ML20212A852
| ML20212A852 | |
| Person / Time | |
|---|---|
| Issue date: | 09/08/1997 |
| From: | Rathbun D NRC OFFICE OF CONGRESSIONAL AFFAIRS (OCA) |
| To: | Gingrich N, Gore A, Murphy R GENERAL ACCOUNTING OFFICE, HOUSE OF REP., SPEAKER OF THE HOUSE, SENATE, PRESIDENT OF THE SENATE |
| References | |
| CCS, NUDOCS 9710270025 | |
| Download: ML20212A852 (3) | |
Text
<
- 88o9 p k UNITED STATES s* NUCLEAR REGULATORY COMMISSION
+ WADHINGTON O.C. setto ee01 4,..... September 8, 1997 ,
The Honorable Al Gore President of the United States Senate Wasliington, DC 20510
Dear Mr. President,
Pursuant to Subtitle E of the Small Business Regulatory Enforcement Fairness Act of 19%, 5 U.S.C. 801, the Nuclear Regulatory Comission (NRC) is submitting final amendments to the Comission's rules in 10 CFR Part 50. The NRC is amending its regulations to correct an error in several sections in the regulations governing nuclear power plant licensing which define the term.
- safety related systems, structures, and components."
Wehavedeterminedthatthisruleisnota"majorrule"asdefinedin5U.S.C.
804(2). We have confirmed this determination with the Office of Management and Budget.
Enclosed is a copy of the final rule that is being transmitted to the Office of the Federal Register for publication. This final rule will become effective when it is published in the Federal Register.
Sincerely, N
Dennis K. Rathbun, Director Office of Congressional Affairs
Enclosure:
Final itule Iojo2ggg25 g ggs' ((\,\(\(ll}lhlh PDR
,
- t seg g 1 UNITED STATES g ,
NUCLEAR REGULATORY COMMISSION
, WASHINGTON. D.C. 30006 4 001
% ,,,,, September 8, 1997 The Honorable Newt Gingrich Speaker of the United States House of Representatives Washington, DC 20515
Dear Mr. Speaker:
Pursuant to Subtitle E of the Small Business Regulatory Enforcement Fairness Act of 1996. 5 U.S.C. 801, the Nuclear Regulatory Commission (NRC) is submitting final amendments to the Commission's rules in 10 CFR Part 50. The NRC is amending its regulations to correct an error in several sections in the regulations governing nuclear power plant licensing which define the term.
" safety related systems, structures, and components.*
We have detennined that this rule is not a " major rule" as defined in 5 U.S.C.
804(2). We have confirmed blis determination with the Office of Management and Budget.
Enclosed is a copy of the final rule that is being transmitted to the Office of the Federal Register for publication. This final rule will become effective when it is published in the Federal ftegister.
Sincerely.
M/ s Dennis K, Rathbun. Director Office of Congressional Affairs
Enclosure:
Final Rule
)
0 0sr Odck i
y sq Mouq\ UNITED STATES s
P; NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. SteeHe01
%,,,,,,, september 8, 1997 Mr Robert P. Murphy General Counsel General Accounting Office ,
- Room 7175 !
. 441 G. Street. NW. :
Washington. DC 20548
Dear Mr. Murphy:
Pursuant to Subtitle E of the Small Business Regulatory Enforcement Fairness Act of 1996, 5 U.S.C. 801, the Nuclear Regulatory Commission (NRC) is submitting final amendments to the Commission's rules in 10 CFR Part 50. The NRC is amending its regulations to correct an error in several sections in the regulations governing nuclear power plant licensing which define the term,
" safety related systems, structures, and components."
We have determined that this rule is not a " major rule" as defined in 5 U.S.C.
804(2). We have confirmed this determination with the Office of Management and Budget.
Enclosed is a copy of the final rule that is being transmitted to the Office of the Federal Register for publication. This final rule will become effective when it is published in the Federal Register, ,
Sincerely, Dennis K. Rathbun, Director Office of Congressional Affairs
Enclosure:
Final Rule
. =-, ._ - _ ._ . .
CONGRESSIONAL CORRESPONDENCE SYSTEhi DOCUMENT PREPARATION CHECA7.lST This check list is to be submitted with each document (or group of Gs/As) sentforprocessing into the CCS.
- 1. BRIEF DESCRIPTION OF DOCUMENT (S) 'l . b< ~
(d
- 2. TYPE OFDOCUhfENT K CORRESPONDENCE HEMINGS (Qs/As)
- 3. l.;UMENT CONTROL _ SENSITIVE (NRC ONLY) X NON-SENSITlW
- 4. CONGkESSIONAL COMMITIEE AND SUBCOMMITIEE ((f applicable)
Congressional Committee Subcommittee
- 5. SUBJECT CODES (A)
(B)
(C) _ _
6, SOURCE OFDOCUMENTS (A) 5S20 (DOCUMENT NAME )
(B) SC4N (C) ATTACHMENTS (D) OTHER 0QDA7ES
- 7. SYSTEM 1,0/ DATA OC4 SENTDOCUMENT TO CCS (A)f'l'? Il (B) DATE CCS RECEIVED DOCUMENT (C) _ DATE RETURNED TO OC4 FOR ADDITIONAL INFORMATION (D) DATE RESUBM!TTED BY OC4 TO CCS (E) DATE ENTERED INTO CCS BY (F) DA7E OC4 NOTIFIED THAT DOCUMENT 15 IN CCS O! U**
COMMENTS:
RELEASE TO PDR
. 9 0 0(2j n. ' ' 3 m 1
l
. , i j . [7590 01.P) !
t c
NUCLEAR REGULATORY COMMISSION .
a 10 CFR Part 50 j i RIN 3150 AF75 Definition of Safety Related structures, Systems, [
and Components; Technical Amendment >
AGENCY: Nuclear Regulatory Commission. ,
M ACTION: Direct final rule. .
I i
SUMMARY
- The Nuclear Regulatory Commission is amending its regulations to correct an error !
In the language of several sections in the regulations governing nuclear power plant licensing that define the term,
- safety related structures, systems, and components." These definitions are !
inconsistent with the definition in regulations appiicable to the siting of nuclear power plants and
)
i the Commission's longstanding practice and interpretation of that term, i
EFFECTIVE DATE: This direct final rule is effective [60 days after publication in the Federal Register), unless significant adverse comments are received by [30 days after publication in the
, Federal Register), if significant adverse comments are received, the effective date will be delayed and timely notice will be published in the Federal Register, 4
ADDRESSES: Mail comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff. Hand deliver comments to 11555 Rockville Pike, Maryland, between 7:30 am and 4:15 pm on Federal 4
workdays,
, For information on submitting comments electronically, see the discussion under Electronic Access in the Suppicmentary Information Section.
Copies of any comments received may be examined at the NRC Public Document Room, 2120 L Street NW (Lower Level), Washington, DC.
FOR FURTHER INFORMATION CONTACT: Geary S. Mizuno, Office of General Counsel, U.S.
Nuclear Regulatory Commission, Washington DC 20555 0001, telephone (301) 415163g,; e mail 4
GSM@nrc. gov, or Clark Prichard, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555 0001, telephone (301) 415-6203; e mail CWP@nre gov.
SUPPLEMENTARY INFORMATION:
This direct final rule corrects an error in the language of several regulations in 10 CFR Part 50 defining the term
- safety related structures, systems, and components," which is inconsistent with the concept of ' safety related structures, systems, and components"in 10 CFR Part 100, Appendix A.
Currently, " safety-related structures, systems, and components"in 10 CFR 50.2 (Definitions) and 10 CFR 50.65 (Maintenance Rule), and
- safety related electrical equipment"in 10 CFR 50Ag (Environmental Qualifications Rule) are defined as those structures, systems and components that are relied upon to remain functional during and following design basis events to ensure:
(1) The integrity of the reactor coolant pressure boundary,
, (2) The capability to shut down the reactor and maintain it in a safe shutdown condition, and 2
l l
. (3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the applicable guideline exposures set forth in $
50.34(a)(1) or $ 100.11 of this chapter, as applicable. (emphasis added)
The corrections would replace the conjunctive word, and," by the disjunctive word, "or,"
in these regulations, thereby clarifying that a structure, system, or component which falls into any one (or more) of the three categories set forth in the definition shall be regarded as " safety.
related." The correction would also delete the word, " postulated,"in the definition of safety-related structures, systems, and components"in 10 CFR 50.2. The torrections do not constitute i
l a change in Commission policy with respect to the scope of structures, systems, and 1
components to be regarded as " safety related." Rather, the corrections will conform the language in 10 CFR 50.2,50.49 and 50.65 to the language in 10 CFR Part 100, Appendix A, where the concept of " safety related structures, systems and components" was first incorporated into the Commission's regulations, in 10 CFR Pa 1100, Appendix A, which sets forth the seismic design requirements for nuclear power plants, the nuclear power plant applicant must determine the design basis for vibratory ground motion from the " Safe Shutdown Earthquake"(SSE). Once the SSE is determined, the nuclear power plant must be designed such that "if a Safe Shutdown Earthquake occurs, certain structures, systems and components will remain functional."ld.. Subparagraph VI.(a)(1). The regulation then defines these structures, systems and components which must be designed to withstand the SSE as those necessary to assure:
(i) the integrity of the reactor coolant pressure boundary, (ii) the capability to shut down the reactor and maintain it in a safe shutdown condition, or (iii) the capability to provent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of this part."(emphasis
~3
added).
id., ang g!te 10 CFR Part 100, Appendix A, Section 111, definition of ' safe shutdown earthquake." The regulation then denotes these structures, systems and components as " safety-related." 10 CFR Part 100, Appendix A, Subparagraph VI.(a)(1)(second textual paragraph).'
l The first regulation in 10 CFR Part 50 utilizing the term, " safety related" was 10 CFR Part l
l 50, Appendix B, the introduction of which stated that the requirements of the appendix applied to the " safety related functions" of structures, systems, and components which prevent or mitigate the consequences of postulated accidents. However, Appendix B did not actually include a definition of " safety related". The first regulation in 10 CFR Part 50 to include a definition of
" safety related structures, systems, and components" was 10 CFR 50.49. As originally promulgated, $ 50.49((b)(1) defined " safety related equipment" as those necessary "to ensure:
(i) the Integrity of the reactor coolant pressure boundary, (ii) the capability to shut down the reactor and maintain it in a safe condition, and (iii) the capability to prevent or mitigate the consequences of t.0cidents which could result in potential offsite exposures comparable to the 10 CFR Part 100 guidelines."(emphasis added)
(48 FR 2729; January 21,1983).
Thus, the core definition of " safety related equipment"in 10 CFR 50.49 was essentially the same as the definition of ' safety related structures, systems, and components"in 10 CFR Part 100, Appendix A. However, nothing in the statements of considerations for the proposed or final 10 CFR 50.49 explains why the "or" in the core definition of " safety related" was changed to "and." Sit 47 FR 2876; January 20,1982 proposed rule and 48 FR 2729; January 21,1983 -
1 See also 38 FR 31279 at 31280 (November 13,1973)(middle column) noting that Paragraph VI(a)(1) of the final rule was changed to " eliminate the requirement that safety related structures, systems, and components also be designed to withstand the effects of vibratory motion of fifty percent of the Safe Shutdown Earthquake in combination with other appropriate loads well within elastic limits."(emphasis added).
'4
e final rule. Nor was there any discussion in the statements of considerations which would suggest j that the Commission intended to narrow the scope of structures, systems and components that would be considered " safety related." Indeed, language in Revision i to Regulatory Guide (RG) 1 1.89, " Environmental Qualification of Certain Electrical Equipment important to Safety fnr Nuclear Power Plants"(June 1984) strongly suggests that the use of the conjunctive word,"and" was an error and was not intended to change the fundamental scope of safety related structures, systems and components. Appendix A to RG 1.89 " Typical Safety Related Electrical Equipment or System," purports to list systems and equipment that are " safety related." However, none of the equipment and systems actually listed as being
- safety related" would meet the definition of safety related structures, systems and components if the conjunctive "and" were interpreted to require all three criteria in the " safety related" definition to be satisfied. Moreover, a footnote to Appendix A of RG 1.89 states:
Paragraph 50.49(b)(1) identifies safety related electrical equipment as a subset of electrical equipment important to safety and defines it as the equipment that is relied upon to remain functional during and following design basis events to ensure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe conditiv or (3) the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the 10 CFR Part 100 guidelines. (emphasis added)
That the RG uses the disjunctive "or" when describing the underlying regulatory requirement of 10 CFR 50.49 is a strong indication that the NRC did not intend to change the scope of structures, systems, and components deemed to be " safety related," and that the use of 5
q 1
the conjunctive word, 'and,* was a grammatical error.
The conjunctive word, "and,' was subsequently used in the Maintenance Rule,10 CFR I
50.65, to describe the structures, systems, and components subject to the rule, as well as in the definition of " safety related structures, systems, and components" contained in 10 CFR 50.2, which was added by a 1996 rulemaking amending Parts 50 and 100. Because the statements of considerations for the proposed and final rules did not contain any discussion of the " safety.
related" definition, the Commission concludes that the subsequent rules simply repeated the definition used in 10 CFR 50.49 without intending any change in the scope of safety related structures, systems, and components. Att 53 FR 47822 (November 28,1988. proposed .
Maintenance Rule); 56 FR 31324 (July 10,1991 final Maintenance Rule); 57 FR 47802 (October 20,1992. first proposed rule amending parts 50 and 100); 59 FR 52255 (October 17,1994 second proposed rule amending parts 50 and 100); and 61 FR 65171 (December 11,1996. final rule amending parts 50 and 100).
The final rule amending 10 CFR Parts 50 and 100, which inter g!ja added the definition of
' safety related structures, systems, and components to 10 CFR 50.2, also added the word,
' postulated," to the term, " design basis events,'so that the term reads, " design basis (postulated) events." Nothing in the statements of consideration for the first or second proposed rules, or the final rule, explains the addition of the word, 'pottuiited,"in the Section 50.2
' definition of" safety related structures, systems, and components while leaving it out of the definitions of " safety related structures, systems, and conkponents'in 10 CFR 50.65 and 10 CFR
- Part 100, Appendix A, and ' safety related electrical equipment'in 10 CFR Sh49. Therefore, the Commission also concludes that the addition of the word," postulated" wa 4 an error and should be removed to conform the definition of " safety related structures, systems, and components' to the long standing wording of that term.
'6 l
l I
L_ .
For these reasons, the Commission has determined that the amendments to 10 CFR 50.h2,50.4g, and 50.65 are of a corrective nature, and do not involve any change in existing policy or otherwise constitute a new policy with respect to the scope of structures, systems, and components considered to be " safety related." Furthermore, since these amendments clarify the originalintent of the Commission, they can be considered to be an interpretation of existing regulations. Accordingly, the Commission finds that public notice and opportunity for comment
, are unnecessary pursuant to 10 U.S.C. 553(b)(3)(A) and (B) and the Commission is publishing this rule in final form without first seeking public comments on the amendment in a proposed l rule. However,if the NRC receives significant adverse comment by [30 days after publication),
j the NRC will publish a notice in the Federal Register that with:fraws this action, and will address the comments received in response to this direct fir,al rule as comments on a proposed rule (identical to this direct final rule) that is being concurrently published in the proposed rules section of this Federal Register. Any significant adverse comments will be deemed to be comments on the proposed rule and will be addressed in a subsequent final rule. The NRC will not initiate a second comment penod on this action.
Criminal Penalties For purposes of Section 223 of the Atomic Energy Act of 1954, as amended (AEA), the Commission is issuing the direct final rule under one or more of sections 161b,1611, or 161o of the AEA. Willful violations of the direct final rule are subject to criminal enforcement.
Electronic Access Comments may be submitted electronically, in either ASCll text or Word Perfect format 7
l l
. (version 5.1), by calling the NRC Electronic Bulletin Board on FedWorld or connecting to the NRC interactive rulemaking web site,"Rulemaking Forum." The bulletin board may be accessed using a personal computer, a modem, and one of the commonly available communications software packages, or directly via Intemet. Background documents on the rulemaking are also available for downloading and viewing on the bulletin board.
If using a personal computer and modem, the NRC subsystem on FedWorld can be accessed directly by dialing the toll free number: 1800 303 9672. Communications software parameters should be set as follows: panty to none, data bits to 8, and stop bits to 1 (N,B,1). Using ANSI or VT 100 terminal emulation, the NRC rulemaking subsystems can then be accessed by selecting the
- Rules Menu" option from the "NRC Main Menu." For further information about options available for NRC at FedWorld, consult the
- Help /information Center" from the "NRC Main l Menu." Users will find the *FedWorld Online User's Guides" particularly helpful. Many NRC subsystems and databases also have a Help /Information Center" option that is tailored to the particular subsystem.
The NRC subsystem on FedWorld can also be accessed by a direct dial phone number for the main FedWorld BBS: 703 3?13339; Telnet via Internet: fedworld. gov (192.239.93.3); File Transfer Protocol (FTP) via Intemet:ftp:fedworld. gov (192.239.92.205); and World Wide Web using: http://www.fedworld. gov (this is the Uniform Resource Locator (URL)).
If using a method other than the toll-free number to contact FedWorld, access the NRC subsystem from the main FedWorld menu by selecting *F Regulatory, Government Administration and Stata Systems," then selecting "A Regulatory information Mall." At that point, a menu will be displayed that has an option "A - U.S. Nuclear Regulatory Commission" that will take you to the NRC Online Main Menu. You can also go directly to the NRC Online area by typing "/go nrc" at a FedWorld command line. If you access NRC from FedWorld's Main Menu, 8
__b
=
, then you may retum to FedWorld by selecting the Retum to FedWorld" option from the NRC Online Main Menu. However,if you access NRC at FedWorld by using NRC's toll free number, then you will have full access to all NRC systems, but you will not have access to the main FedWorld system, if you contact FedWorld using Telnet, you will see the NRC area and menus, including the Rules menu. Although you will be able to download documents and leave messages, you will not be able to write comments or upload files (comments). If you contact FedWortd using FTP, a'l files can be accessed and downloaded but uploads are not allowed; all you will see is a list of files without descriptions (normal Gopher look). An index file listing all files within a subdirectory, with descriptions, is included. There is a 15 minute time limit for FTP access.
Although FedWorld can be accessed through the World Wide Web, like FTP that mode only provides access for downloading files and does not display the NRC Rules menu.
You may also access the NRC's interactive rulemaking web site through the NRC home page (http://www.ntc. gov). This site provides the same access as the FedWorld bulletin board, including the facility to upload comments as files (any format), if your web browser supports that function.
For more information on NRC bulletin boards, call Mr. Arthur Davis, Systems Integration and Development Branch, U.S. Nuclear Regulatory Coramission, Telephone: 301415 5780; e-mail: AXD3@nrc. gov, For information about the interactive rulemaking site, contact Ms. Carol Gallagher, (301) 415-6215; e mail CAG@nrc. gov.
EnvironmentalImpact: Categorical Exclusion The Commission has determined that this direct final rule is the type of action described in categorical exclusion 10 CFR 51.22(c)(2), since this direct final rule makes amendments to the 9
\ . ,
tl j
regulations which are corrective and nonpolicy in nature. Therefore, nei impact statement nor an environmental assessment has been prepare Paperwork Reduction Act Statement This direct final rule does not contain a new or significantly amended inform 01, et seq.).
collection requirement subject to the Paperwork Reductionb Act of 1995 (44 U Existing requirements were approved by the Office of Management and 3150-0011.
Public Protection Notification The NRC may not conduct er sponsor, and a person is not required to re collection of information unless it displays a currently valid OMB control number Regulatory Analysis {
The Commission has not prepared a regulatory analysis d for this a final rule does not present new or revised positions, impose a new requir new action.
Regulatory Flexibility Certification As required by the Regulatory Flexibility Act of 1980 (5 U.S.C,60 10
e certifies that this rule will not have a significant economic impact on small entities. This rule affects only the operation of nuclear power plants. The companies that own these plants do fall within the scope of the definition of "small entities" set forth in the Regulatory Flexibility A the small business size standards adopted by the NRC (10 CFR 2.810). Since these compan i
are dominant in their service areas, this rule does not fall within the purview of the Act.
Beckftt Analysis l
The direct final rule does not impose any change on licensees with respect to the term,
" safety related structures, systems and components." Rather, it provides a definition of related structures, syste,ns and components" throughout 10 CFR Part 50 that is identical to th definition contained in 10 CFR Part 100, Appendix A, the NRC's first regulation defining " safet related structures, systems and components," which provides that
- safety related" structures, systems and components are those that p%sess any one of the three numbered attr in the definition. This definition is consistent with both the NRC's and nuclear power plant licensees' longstanding understanding that the term,
- safety related structures, systems and components" includes those structures, systems and components that possess any one three listed attributes. Therefore, the NRC has determined that the Backfit Rule,10 CFR 50 does not apply to this direct final rule because it does not impose any backfits as defined i CFR 50.109(a)(1), and a backfit analysis has not been prepared for this direct final rule.
Small Business Regulatory Enforcement Fairness Act in accordance with the Small Business Regulatory Enforcement Faimess Act Of 1999, the NRC has determined that this action is not a " major rule" and has verified this determinatio 11
the Office of Information and Regulatory Affairs, Office of Management and Budget.
4 List of Subjects in 10 CFR Part 50 Antitrust, Classified information, Criminal penalties, Fire protection, Intergovemmental relations, Nuclear power plants and reactors, Radiation protection, Reactor siting criteria, ;
Reporting and recordkeeping requirements.
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 of 1974, as amended, and 5 U. S. C. 552 and 553, the NRC is adopting the following amendmen'.s to 10 CFR Part 50.
PART 50-DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
- 1. The authority citation for Par 150 continues to read as follows:
AUTHORITY: Secs. 102,103,104,105,161,182,183,186,189,68 Stat. 936,937,938, 948,953,954,955,956, as amended, sec. 234,83 Stat.1244, as amended (42 U.S.C. 2132, 2133, 2134, 2135, 2201, 2232, 2233, 2236, 2239, 2282); secs. 201, as amended, 202, 206, 88 Stat.1242, as amended, 1244,1246 (42 U.S.C. 5841,5842,5846).
Section 50.7 also issued under Pub. L.95-601, sec.10,92 Stat. 2951 (42 U.S.C. 5851).
Section 50.10 also issued under secs. 101,185,68 Stat. 955 as amended (42 U.S.C. 2131, 2235), sec.102, Pub. L. 91 190,83 Stat,853 (42 U.S.C. 4332). Sections 50.13, and 50.54(dd),
and 50.103 also issued under sec.108,68 Stat. 939, as amended (42 U.S.C. 2138). Sections 50.23,50.35,50.55, and 50.56 also issued under sec.185,68 Stat. 955 (42 U.S.C. 2235),
Sections 50.33a,50.55a and Appendix Q also issued under sec.102, Pub. L. 91 190,83 Stat.
-12
._ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _ _ . _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ ~ _ . . _ .
853 (42 U.S.C. 4332). Sections 50.34 and 50.54 also issued under sec. 20 t U.S.C. 5644). Sections 50.58,50,91, and 50.92 also issued under Pub. L 97 (42 U.S.C. 2239). Section 50.78 also issued under sec.122,68 Stat. 939 (4 also issued under sec.184,68 Stat. 954, as amended (42 U.S.C. 2234).
Sections 50.80 50.81 Appendix F also issued under sec.187,68 Stat. 955 (42 U.S.C 2237),
- 2. In i 50.2, the definition of safety related structures. svstems and compo revised to read as follows: ,
l 50.2 Definitions.
1 Safety related structures, systems and components means those structures and components that are relied upon to remain functional during end followi 4
i events to assure:
2 (1) The integrity of the reactor coolant pressure boundary; 3
(2) The capability to shut down the reactor and maintain it in a safe j or (3) The capability to prevent or mitigate the consequences of acc in potential offsite exposures comparable to the applicable guideline e
$ 50.34(a)(1) or 6100,11 of this chapter, as applicable,
- 3. In $ 50.49, paragraph (b)(1)(1)(B) is revised to read as follows:
5 50.49 Environmental quell 9 cation of electric equipment importan
! power plants.
'T 13
_ _ . - _ _ _ . . _ _ _ _ _ _. . _ . _ _ _ _ _ _ __m___ .,.
e O o (b) ,
(1) l (1)
(B) The capability to shut down the reactor and maintain it in a safe shutdown condition; or !
- 4. In $ 50.65, paragraph (b)(1) is revived to read as follows:
$ 50.68 Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
'14
a
, (b)
(1) Safety related structures, s** ems and components that are relied upon to remain functional durhg and fo!Io , design basis events to ensure the integrity of the reactor coolant pressure boundary, th capability to shut down the reactor and maintain it in a safe shutdown condition, or the capability to prevent or initigate the consequences of accidents that could result in potential offsite exposure comparable to the guidelines in i 50.34(a)(1) or i 100.11 of this chapter, as applicable.
1 48 Dated at Rockville, MD, this 7 day of ,1997.
For the Nuclear Regulatory Commission.
!.. Jose p Callan, Executive Director for Operations.
15 u