ML20212C345
| ML20212C345 | |
| Person / Time | |
|---|---|
| Issue date: | 10/23/1997 |
| From: | Bangart R NRC OFFICE OF STATE PROGRAMS (OSP) |
| To: | GENERAL |
| References | |
| NUDOCS 9710290192 | |
| Download: ML20212C345 (9) | |
Text
-
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' STATE bAISON OFFICERS ,
CODES AND STANDARDS; IEEE NATIONAL CONSENSUS STANDARD (SP 97 075) (
- 1^
J _ , ;-
,;., LThe N,uclear Regulatory Commission (NRC) is amending 10 CFR Part 50, ' Domestic Licensing '
4 t of Production and Utilization Facilities," to incorporate by reference IEEE Std. 603-1991, a L ' . ,
, national consensus standard for power, instrumentation, and control portions of s %ty systems ( '
^
.in nuclear power plants. This action is r.ecessary to endorse the latest version of this national /
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consensus standard in NRC's regulations, and replace an IEEE standard currently endorsed in the NRC's regulations which has been withdrawn by the IEEE.
The Commission has determined under the National Environmental Policy Act of 1969, as amandad, and the Commission's regulations in subpart A of 10 CFR Part 51, that this rule - 1
' would not be r. major Federal action significantly affecting the quality of the human environment '
- L and, therefore, an environmental impact statement is not required. The Commission has prepared an Environmental Assessment supporting this finding of no significant environmental
- impact. Enclosed for your review are copies of the Federal Reaister notice and the Environmental Assessment. The final rule is effective on January 1,1998, unless significant
- adverse comments are received by December 1,1997. Please provide comments to:
Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 205M-0001; Attention:
Rul6 makings and Adjudbations Staff. For further information, contact Satish K. Aggarwal, Senior Program Manager, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555, telephone (301) 415-6005; (e-mail: SKA@NRC. GOV).
l NG RT Richard L. Bangart, Director Office of State Programs
Enclosures:
As stated Distribbtion:
DIR RF DCD (SP03)
S. Aggarwal, RES _
Agreement State File
- SLO General File
\ \
DOCUMENT NdME: G:tSCD(SP97075.SCD *Sce previous concurrence.
T'feceive a cop r of this document, Indicate in the box: "C" = Copy without attachmenvenclosure 'E's Cop mth attachment / enclosure *N" a No copy l l OFFICE OSP OSP:DD OSP:D/M l l zlNAME SCDroggitis:gd PHLohaus RLBangartWid -
lDATE -10/21/97* 10/21/97* 104 997 OSP FILE CODE: SP-A-4 . SP-S-9 mm
.MLp w $ ???n 0 enngn- ~ '"
9710290192 971023 ll ll h.l llllll ll PDR STPRO ESOGEN ,e i ii5 * -
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STATE LIAISO FFICERS CODES AND STA ARDS; IEEE NATIONAL CONSENSUS STANDARD (SP )
l The Nuclear Regulatory Qommission (NRC) is amending its regulations to incorporate by reference IEEE Std. 603-1 91, a national consensus standard for power, instrumentation, and control portions of safety s tems in nuclear power plants. This action is necessary to endorse the latest version of this nat al consensus standard in NRC's regulations, and replace an IEEE standard currently endor' sed in the NRC's regulations which has been withdrawn by the IEEE.
The Commission has determined under the National Environmental Policy Act of 1969, as i amended, and the Commission's reg'ulations in subpart A of 10 CFR Part 51, that this rule would not be a major Federal action siMificantly affecting the quality of the human environment I and, therefore, an environmentalimpact statement is not required. The Commission has prepared an Environmental Assessment supporting this finding of no significant environmental ;
impact. Enclosed for your review are copids of the Federal Register notice and the '
p Environmental Assessment. The final rule is' effective on January 1,1998, unless significant
)- adverse comments are received by Decemberx1,1997. Please provide comments to:
~ Secretary, U.S. Nuclear Regulatory Commissio'nt Washington, DC 20555-0001; Attention: ,
Rulemakings and Adjudications Staff. For furtherinformation, contact Satish K. Aggarwal,'
,
- Senior Program Manager, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory.. =
,)
, Commission, Washington, DC 20555, telephone (301) 415-6005; (e-mail: SKA@NRC. GOV). ,
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,.,; Richard L B ngart, Director
,:; 4 -
Office of State Programs >
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Enciosures:
As stated \A 3; ,
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Distribution:
\
.DIR RF \
DCD (SP03)
OGP Staff. PDR (YES/) \
S. Aggarwal, RES Agreement State File SLO General File
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. DOCUMENT NAME: G:tSCDtlEEE.SCD ,
\
v w.c.sv. . com ons. ooce.n.nuame.e. in in. nor c #wbA .nacnen.nv.noo.ur. r coo+m en_.nv.nciosure v % cooy OFFICE 3!)OSP OSWpDj OSP:D s NAME SCDroggitis:gd PHLohMysY T RLBangart \
DATE 10/lf/97 10N/07 10/ /97 \
OSP FILE CODE: SP-A-4 SP'S-9 x
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p i UNITED STATES
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} NUC!. EAR RECULATCRY CUMMISSION WASHINGTON, D.C. 30666 4 001
% ,, # October 23, 1997 STATE LIAISON OFFICERS CODES AND STANDARDS; IEEE NATIONAL CONSENSUS STANDARD (SP-97 075)
- The Nuclear Regulatory Commission (NRC) is amending 10 CFR Part 50, ' Domestic Licensing of Production and Utilization Facilities," to incorporate by reference IEEE Std. 603-1991, a national consensus standard for power, instrumentation, and control portions of safety systems .
In nuclear power plants. This action is necessary to endorse the latest version of this national consensus standard in NRC's regulations, and replace an IEEE standard currently endorsed in the NRC's regulations which has been withdrawn by the IEEE, The Commission has determined under the National Environmental Policy Act of 1969, as amended, and the Commission's regulations in subpart A of 10 CFR Part 51, that this rule would not be a major Federal action significantly affecting the quality of the human environment
, and, therefore, an environmentalimpact statement is not required. The Commission has prepared an Environmental Assessment supporting this finding of no significant environmental i impact. Enclosed for your review are copies of the Federal Reaister notice and the Environmental Assessment. The final rule is effective on January 1,1998, unless significant adverse comments are received by December 1,1997. Please provide comments to:
Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001: Attention:
Rulemakings and Adjudications Staff. For further information, contact Satish K. Aggarwal, Senior Program Manager, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555, telephone (301) 415-6005; (e-mail: SKA@NRC. GOV).
\( lla IA M Richard L. Bangart, Director Office of State Programs
Enclosures:
! As stated J
, , .53933- Federal Register / Vcl. 62, Ns. 201' / Friday, October 17,'1997 / Rules and'Regulati:ns
~
and weight range and the tumber cf (6) Subtracting AUD or equivale:t maaa*****: Mall comments 12:
- days grasing occurred, and the am
- unt - v:lue cf suppl:m:ntal feed fed to the Socrotary, U.S. Nuclear lat:ry and of feed led such grazing livestock during b crop year . . Commission, Washington, an 20555-j-
during eny posing period - result of paragraph (cX5) of this 0001; Attention: Rulen,akings tad ear. section. Adjudications Staff. Hand deliver.
within the croNt Day adjustments, (7)
If) Animal as Subtracting the result of paragraph comments to 11555 Rockville Pike, smermined by CCC, may be calculated . (cM6) of h section from the poult of , Rockville, Maryland, between 7:30 a.m.
l when a producer of forage paragraph (cX.) of % section, if a aero and 4:15 p.m. on Federal workosys.
prodo=Inantly grased, provides or negauve number results, payment . pon Pusmesa sepOfesAT100100NTACT4 edequate evidence, as determinml by - cannot be calculated.
CCC, that unit i management and Soush K. Aggarwal, Senior Program (s) Multi maintenance p ces provide dlSerent paragraph (plying cX7)of the positive
% section by: result of Otuce of Nuclear Regulatory Manager, carrying capacity than practices Research, U.S. Nuclear Regulatory (i) For the 1997 through 1996 crop Commission Washington,DC20555, generally pmvided forage acreage used years,60 percent of b everage market Telephone (301)415-e005 Fox (301) to calculate the approved county - price, as a r=iad by CCC, or any -
expected carrying capacity. 415-5074 (e mail: SKAGNRC.COV).
comparable coverage, as determined b Y. suppt.aumNTAny esponesATION: NRC
- e. Amend 51437.9 to wviso paragroph COC8 or . , * *
(bX2) to med as follows: considers % rulemmHng,which (ii) For the 1999 and subsequent endorses IEEE Std. 603-1991, to be ggagg., m w
- years,55 t of the average market Price, as etermined by CCC, or any noncontmversial because, as noted in
. the background discussion, there was no (b) * *
- eomPmable cowage, as duermined bY adverse public <===aat on the g
(2) The failure of the producer to Ngulatory guide endorsing M ressed or replant to the same crop in b siseed at weshlaston. DC. on October s. standard. Accordingly,theCommission county when it is practicable to ressed int.
Ands that public nouco and opportunity
'or replant: - M*sthKany, for comment are ~+n 1y pumuant
. . . . .. Ersevolve Yios President, Cosimodify oedit to 5 U.S.C. 553(bMB). Thus, the
- 9. Amend $1437.11 to revise the C"'P*'d'**- . Camission is publishing h rule in introductory text and add paragraph (c) im Doc. s7-37433 Fuod 1&16-07; 4:45 em) Anal form without seeking public -
to reed as follows.* saanes esse om.eo, comments on the amendment in a .
proposed rule. This action will become
$1487.11 Paymente for reduesd yloide end eHoctive on January 1,1998. However, t psevented plenting.
If the NRC receives significant adverso la the event that the area loss NUCLEAR REOUL.ATORY comments by December 1,1997, then requirsment has been satisSed for the N the NRC will publish a document that crop and: withdraws 2 action, and will address e- . . .- . 10 CPR Part 30 ;
the comments received in response to J (c) N producer has sustained a loss RIN 3166-AP73 an identical proposed rule which is cf forage determined by CCC to be being concurrently published in b preda=inand grened la accordance Codes and Stenderde;IEEE National Proposed rules sectlen of this Federal w,th $ 1437.7(y),in excess of 50 percent
~
1 Consensus Stendere Regleter. Any signiScant advwee -
cf the producer's expected Animal Unit comments will be addressed in a
. Day established for the unit, the NAP AesNr.Y: Nuclear Regulatory subsequent Anal rule. The NRC will not Commission,
- payment will be determined by: snitiate a second comment period on (1) Dividing the unit acreage for each ACm0N. Disct Baal rule. . this action in b r.ent b direct Saal idenuSed on
[es cap Twva andsubp euemeARY:The Nucle er Regula Co,aunin!on is amending us tions %-
result by b corres reference IEEE Std. In 10 CFR h basis ading grasing odebused determination e as'* ""F,.te Somt, e fonal na consensus Licensing of
- 50. " Domestic uction and Utilisation .
carrying capacity, totaling the usult for standard tw poww,instrunnentauon. Facilit'es," $ 50.55a requires that the ,
each species or typen.and varieties, and control portions of safety systems in protection systems in nuclear power
- (2) blultiplying the result of paragraph nuclear poww plants. This action is plants meet the mquirements set forth in (cM1) o'f h section by 50 t. necessary to endorse the latest version IEEE Std. 279, " Criteria for Protection (3) Multiplying the num ofanimals of this national <=====aus standed in - Systems for Nuclear Power Generating -
grased by the daily allowance of corn NRC's regulations, and replace an IEEE Stations," in effect on the formal docket according to type and weight range and standard currently endorsed in the date of b application. However,IEEE divide the result by pounds of corn CEC HRC's regulations which has been Std. 279 la obsolete, has been determines is mey to provide the withdrawn by the IEEE. withdrawn by IEEE and has now been daily energy requirement for one animal E'PecTNE DATE:The Baal rule is superseded by IEEE Std. 603-1991,
. unit. - effective on January 1,1998, unless " Criteria for Safety Systems for Nuclear
. (4) Multiplying the result of paragraph significant adverse comments are Power Generating Stations."
.. (cM3) of this section by the nuber of - received by December 1,1997, if the in November 1995, the NRC s'aff days grazing occurred to detern.ine offective date is delayed, timely notice issued for public comment a draft groes actual AUD. will be published in the Federal regulatory guide, DG-1042, whicl, was (5) Adding AUD for ineligible c ..ses Register. The incorporation by reference proposed Revision 1 to Regulatory
- cfloss and incidental mechanically ofIEEE Std. 603-1991 is approved by Culde 1.153 " Criteria for Safety harvested Category 1 forage to the result the Director of the Federal Register as of Systems." This draft regulatory guide ciparagraph (cK4) of h section. January 1,1998, proposed to endorse IEEE Std. 603-1991 e
A.
. I
+
Federal Register / Vrl. 62 No. 201/ Friday, October 17, 1997 / Rules and Regulations 53933 (including the correctlin sheet dated and maintain it in a saf; shut down described in the regulatory guide,if a January 30,1995). Because there were condition, or (iii) the capability to referenced standard has not been no adverse public comments to Revision prevent or mitigate the consequences of endorsed in a regulatory guide, the 1 to Regulatory Guide 1.153, the accidents that could result in potential licensees and applicants may consider
. Commission believes that there is off site exposures comparable to the to and use the information in the general public consensus that IEEE Std. CFR part 100 guidelines." A " safety referenced standard consistent with 603-1991 provides acceptable criteria function" is defined by IEEE Std. 603- current regulatory pracuces, for safety systems in nuclear power 1991 as "one of the processes or plants, condidons (for example, emerEency Electronic Access .
" P Discussion The direct final rule inco orates a c "'ba n ]va' mer'8 ncore theYou may also provide comments via NRC s interactive rulemaking national consensus standar ,IEEE Std. cooling remova , and post accident containment isolation radioacdv7ty) website through the NRC home page 603-1991, for establishing minimal essential to maintain plant parameters (http 1/www.nrc. gov).This site provides funr:tional and design requirements for ~ within acceptable limits established for the availability to load comments as power, instrumentation, and control adesi basis event." files (any format),i your web browser portions of safety systems for nuclear Th mmission considers that the supports that function. For information power plants into NRC regulations. nis systems covered by IEEE Std. 603-1991 about the interactive rulemaking action is consistent with the provisions and IEEE Std. 279-1971 are the same, website, contact Ms. Carol Gallagher, of the National Technology Transfer and Therefore, for purposes of aragraph (h) (301) 415-5905 (e malh CAG@nrc. gov).
Advancement Act of1995. Pub.I 104- of to CFR 50.55a," prot on systems,"
113, which encourages Federal and " safety systems' are s onymous. Findin of No EnvironmentalimPact:
regulatory agencies to consider adopting The Commission notes th these two Avail liity of Environmental industry consensus standards as an terms are also synonymous with the Assessment altemative to de novo agency . term " safety related systems," used The Commission has determined development of standards anecting an elsewhers in the Commission's under the National Environmental industry. This action la also consistent regulations. Therefore, licensees are Policy Act of 1969, as amended, and the with tht, NRC policy of evaluating the e ected to apply I"EE Std. 279-1971 an IEEE Std. 603-1991, as a Commission's regulations in subpart A latest versions of national consensus standards in terms of their suitability for . to "safet related systems." ppropriate, of 10 CFR part 51, that this rule would endorsement reguladons or This le mandates the use ofIEEE not mo re lato gul Std. 603-1991 (including the correction ,3gn y g t e unlity of the a y,10 CFR 50.55 a(h) spectBes sheet dated January 30,1995) for future human environment and, erefore, an that " protection systems" for plants nuclear power lants, including final environment impact statement is not with construction permits issuad after design a rov s, design certifications required. The Commission has prepared January 1,1971, must meet the and co ed licenses unler 10 CFP. an Environmental Assessment requirements in IEEE Std. 279 in effect part 52. Current licensees may continue suppor'ing this finding of no sign 16 cant on the formal docket date of the to meet the requirements set forth in tt, environmentalimpact.
applicrtion for a construction permit. edition or revision of IEEE Std. 279 in The NRC has sent a copy of the IFEE Std. 279 states that a " protection effect on the formal date of their environmental assessment and a copy of system" encompasses all electric and application for a construction permit or the Federal Register Notice to every mechanical devices and circuitry (from may, et their option, tae IEEE Std. 603- State liaison officer and requested their eensors to actuation device input 1991, provided they r:omply with all comments on the environmental terminals) involved in generating those applicable requirements for makin8 assessment.The environmental signals associated with the protective changes to their licensing basis. assessment is available for inspection at function. These signals include those However, changes to protection systems the NRC Public Document Room,2120 that actuate reactor trip and that,in the in operating nuclear powst plants event of a serious reactor accident, L Street NW., Washington, DC. Also, the initiated on or after Janue71,1998 NRChascommitteditself tocompi 6 me ate engineered safeguards such as must meet the requirements in IEEE Std. In all its actions with the Presidentia containment isolation, core spray, safety 603-1991. For purposes of this rule, in}ection, pressure reduction, and air Executive Order #12898-Federal "chan " to protection systems include Actions to Address Environmentai cleaning. " Protective Function" is (1) m ifications, augmentation or defined b IEEE Std. 279, as "the replacement of protection stems Justice in Minori Populations and sensing o one or more variables permitted b license amen ents,(11) lewdncome Popu ations, dated 11,1994. Thenfom, the NRC associated with a particular generating changes ma e by the licensees pursuant Febm station condition. signal processing. and to procedures in to CFR 50.59, and (111) also ha determined that there are no the initiation and com letion of the plant specific departures from a design disproportionate, high, and adverse ,
protective action at va es of the certification rule under 10 CFR part 52. impacts on minority and low income ,
ulations. The NRC uses the
- variables established in the design In-kind (like fordikel replacement of bases." pro'tection s stem com nents are not o wing working definition cf IEEE Std. 603-1991 uses the term considered anges to e protection environmental justice: envirt,umental
" safety systems" rather than " protection systems. justice means the fair treatment and systems." A " safety system" is defined Section 3 of IEEE Std. 603-1981 meaningfulinvolvementof all cople.
by IEEE Std. 603-1991 as "a system that references several industry codes and regardless of race, ethnicity, ture, is relied upon to remain functional standards. If the referenced standard has income, or educationallevel with '
during and following design basis been endorsed in a regulatory guide, the respect to the development, events to ensure: (i) The integrity of the standard constitutes a method implementation, and enforcement of reactor coolant pressure boundary,(ii) acceptable to the Commission of environmental laws, regulations and the capability to shut down the reactor meeting a regulatory requirement as policies.
I a
" 53934 ' Federal Register / Val, 62. N$ 201- / Friday,' October 17,199 d Regulati:na -
E ~*. Redecdes Act Statement. - protecti:n syst:ms, but the rule permits PART ab DOMESTIC LICENSING OF This Anal rule does not contain a new the licenses the option of meeting IEEE PRODUCTION AND UTILIEATION -
or ===utad infonnation collection Std.603-1991, FACILITIES --
b th k The backfit rule was notintended to 4 501 -
tions vp c tinues to d Yw w J cpproved by the See of Management*PPl acants, and therefore e backSt rule Aetherity secs.102,t03,104,los,161, and Budget. approval No. 3150-0011, does not apply to the portion of the rule set.183,see, tee,es siet.eso,e 7.est, .
applicable to scw construction pennits, ' ees, ess, es4 ess, eso, as amended, sec.
4 Puhtic Preescties Netl8 cation new operating licenses, new Anal design 334, es stat. t344, as amended (42 U.S.c If a document used tois an *PProvals, rww dwi certi8 cations and 31324 133,3134,atss,3:01,32:2 assa, 8 ao infonnation collection does display ==hl=ed licensa. $1s rule does not gM . 8asa a currently valid OMB control number, change the licensing basis (14,IEEE 3,,t, g 1see (42 U.S.c seet, teet, sees).
(
the NRC may not conduct or sponsor. Std. 279) for plants that do not latend ande is not required to respond to make any changes to their power and suda s&7 aim issed uder Pub 1 M-to, as tion collection. instrumentation and control systems / . cos,section we, to, es also so.1o stat.issued sent (42 U.S.C under esce.6est).
3 os,
,_ ,_ However, the rule would require future tes, se stat. ess as amended (42 U.s.c stat, i Analyels
. , changes to existing power and 2235), sec. t02 Pub. L st-1so, as stat. 853 b ra==taalon has prepared a lastrumentation and control portions of (42 U.S.c essa). sectione so.1s, and so.s4 regulatory analysis which shows that -.. protection systems to comply with b (ddl. and so. sos also tesoed under sec. too, the proposed amendment does not new standard. This would not be . es stat. eso, as rended (42 U.S.c at so).
impose any new requhements or costs - considered a back8t, since the changes .. sectione so as, so.as, so.ss, and so.se also on current licensees who do not make are voluntaril laitiated by b licensee, amod undw sec. tes, es stat. ess (42 U.S.c ,
systems or separately by the NRC after 22:51, sections so.ssa,so.ana and Appendix changes licensees plannto safetfagosing or prop.
changes However, a separate be t analysis.This is ",, Ng%'3$$" ,h"'
to power and instrumentation & control consistent with post NRC practice and and 50.54 also issued under sec. 204, se stat.
systems will be impacted because they , the "
discussions on backAtting in . t34s (42 U.S.c sees). sectione so.ss, so.st, willbe required to meet the Value-Impact Statement" prepared for , and so.ea also issued under Pub,l e7-41s. I uirements ofIEEE Std. 603-1991 for Revision 1 to Regulatory Guide 1,153. A es stat. sors (42 U.s.c assel. section so.7s even though the :=malader copy of the Value-Impact Statement is aleo leeued under sec, taa, se stat. ese (42
. of b p t power and I&C systems are available for inspection or copying for a . U.S.c 21s2), section so,co-so.s1 also ,
only required to meet their current fee in ,he Co==Imalon's Pubtle leeued under sec. sse, se stat. w4. as licensing basis.N draft regulatory Document Room at 2120 L Street NW , amended (42 U.S.c 22:41. Appendix l'alao analysis is available for inspection in Washing;on, DC, under Task DG-1042. luued undw ac.187, se stat. 95s (42 U.S.c ,
the NRC Public Document floom,2120 . la e , b NRC has determins,d 2237h ,
L Street, NW , Washington, DC. that the t rule, to CFR 50.109, - 12. In $ 50.55a, paragraph (b)is ,
=. . does not apply to 2 direct Baal rule revised to read as follows: e
. , MHHy CertiScation because it does not impose any backfits As required by the Regulatory , as denned in to CFR 50.109(a)(1) and, ' II"00' O*0"U 808"O"88*
Flexibilit * * * * *
-theen==y lanton Act of1980 (5 U.S.C 605(b)), therefore, a backfit analysis has not been(b) Protection and Sofety Systems, (1) certifies that h rule prepared for this direct Anal rule.
will not have a significant economic IEEE Std. 603-1991 and the correction impact on small entittu. nas rule Small Busiases Regulatory Infuessment - sheet dated January 30,1995, which are a5ects only the operation of nuclear . Fairaris Act referenced in paragraph (h)(3) and power lants b companies that own In accordance.with the Small (h)(4), are approved for incorporation by
.these to do not fall within b scope Business Regulatory Enforcement reference by the Director of the Federal-ofthe Snition of"small entities" set Fairness Act of1996, the NRC has Register in accordance with 5 U.S.C . .
forth in the Regulatory Flexibility Act or determined that this action is not a 552(a) and 1 CFR part 51. A notice of major rule and has verified this the small business size standards any changes made to the meterial adopted by the NRC (10 CFR 2.810). . determination with the OfBce of incorporated by reference will be Since these companies are da=Inant in Information and Regulatory Affairs of : published in the Federal Register. . .
their service areas, this rule does not fall OMB. Copies ofIEEE Std. 603-1991 may be Wi&in es Purview of ee Act. - d ' "
List of Sehlects la 10 CFR Part so [
Badat Analysis _ ,,3 El m Antitrust,ClasslBod information, Service Center,445 Hoes Lane, h rule requires applicants and Criminal penalties Fire protection, Piscataway, NJ 06e55. It is also available ,
holders of new construction ts, Incorporation by reference, ' forins on at the NRC Library,11545 h operating licenses,new design latergovernmentalrelations, Nuclear e Pike, Rockville, MD 20652-
- m approvals, new design certifications and Power lants and reactors, Radiation - 2738, and at b OfSco of the Federal
. combined licsones to comply with IEEE on, Reactor siting critoria, and Register,800 North Capital Street, NW, Std. 603-1991 (including the correction Porting and recordkeeping Suite 700, Washington, DC. IEEE Std.
. .abest dated January 30,1995). Changes seguirements. . .
279, which is referenced in paragraph
. to Protection eystems in existing For the reasons set out in the . (h)(2) of this section was approved for operating plants initiated an or after *; preamble and under b authority of the incorporation by reference by the January 1,1996 must meet the Atomic Energy Act of 1954, as amended Director of the Federal Register in requirements ofIEEE Std. 603-1991, the Energy Reorganisations Act of1974, accordance with 5 U.S.C. 552(a) and 1
] EEE Std. 279 will continue to apply to as amended, and 5 U.S.C. 552 and 553, CFR part 51. Copies of this standard are existing nuclear power plants that do the NRC is adopting the following also available as indicated for IEEE Std.
not make any changes to their amendment to to CFR part 50. 603-1991. '
i
__ _ _ _ _ _ . _ . _ . _ _ . . _ .. _ _ . _ _ _ -- .___-___.__._m Federal Register / Vcl. 62. No. 201 / Friday, October 17, 1997 / Rules and Regulati:ns 53935
[
(2) Dennitirns. suumaanY This amendmelt ad: pts a receind a report cf an N2 c orspeed (1) For purposes of this paragraph the new airworthinus directive (AD) that is condition on an AlliedSignalInc.
i ,
terms " protection systems," " safety applicable to AlliedSignalInc. (formerly (formerly Textron Lycoming) Model
- systems," and " safety-related systems" Textron Lycoming) Model T53138 T5317A-1 turboshah engine. The
- are synonymous. T5317A, and T53 serin military investigation renaled that the N2 1 (11) Changes to protection systems turboshaft engines approud for overspeed condition was caused when laclude modi $ cation, augmentation or installation on aircesh certined in the N2 overspeed governor bevel gear, replacement of protection systems accordance with Section 21.25 of the which is part of the accessory drin
- permitted by license amendments, Fedwal Aviation Regulations fFAR). carrier and cap assembl , shifted out of
, changes to protection systems made by This action requires a one time visual position. This gear shi out of
- liranaams pursuant to 10 CFR 50.59, and inspection of ===ary drive carrier position was determined be due to i plant specinc departures from a deelga assemblies for a5ected serial numbers improper manufacturing ofb j i certl81 cation rule undw 10 CFR part 52. (S/Ns) designating a defective assembly, ====y drin carrier and cap <
! (:.) Protection systems. For nuclear and if the S/N is applicable, assembly, Part Number (P/N)1-0W l power plants with construction permits rept-t with a serviceable 210-41, which is installed on the higher assued aher January 1,1971, but prior to assembly.This amendment is pted level assembly, accessory drive carria
- January 1,1998, protection systems by a sport of an N2 overe eseeably, P/N 1-0W220-03,1-0%
! must most the requirements set forth condition due to a defective ==== y 2&12, or 1-470-220-13. All accessory
{ either in the Institute of Electrical and drin carrier assembly.& actions drive carrier assemblies, P/Ns 1-470-
' Electronics Engineers (IEEE) Std. 279, speci8ed in this AD are intended to 22Kl.1-070-220-12, and 10W2W ,
! " Criteria for Protection Systems for prevent accessory drive carrier assembly la,tastalled eher November 1,1985, i l Nuclear Power Generating Stations," or hilure, which could result in an N2 and have been identi8ed by serial i in IEEE Std. 603-1991," Criteria for overspeed and an uncontained engine number (S/N) am subject to this
! Safety Systems for Nuclear Power failure. .
Inspection.This constion,if not Generating Stations,"and the correction
- e4Tas: Effective November 3,1997. corrected, could result in meca==ary l drhe carria ensembly failure,which sheet deted Jan 30,1995. However. The incorporation by reference of changes to pro on eyetems initiated canain publications listed in h could result in an N2 overs on or aher January 1,1998 must meet regulations is approved by the Director $ uncontalud engin failure, peed and an the requirements set forth in IEEE Std. of the Federal Register as of November The FAA has reviewed and approved 403-1991, and the correction sheet 3,1997. ,
the technical contents of AlliedSignal dated January 30,1995. Comments for inclusion in' the Rules Inc. Alert Service Bulletin (ASB) No.
T53138/17A-A0092, Revision 1, dated (4) Safety systems. For construction
. permits, operating licenses, Saal design.
December Docket must be received 16,1997.
July 1,1997; ASB No.T53-L-138-on or.before A0092, dated June 4.1997; and ASB No.
-approvala, design certi8 cations and +
anammense. Submit comments in combined licenses issued on or stor tri licate to the Federal Aviation . T53-L-703-A0092, dated June 4,1997.
These ASPS decribe procedures for January 1,1994, enfoty systems must A tion (FAA),New England a meet the re'quirements set forth in IEEE Region,OfBce of the Assistant Chief . M a anh visualins Std. 603-1991, and the correction sheet, Counsel, Attention: Rules Docket No. of accesmy drin carrier assemb les for affected S/Ns designating a defective -
detod }anuary 30,1995. 97-ANE-88-AD.12 New England *"
Dnied at Rockvilk,this eth day of Oosober. Executive Park, Burlington, MA 01803-. AIg ",' *Pglicable, b
5299. Comments may also be sent via P tee?
For the Nuclear Regulatory t'a==4=ta. the laternet using the following address: y se ansafe condition has been lehm C. noyle, 9 ad enginepropefas. dot. gov , identined that is likely to exist or -
- ee emt secretaryofthe cosunission ",""[***
g , g develop on other engines of the same IFR Doc. 97-27421 Filed to-1M7; 8:45 am) sub type design, this AD is being issued to une easses sees ise*** service informadon refuened in Prennt accessory drive carrier assembly Emilurs,This AD uires e one-time els AD my be obtainha visuaHmpecdon o acemy drin AuledSignal Aerospace Atta: Data
- DEPARTIAENT OF TRANSPORTATION Distribution, M/S 64-3/2101-201, P.O.
"*"**bH e Ns ,
Box 29003, Phoenix, AZ 45038-9003; Enadng , y ,
' FeEletal Avletion Administration assembly,an if the S/Nis applicable.
. telephone (602) 365-2493, fax (602) be - 8'P lacement with a servimable assembl actions am required to be 14 CPR Port at 365-5577.This
..i ,1 at the FA,A,information New Eng mafand No.97-ANE ES-AD; Amenenent Re51 on.OfBce of et Assistant Chief Counsel,12 New England Executive
]secrib previo .'
00; AD 97-41-97) Since a situation exists fhat requires Park. Burlington, MA: or at the OfBee of the immediate adoption of this 14N 2130-AA44 the Federal Register,800 North Capitol reguhuon,it h found that noda and .'
Street, NW., suite 700, Washington, DC. blic mment Airworthiness Directives; AlliedSignal Pon PunTNER esposuaAfton 00NTAct: Ray {PPortunity for p o Inc. (Formerly Textron Lycoming) P
, Vakill, Aerospace Engineer,Los Angeles ca7exhts for making t amendm at R$odelT53138 TS317A,and783 Aircraft Certiacation Office, FAA, pelHtery)Turhoshaft Engines offective in less than 30 daI Transport Airplane Directorate,3960 Paramount Blvd., Lakewood, CA 90712 Casaments invited AGENCY: Federal Aviation Administration, DOT. 4137. **l*Phone (562) 627-5262, fax . Although this action is in the form of
-(562)627-5210. a Snal rule that involves requirements
- tu mquet for 9UPPL8hlENTanY sIF0fedATl0N:The affecting flight safety and, thus, was not
- " preceded by notice and an opportunity Federal Aviation Ariministration has c
w
ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT ENVIRONMEhTAL ASSESSMEhT identylension qfRulemaking:
! The NRC is proposing to amend 10 CFR 50.55a, which defines the requirements for j applying national consensus standards. Party.$ "h" of this section currently requires that protection systems in nuclear power plants meet the requirements set forth in IEEE
- Std. 279," Criteria for Protection Systems for Nuclear Generating Stauons." However, i IEEE Std. 279-1971 is obsolete and has been withdrawn by IEEE. This standard has now been superseded by IEEE Std. 603-1991, " Criteria for Safety Systems for Nuclear Power Generating Stations,"
. The proposed amendment to 10 CFR 50.55a (h) would require that for coristruction
! permits, operating licenses, combined licenses, and design certifications, issued on or l aAer January 1,1998, the safety systems meet the requirements set forth in IEEE Std. 603-1991. Changes to safety systems in existing operating power plants initiated after January 1,1998 must also meet the requirements ofIEEE Std. 603-1991.
- The Needfor the Rulenmaking
- .
i l The current regulation,10 CFR 50.55a (h), is obsolete because it incorporates by
, reference IEEE Std. 279, which has been withdrawn by IEEE. NRC proposes to update this reference to a national consensus standard to reflect current technology. The Commission has concluded that IEEE Std. 603-1991 is a sigaificant improvement over i- IEEE Std.' 279-19H. The latest standard provides clear explanations to the general
- criteria provided i du earlier standard. It also includes criteria for shared systems and i covers considerations of human factors, clarification of the criteria for interaction between sense and command features and other systems, and clarifications of the design basis event requirements for critical points in time or the plant conditions.-
l Thus, it is in the inte est of the public health and safety for the Commission to adopt later -
i versions of the IEEE systems criteria document. By providing clearer guidance on the l criteria for safety systems, and by including criteria on related issues, IEEE Std. 603-1991 offers an improvement to health and cafety by reducing the potential for
! misunderstanding of the criteria for safety systems.
[
i.
I i
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2 ,
l Environment =1Imnact af the Rufennaking:
l The Commission has completed its evaluation of the fmal rulemaking and concluded that !
these criteria contained in IEEE Std. 603 1991 will provide a means of promoting safe practices for design and evaluation of safety systems perforinance and reliability by providing clear guidance for criteria for safety systems. It is, thus, expected that the fmal rule will reduce the probability or consequences of an accident. The Commission also concluded that the fmal rule will not affect the amount and type of effluent that may be released off-site and there should be no significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the Commission concludes that this fmal rule will result in no significant radiological environmental impact.
The fmal rule does not affect non-radiological plant effluent and has no other environmental impact. Therefore, the Commission concludes that there are no significant non-radiological environmental impacts associated with the amendment.
Alior--am to the Pronosed Am*=A~nt:
One alterm.tive to incorporating by reference into NRC regulations the updated IEEE Std. 603-1991, would be to take no action. This would mean that the NRC would continue to rely upon an obsolete industry standard, which has been withdrawn by IEEE.
This option will not utilize the current state-of-technology and benefit from the operating experience gained over the past 20 years. This is not acceptable since the improvements in IEEE Std. 603-1991 can reduce the probability or consequences of an accident with no adverse impact on the environment or occupational exposure.
A second alternative would be to incorporate the entire text ofIEEE Std, 603-1991 into the NRC regulations. This approach is not practicable.
Alternative Use ofResources:
This action does not involve the use of any resources not previously considered in other rulemakings.
R*-**c Cons =1**d ==d sources Used:
The Commission would mail this draft environmental assessment to the States for their comments.
.