(a) and ~ (b), 73.37(f), 73.40(b). and (d),.
73.46fg)(6)and(h)(2),73.50(g)(2),(3)(iii)(B),and(h);73.55(h)(2)_and' (4)(iii)(B), 73.57, 73.70, 73.71, and 73.72 are issued under sec.1161o; 68 Stat.- 950,-as amended (42 U.S.C. 2201(o)).
- 9. Section 73.2.is amended by adding a definition for'" Contiguous sites" in proper alphabetical sequence, and revisin'g the definitions of " Formula quantity," "Special nuclear material of moderate strategic significance," and "Special nuclear material of low strategic significance" to read as follows:
9 73.2 Definitions.
" Contiguous sites" means locations' subject _to the control'of a licensee,-
in close proximity to each other, and for the possession, use, or_ storage of-special nuclear material where the licensee's same security measures or organizational elements, including the alarm station and response personnel, are used to provide the capabilities necessary.to'satisfyf applicable security-requirements.
" Formula quantity" means strategic special nuclear material in 'any combination in a quantity of _5000 grams or more computed by the formula, grams j
= (grams contained U-235) + 2.5 (grams U-233 + grams plutonium). In 13 Enclosure
[7590-01]-
1 t
unirradiated form this class of material is sometimes referred to as a Category 1 quantity of material.
"Special nuclear material of low strategic significance" means:
(1)'Less than an amount of special nuclear material of moderate strategic significance as defined in paragraph (1) of the definition of strategic nuclear material of moderate strategic significance in this section, but more than 15 grams of uranium-235-(contained in uranium enriched to 20 percent or more in U-235 isotope) or 15 grams of uranium-233 or 15 grams of. plutonium.or the i
combination of 15 grams when computed by the equation, grams = (grams contained U-235) + (grams plutonium) + (grams U-233); or (2) Less than 10,000 grams but more than 1000 grams of uranium-235 (contained in uranium enriched to 10 percent or more but ~less than 20 percent in the U-235 isotope); or (3)10,000 grams er more of uranium-235 contained in uranium enriched abor natural but less than 10 percent in the U-235 Isotope.
l MT n unirradiated form this class of material is sometimes referred to as a-
~
Category III quantity of material.
"Special nuclear material of moderate strategic significance" means:
1 ).
Less than a formula quantity of strategic special nuclear but more than 1000 grams of uranium-235 (contained in uranium enriched to 20 percent or more in i
the U-235 isotope) or more than 500 grams of uranium-233 or plutonium or.in;a combined quanti _ty of more than 1000 grams when computed by the equ tion, grams
= (grams contained U-235) + 2 (grams U-233 + grams plutonium), or (2) 10,000 grams or more of uranium-235 (contained in uranium enriched to 10 percent _or more but less than 20 percent in the U-235 js_o_t_o M n unirradiated form this bfili of material'IRbitiblTr6Es referred to as a Category II quantity of I
material.
1 10.
In 5 73.20, paragraph (b)(3) is redesignated as paragraph (b)(4), a-new paragraph (b)(3)'is added, and paragraphs'(b)(2) and (c) are revised to read as follows:
i l
I f
14 Enclosure J
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[7590-01]!
IS 73.20 General performance objective and requirements.
(b)
- ( 2 ). Is designed with sufficient redundancy and diversity to ensure maintenance of the capabilities described in 55 73.25 and 73.45;
-(3)
Includes a safeguards contingency capability that can meet the criteria in Appendix'C to this part " Licensee. Safeguards Contingency Plans,"
and (c) Each licensee subject to the requirements of paragraphs (a) and (b) of this section shall establish, maintain, and follow NRC-approved safeguards-physical protection and safeguards contingency plans that describe how the licensee will comply'with the requirements of paragraphs (a) and (b)~of this section.
11.
In 5 73.26, paragraph (h)(b) is revised to read as follows:
5 73.26 Transportation physical protection systems, subsystems, components, _
and procedures.
(h) Test and Maintenance Programs'. ***
l (6) The transportation security program must be. reviewed at least every 12 months by individuals independent:of both security _ program management'and personnel who have direct. responsibility for implementation; of the security 1 program. The' review must include a review and audit of' security: procedures and practices, an evaluation of the effectiveness of. the physical" protection:
system, an audit of the physical-protection system testing and maintenance 4
. program, and an audit of. commitments established for response by local law enforcement authorities. The results of the-review and the audit along-with recommendations.for improvements and corrections must be documented, reported
.to the responsible organization management, and kept available for inspectioni for a period of three years.
573.40[ Amended),
12.
In 5 73.40, paragraphs (b), (c), and (d) including footnote 1, a're-l removed.
i i
t 15 Enclosure-
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[7590-01]
13.
In's 73.46, paragraphs-(g)(6) and (h)(1) are revised to read as follows:
e 6 73.46 Fixed site physical protection systems,- subsystems, ' components, and procedures.
(g) Test and Maintenance Programs. ***
(6) The security program must be reviewed at least every 12 months by individuals independent of both security program management and personnel who-have direct responsibility for implementation of the security program. The review must include a review and, audit of security procedures and practices,.an evaluation of the effectiveness of the physical protection system, an audit of the physical protection system testing and maintenance program, and an audit of:
~'
commitments established for response by local law enforcement authorities. The results of the review, audit, and evaluation along with recommendations for improvements and corrections, if any, must be documented and reported to the j
licensee's plant management and to corporate managementLat least one level' higher than that' having responsibility for the day-to-day plant operations.-
The reports must be kept available at the planz for inspection for a period of; l
e three years, i
(h) Contingency and response plans and procedures.
(1) Theilicensee'-
shall establish, maintain, and follow an NRC-approved safeguards contingency plan for dealing with threats, thefts, and-radiological sabotage related.to the.
strategic special nuclear material and' nuclear facilities subjectito the j
provisions of this section.
Safeguards contingency; plans must be in accordance'
]
with the. criteria in Appendix C to this part " Licensee Safeguards Contingency:
Plans.- Contingency plans must include, but not be. limited _to, the response.
- requirements in paragraphs-(h)(2) through (h)(5) of this'section. aThe: licensee shallsretain a copy of the current safeguards _ contingency plan as a~ record..
until the Commission terminates. the_ license and, if'any portion of thej plan;is i
~
L
- superseded,1 retain the superseded material for three yearsL af ter each ; change.
.14.-
In $!73.50,: paragraphs (g)(1); and.(h) are revised to rea'd: as-follows:
9-.73.50 Requirements for_ physi _ cal _ protection of licensed activities.-
f 16.
Enclosure
,e...
u E
[7590-01]
t (g)' Response requirement.
(1) The' licensee shall establish, maintain, and follow an NRC-approved safeguards contingency plan for dealing with
- threats, thefts, and radiological sabotage related to the special nuclear material and nuclear facilities subject to.the provisions =of this section.
Safeguards contingency plans must be in accordance with the' criteria in v
V Appendix C to this part," Licensee Safeguards Contingency Plans." The licensee shall retain a copy of the current safeguards contingency plan and each change to the plan as a record until the Commission terminates the license and,.if any f
portion of the plan is superseded, retain the superseded material for three j
years after each change.
.i (h) Each licensee shall establish, maintain, and follow an NRC-approved
. training and qualifications plan outlining the processes by which' guards, watchmen, armed response persons, and other members of.the security-organization will be selected, trained, equipped, tested, and qualified to ensure that these individuals meet.the requirements of paragraph (a)(4) of this:
section.
15.
In s 73.55, paragraphs (b)(4)(ii), (d)(7)(i)' introductory text, (g)(4), and (h)(1) are revised to read as follows:
5 73.55 Requirements for physical protection of licensed activities in nuclear power-reactors against radiological sabotage.
-(b)***
(4)***
(ii) Each licensee shall establisn, maintain, and-follow an NRC-approved-training and qualifications plan outlining the processes by which guards, l
watchmen, armed response persons, and other members of the security organization will be selected, trained, equipped, test"d, and qualified.to ensure that these individuals meet the requirements of this' paragraph. The-licensee shall maintain a current copy of.the training and qualifications plan.
as a record until the Commission terminates the license'for.which the plan was
-developed and, if any portion of the plan-is superseded, retain the material-
]
that is superseded for three years after each change. The training and
~
qualifications plan must include a schedule to show how all security; personnel j
1 17
. Enclosure-H
4 17590-01]-
y will be qualified two years after the submitted plan is approved. The trair.ing and qualifications' plan must be followed by the licensee 60 days after the submitted plan is approved by the NRC.
(d)
(7)
(i) Establish an access authorization system to limit unescorted access to vital areas during nonemergency conditions to individuals.who require access in order to perform.their duties. Access to vital areas for the purpose of l
general familiarization and other nonwork-related activities may not be authorized except for good cause shown to the licensee. To achieve this, the licensee must:
(g)
(4) The security' program must be reviewed at least every 12 months.by-individuals independent of both security program management and personnel who have direct responsibility for implementation of the-security program.. Thel
- review must include a' review and audit of security procedures and practices,;
evaluation of the effectiveness of the physical protection system, an audit of the physical protection system testing and maintenance program, and 'an-audit of commitments established'for response by local law enforcement authorities.
The results of the review audit and evaluation along with recommendations for improvements and corrections, if any, must be documented and reported to the licensee's plant management and to corporate management at least one level.
higher than.that having responsibility for the day-to-day plant operation..The
- reports must be kept available at the plant for inspection for a period of three years.
(h) Response requirement.
(1) The licensee shall establish, maintain, and. follow an NRC-approved safeguards contingency plan for dealing with
. threats, thefts, and. radiological sabotage related to the nuclear facilities subject to the provisions of-this section. ' Safeguards contingency plans.must'
- be in'accordance with the criteria in. Appendix C to this part," Licensee
. Safeguards Contingency Plans."
^
- 16. In $ 73.60, the introductory paragraph and paragraph (e) are revised' to read as follows:
I
~
18-Enclo'sure.
a
[
[7590-01]'
$ 73.60 Additional requirements for the physical protection of special nuclear material at'nonpower reactors.
Each nonpower reactor licensee who,' pursuant to the requirements.of Part 50, possesses at any site'or contiguous sites subject to control by'the licensee uranium-235 (contained in uranium enriched to 20 percent or more in the U-235 isotope), uranium-233, or plutonium alone.or in any combination in a quantity of. 5,000 grams or more computed by.the formula, grams = (grams contained U-235) + 2.5 (grams U-233 + grams. plutonium),
shall protect..the special nuclear material from theft or diversion pursuant to the requirements ofparagraphs73.67(a),(b),(c),and(d)andthissection,exceptthca licensee is exempt from the requirements of paragraphs (a), (b), (c), (d), and (e) of this section to the extent that it possesses or uses special nuclear material that is not readily separable from other radioactive material and that-has a total external radiation dose rate in excess of 100 rems per hour at a distance of three feet from any accessible surface without' intervening i
shielding.
.(e) Response requirement.
Each licensee shall establish, maintain, and follow an NRC-approved safeguards contingency plan for dealing with threats, thefts, and raiiological sabotage related to the special nuclear material and nuclear facilities subject to the provisions of this section.
Safeguards contingency plans must be in accordance with the criteria in Appendix C.to this part " Licensee Safeguards Contingency Plans."
7 4*
17.
In 6 73.67, the introductory text of-paragraphs-(c),-(d), and (f) and paragraph (c)(2) are revised to read as follows:
9 73.67 Licensee fixed site and in-transit requirements for the physical
- protection of special nuclear material of moderate and low strategic
-significance.
(c) Each licensee who possesses, uses, transports, or delivers to'a
. carrier for transport special.' nuclear material of moderate strategic sig-
.nificance or 10 kg or more of special nuclear material of low strategic significance shall:
I 1.9 Enclosure
7
~
[7590-01]
+
(2) Within 30 days after the plan submitted pursuant to' paragraph (c)(1)~
J of.this section'is approved or when specified byLthe NRCL in writing, implement the approved security plan.
'(d) Fixed site requirements for special nuclear material of moderate strategic significance. Each licensee who possesses,. stores, or uses c
. quantities and types of special nuclear material of moderate strategic significance at a fixed site or. contiguous sites except as allowed by. paragraph (b)(2) of this section and except those who are licensed.to operate a nuclear power reactor pursuant to Part 50, shall:
(f) Fixed site requirements for special nuclear material of-low strategic significance.
Each licensee who possesses, stores, or uses special nuclear material of low strategic significance at a fixed site or contiguous sites, except those who are licensed to operate a nuclear power' reactor
-pursuant to Part 50, shall:
- 18. In 5 73.70, paragraph (c) is revised to read as-follows:
5 73.70 Records.
(c) A register of visitors, vendors, and other individuals not. employed by the licensee. The. licensee shall retain this register as a record for three years after the last entry is made in the register.
19.
In Appendix B to Part 73, the Introduction is revised to read as follows:
APPENDIX B - GENERAL CRITERIA FOR SECURITY PERSONNEL Introduction
. Security personnel who are responsible for: the protection of special.
-i nuclear material on site and.in transit and for the protection of the facility l
or shipment vehicle against. radiological' sabotage should,Llike other, elements b
of the physical security system,~ be required to meet minimum criteria to ensure 20 Enclosure
k
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.e
-[7590-01]~
'that they will effectively perform their assigned security-related job duties.
.In order to ensure that those' individuals responsible for security are properly equipped and qualified to execute the job duties' prescribed for.them, the NRC has developed general criteria that specify security personnel qualification requirements.
L These general criteria establish requirements for the selection, training, equipping, testing, and qualification of individuals who will be responsible for protecting special nuclear materials, nuclear facilities, and nuclear shipments.
When required to have security personnel that have been trained, equipped, and qualified to perform assigned security job duties in accordance with the criteria in this appendix, the licensee must establish, maintain, and follow a plan that shows how the cr Heria will be met. The plan must be submitted.to' the NRC for approval. The plan must be implemented within 30 days'after approval by the Commission unless otherwise specified by the Commission in writing.
- 20. In Appendix C to Part-73, the Introduction is revised and a new section on Audit and Review is added to read as follows:
APPENDIX C -- LICENSEE SAFEGUARDS CONTINGENCY PLANS Introduction A licensee safeguards contingency plan is a documented plan to give guidance to licensee personnel in order to accomp1ish specific defined objectives in the event of threats, thefts, or radiological sabotage relating-to.special nuclear material or nuclear facilities licensed under the' Atomic Energy Act of 1954, as amended. An acceptable. safeguards contingency plan must contain (1) a predetermined set of decisions and actions. to satisfy. stated objectives, (2) an identification of the data, criteria,' procedures, and mechanisms necessary to effect efficiently the decisions and actions, and (3).a specification of the individual, group, or organizational entity responsible for each decision and action.
The goals of licensee safeguards contingency plans for dealing with
_ threats, thefts, and radiological sabotage are:(1) to organize the response-A 21 Enclosure p
[7590101]'
. effort.at the licensee level, (2) to provide predetermined structured responses
.Dy licensees to safeguards contingencies, (3) to. ensure.the integrat' ion of the
~
licensee response with the re'sponses by other entities, and (4) to achieve a measurable performance in response capability. Licensee safeguards contingency planning should result in organizing the licensee's~ resources in'such a way that the participants will be identified, their several responsibil.ities-specified, and the responses coordinated. The responses 1should be timely and consistent internally and consistent with'each other.
It is important to note that a licensee's safeguards contingency. p1an 'is >
l intended to be complementary to:any emergency plans developed pursuant to Appendix E to Part 50 of this chapter or to paragraph.70.22(1).oflPart 70 of this chapter.
Contents of the Plan Audit and Review At' intervals not to exceed 12 months, the licens'ee shalll provide for a-review' of the safeguards contingency plan.by individuals independent 'of both security.
program management and personnel who have direct responsibility for imple-mentation of the security program. The review must include a review and audit.
of' safeguards contingency procedures and practices and a' test of the safeguards-system along with commitments established for response by local law enforcement authorities.
The licensee shall document and report the results of the review and'
~
audit along with recommendations for improvements and corrections, if any, to
- the licensee's corporate and plant management at.least one. level higher than-that having-responsibility for the day-to-day operation of the' plant. The report must be kept available at the plant for inspection for a period ofrthree.
.. yea rs.
PART 75--- SAFEGUARDS ON ' NUCLEAR MATERIAL - IMPLEMENTATION'
'0F US/IAEA AGREEMENT
- 21. The authority citation for.Part 75 continues to read as follows:
22:
Enclosure
4 1
-3
[7590-01]L 7
1 Authority: -Secs 53,163, 103, 104,'122, 161, 68 Stat. 930, 932, 936,1937,-
939,:948, as amended-(42 U.S.C.-2073, 2093, 2133, 2134, 2152, 2201;:sec. 201, 88 Stat. 1242-as amended, (42 U.S.C. 5841).-
Section 75.4 also issued under secs. 135, 141, Pub. L.97-425, 961 Stat.
7 2232, 2241 (42 U.S.C. 10155, 10161).
For~ purposes of sec. 223, 68 Stat. 958, as amended'(42 U.S.C. 2273),
the.
provisions of this part are issued under sec.1610, 68 Stat. 950, as' amended (42 U.S.C. 2201(o)).
22.
In 5 75.4, paragraph (f)(1) is revised to read as follows:
75.4 Definitions.
+
e
+
s.
(f) " Effective kilogram" means a unit used in safeguarding nuclear material. The quantity;is:
-(1) For special nuclear material: The amount specified in b 70.4 of.this chapter.
+
e
+:
+
Dated at Rockville, Maryland this day-of
, 1991.
t For the NucleariRegulatory Commission.
~
' James.M. Taylor, Executive' Director for.0perations.
I L
23 Enclosure-4
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8
.' Document Name:
c MA/FRN' Requestor? s '. ID:
BONSBY'-
Author's~Name:
Sturel
.1 Document Comments:
i CB'1/08/91 MINOR AMENDMENTS FEDERAL REGISTER NOTICE-i
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T' UNITED STATES f.
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.,E NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555
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l-The Honorable Peter H. Kostmayer, Chairman Subcommittee on Energy and the Environment Committee on Interior and Insular Aff airs United-States House of Representatives Washington, DC 20515 y
Dear Mr. Chairman:
The NRC has sent to'the Office of the Federal Register for publication the enclosed final amendments to the Commission's rules in 10 CFR Parts 70, 72, 73, and 75. The final changes will:
(1) add definitions for common terms not currently defined but ' frequently used, (2) make the definitions sections easier-to use by arranging the terms in alphabetical order, (3)' delete action dates that no longer apply, (4) correct outdated terms and cross references, (5) clarify wording.that is susceptible to differing interpretations, (6) correct typographical errors, and (7) make other minor changes.
These minor amendments. affect the public, industry,'and the NRC only insofar as they make the regulations easier to understand, implement, and. enforce.
Sincerely, Eric S. Beckjord, Director Office of Nuclear Regulatory Research
Enclosure:
Final Amendment to rules in 10 CFR Parts 70, 72, 73, 75 cc: The Honorable John J. Rhodes
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UNITED STATES j gh' 8, E '-
. NUCLEAR REGULATORY COMMISSION o, 'jO..
WASHINGTON, D.C. 205S5 P"
?q; '82....4-The Honorable Philip R. Sharp, Chairman Subcommittee on Energy and Power Committee on Energy and Commerce.
United States House of Representatives Washington, DC 20515
Dear Mr. Chairman:
The NRC'has sent to the Office of the Federal Register for publication the enclosed final amendments to the Conmission's rules in 10 CFR: Parts 170, 72, 73, and 75. The final changes will:
(1) add definitionsLfor common. terms not-currently defined but frequently used, (2) make the definitions sections easier to use by arranging the terms in alphabetical order, (3) delete' action. dates that no longer apply, (4) correct outdated terms and cross references,-
(5) clarify wording that is' susceptible to differing interpretations, (6) correct typographical errors, and (7) make other. minor changes.
These minor amendments affect the public, industry,'and the NRC only insofar as O
they make the regulations ~ easier to understand, implement, and enforce.
Sincerely, Eric S. Beckjord, Director Office of Nuclear Regulatory Research i
Enclosure:
Final Amendment to rules in 10 CFR Parts
-70, 72, 73, 75 cc: The Honorable Carlos J. Moorhead A
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- cjk $[)J l NUCLEAR REGU TO Y OMMISSION
a WASHINGTON, D.C. 20555 i
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'The Honorable'BobiGraham, Chairman y?
- Subcomittee on Nuclear Regulation.
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' Comittee on. Environment-and - Public. Works.
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-United States: Senate i'
!. Washington,fDC; 20510' s'
Dear Mr.:
Chairman:.
- R The NRC hassent to the Office of the Federal' Register for' publication'thei 2 enclosed final' amendments to the' Commission's rules in 10'CFR Parts 70i 72,3 1
73 kand 75., The final changesiwil1:.(1) add. definitions foricommon,termsinoti l
currently-defined but frequently 'used, (2) make _the' definitio' s sections ~ easier -
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to use'by arranging the terms-in alphabetical: order,-(3) deletelaction dates:
that 'no longer apply, '(4)' correct outdated ' terms and cross references,
~
-(5) clarify wording lthat isLsusceptible to-differing interpretations,.
1 (6) currect. typographical errors,.and :(7) make other; minor changes.s
-These minor' amendments affect the public, industry, and the=NRC'only insofar asi they.make. the ' regulations easier' to understand, implement, and-Lenforce Sincerely,'
j Eric 5.' Beckfordh Director.
Office of Nuclear Regulatory Rescarch'-
j
Enclosure:
i Einal Amendment to rules in 10 CFR Parts 1
70,_72, 73, 75 The Honorable Alan K. Simpson..
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' WEEKLY STAFF NOTE TO THE COMMISSION OFFICE 0F_ NUCLEAR REGULATORY RESEARCH-Proposed Rule To Be Signed by E00 Gn
, 1991, The Executive Director for Operations approved a finalL.
rule that would amend 10 CFR Parts 70 72, 73, and 75, " Minor Amendments to-the Physical Protection Requirements." The proposed changes!will: :(1) ; add
~
definitions for common terms not _currentlyL defined but frequently used, (2) t make the definitions sections easier to use by arranging the terms in alphabe-
.tical order, (3) delete action dates that no longer apply, (4) correct outdated-terms and cross references, (5) clarify wording that is susceptible to differing interpretations, (6) correct typographical' errors, and (7) make other minor changes. These final amendments are necessary to reflect the results of a systematic review of NRC's Safeguards regulations.
This constitutes notice to the_ Commission that, in accordance with the rulemaking authority delegated to _the EDO, the E00 has received this final rule and proposes to forward it to the Office _of the Federal Register for FR.
publication, unless otherwise directed by the Commission.
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_... _ _ _. _,