ML20247J770

Requests Assessments & write-ups for Events That May Be Reportable as Abnormal Occurrences or Other Events of Interest for Second Quarter of FY98

ML20247J770
Person / Time
Issue date:	04/23/1998
From:	Congel F NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Cool D, Roe J, Ten Eyck E NRC (Affiliation Not Assigned), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20247J755	List: ML20247J751 ML20247J770
References
NUDOCS 9805210407
Download: ML20247J770 (7)

Text

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..' yq. t UNITED STATES

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NUCLEAR REGULATORY COMMISSION a

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%, . . . . . '; Acril 3, 0 98 MEMORANDUM TO: Jack W. Roe, Acting Director, DRPM/NRR Donald A. Cool, Director, inaNS/NMSS Elizabeth Q. Ten Eyck, Director, FCSS/NMSS Paul H. Lohaus, Deputy Director, OSP James Lieberman, Director, OE Stuart A. Treby, OGC Charles W. Hehl, Director, DRP/RGN-l James T. Wiggins, Director, DRS/RGN-l A. Randolph Blough, Director, DNMS/RGN-l Loren R. Plisco, Director, DRP/RGN-il Johns P. Jaudon, Director, DRS/RGN-Il Bruce S. Mallett, Director, DNMS/RGN-il Geoffrey E. Grant, Director, DRP/RGN-lit i John A. Grobe, Director, DRS/RGN-Ill l Cynthia D. Peaerson, Di.ector, DNMS/RGN-Ill Thomas P. Gwynn, Director, DRP/RGN-IV Arthur T. Howell, Director, DRS/RGN-IV Ross A. Scarano, Director, DNMS/RGN-IV FROM: Frank J. Congel, Director ,L incident Response Division '

Office fer Analysis and Evaluation of Operational Data

SUBJECT:

REQUEST FOR ABNORMAL OCCURRENCE AND "OTHER EVENTS OF INTEREST" INPUT FOR THE SECOND QUARTER FISCAL YEAR 1998 The purpose of this memorandum is to request your assessments and write-ups for events that l may be reportable as abnormal occurrences (AOs) or "Other Events of Interest" for the second quarter for fiscal year 1998. Please review the events under your cognizance to ensure that all potential AOs and 'Other Events of Interest" have been identified based on the attached AO

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criteria that were published in the Federal Reaister (April 17,1997: 62 FR 18820).

l I

It is essential to apply the AO criteria correctly and consistently. Due in part to a lack of common understanding of the definition of a misadministration as it app!ies to the wrong treatment site, an event was erroneously determined to be a potential AO based on the AO criterion IV(a)(1) and was included in the proposed AO report to the Commission for fiscal year 1997. After Commission review, this event was deleted and a revised AO report (SECY-98-042,

" Amendment to SECY-97-288, ' Report to Congress on Abnormal Occurrences for Fiscal Year 1907"') was resubmitted to the Commission. The Commission agreed with the staff's interpretation of this criterion as expressed in SECY-98-042, and directed the staff to 1

Attachment 9805210407 980506 PDR ORO NOMA PDR

Jack W. Roe. et. al. .

disseminate this interpretation to the appropriate staff in Headquarters. the Regions, and tne Agreement States.

As stated in SECY-98-042, "The staff in consultation with the Office of the General Counsel has determined that a dose to a patient's wrong treatment site, a: a result of a misadministration, is an absolute dose, regardless of the dose such site would have received if the treatment was completed as prescribed in the written directive. Therefore, since the AO criteria for misadministration are based on the definitions of misadministration, the 1 gray (Gy) (100 rad) dose to the bone marrow, the lens of the eye, or to the gonads, as a result of a I misadministration to a wrong treatment site, is an absolute dose."

If your evaluation of an event indicates that it meets the AO criteria or "Other Events of Interest,"

l please submit a write-up, following Management Directive 8.1, " Abnormal Occurrenca Reporting Procedure." Although we are in the process of revising the guideline for "Other Events of Interest" in response to the SRM on SECY-97-288, " Report to Congress on Abnormal Occurrences for Fiscal Year 1997," we will continue to identify events for Appendix C pursuant to the current guideline.

In addition, please remind your staff of the Commission's direction in the SRM on SECY 193, " Implementation of Section 208 Energy Reorganization Act of 1974; Final Policy Staternent," which states, "The staff should file incident information on potential AOs in the public document rooms (PDRs) as soon as possible, in following this direction, the staff should  !'

place already existing documents on these incidents in the PDRs and identify the incident as a ootential AO."

\

We need your input by May 22,1998, to meet the Commission schedule. If there are any l questions or if your office AO coordinator hat. changed, please contact Harriet Karagiannis at (301) 415-6377 or e-mail HXK.

i

Attachment:

As stated ,

cc w/ attachment: Proaram Office AO Coordinators T. J. Carter, NRR W. F. Burton, NRR G. W. Purdy, NMSS M. A. Satorius, OE R. L. Fonner, OGC P. M. Larkins, OSP J.M.Johansen,RI S. J. Vias, Ril C. M. Hosey, Ril R. D. Lanksbury, Rill R. J. Caniano, Rlli C. A. Hackney, RIV F. R. Huey, RIV

.t.a w s. .y

, ,; ,,m 18820 Federal Register N e W. ,

,, m un ,  ! C ' .m an.: r. :'t.>s, u.m -

standards. subert to NSSB approuL W wtcewG .:r C +..m m and tr,unh .n gu ei ~,m.

rac: n e m a t 9. . ;- :s : . c r;- s basic sk2ll t certificates The . w13 .t';,-

.wrnen me,:a n.s e, :me, - ammunuv owd ardnium ns

= review md endorse the st enMs for >,. e due W kial u.ma.s .

specialty certificates estabiahea for naar yr cn> c (D) mdividuais wah npertue m policy development orgamut.ons .s .

more narrowly defined occupations measurement and assessment,includmg experuse in the area of workforce su within the occupational cluster by requirements, individuals with groups other than the voluntary relevant espenence in designing unbiased assessments and performance. expertise in measurement and Partnership. assessment, and non-governmental The enabling legislation requires based assessments.

organizations witi. a demonstred representation of 11 key stakeholder (3) Expestrr-The partnerships history of successfully protecting the groups as described herein: described in paragraph (1) may also rights of women, individuals with include such other individuals who are ,

disabilities, older persons.,and racial, Excerpted fmm the National Skill independent. qualiSd experts in their Standards Act of 1994 ethnic or religious minonties. J fields. Specific representation from Establishment of Voluntary The NSSB Proposed Criteria in Addition community members and institutions l Partnerships to Develop Standards.- to Statutory Criteria Necessaryfor will be determined as is logical for the (1) In General-For each of the Recogm, tion as a Voluntary Partnership cluster, e.g. if training is primarily occupational clusters identified delivered in community and career pursuant to subsection (a). the National The NSSB propor.es that there will be colleges. then representation should Board shall encourage and facilitate the two levels of participation in the establishment of voluntary partt..rships Voluntary Partnerships: (1) general include individuals from that community.

to develop a skill standards system in membership; and (2) voting The voting members of b Voluntary accordance with subsection (d). membership. Partnerships shal! also, to the extent (2) Representatives-Such voluntary General membership will be open to feasible, be geographically partnerships shall mclude the full and all ndividuals inteiested in reprewntative of the United States and balanced participation of- participating in the discussion and reflect the racial, ethnic, and gender (A)(i) representatives of business receiving communice ions about the diversity of the United States.

., including cepresentwves oflarge development of a voiantary skill A C Py of the authorizing legislation employers and representatives of small standards system so the cluster. will be available at the hearitg.

employers) who have expertise m the Representatives from the trade intosted parties may access a copy on area of workforce skill requirements. associations that have received grants the National Skill Standards Board web and who are recommended by national from the Department of Labor or the site, .vww.nssb.org or call (202) 254-business organizations or trade .

Department of Education to establish 8628 to request a copy.

i associations representing employers in skill standards prior to the date of Signed at Washington, DC. this 14th day o the occupat2on or industry for which a enactment of the National Skill April,1997.

standard is being developed; and Standards Act of 1994 are s ifically Een West.

(ii) representatives of trede invited to participate at this I vel, and hect r.Nati not km tandards

"8 $*'g"tive fro t $ en? or tYe ucatso o tab ish

",*Yh';IP*',' p '*h*

• Voting membership will be (FR Doc. 97-9973 Filed 4-16-97; 8:45 aml De determined by the general membership musse coes aw-aus enactment of this title: through a democratic process. The -

(B) employee representatives who v ting membership will make decisions ha th kio regarding the clust**s skill standards NUCLE AR REGULATORY sk 11 ts a 1 a all be systems.%e voting leadership must COGASSSION ,

( (i)b Is recommended by

• ext t possible, the J

recognized national labor organizations [d M W - J' ; of Seceon 208 Energy representing employees in the The NSSB missica statement Reorgentastion Act of 1974; Revision

((* d l .

(U) such other individuals who are Indicates that " voluntary skill standards to Poecy Semesment will be developed by ind Partnership with education, in full rand Acescv:Nelaar Regulatory n - -1 eenployees with c mmunity stakeholder." We NSSB rammi.sinn.

! signinasit riena and tenure in expects that, in keeping with its mission Acnost: Revise poucy statement.

such on or industry as are statement, the Voluntary Partnerships appropriate given the nature and will demonstrate employer leadership, suomeARTt his policy statement I structure of employment in the but will make every effort to include presents the revised criteria the j

, ra==ipataa will use in submitting the occupadon or industry 5- equal numbers from each of the (C) representatives o following three broadly de$ned ups annual abnormal occurrence (AO)

(i) educationalinstitutions, of stakeholder in the voting ership: reports to Congress and the public in a (ii) casunualty-bened organizations; (1) Employer representatives from timely ==aaar as stated in Section 20e (111) State endlocal e6encies with large. medium, smal' mmpanies, public of the Energy Reorganization Ac 1974 as amended.The AO policy

.Aminime.ative control or duection over and private emploprs, and trade ede=elaa, vocational technical tes minor changes maMations. statement education, or employment and training: implement the aston's directiot (2) Worker representatives from (iv) other policy development to develop w.L.a.ing changes as recognized national labor organizations a====ary and revise criteria IIL, "For organizations with expertise in the area and expert workers who are of workforce skill requirements: and Fuel Cycle Liconeses," to include (v) non-governmental organizations representatives of employee facilities that are not limnaed but are with a demonstrated history of associations.

- ATTACHMENT

federal Register <' N " ~ ~

C '

.i , s 188.'l otnerus" r . ta: N m a a u n u ..>  ; mata n o i , c.' t?B ,m u m .,.c. , c.

NRC certification such a, prous 2! af h seu on e rer.6.V posstNe Nt 'RECc-0090. Volumes *nrma M diffusion plants. The revision clanfic, within 13 day s of its receivmg The Commission published a furtne the AO cntena for all fuel facilities information of each AO and shall revision to the AO policy statement and )

including gaseous diffusion plants. provide as wide dissemir.ation to the cntena in the Federal Register on Such revision provides entena which public as reasonably possible of the December 19,1996 (61 FR 67072) to are more specific for fuel facilities in information specified in clauses (3) and reflect changes in the Commission's determinmg those incidents and events (4) as soon as such information becomes policy and changes to the regulations. In that the Commission considers available. the Staff Requirements Memorandum significant from the standpoint of public In July 1975,in the exercise of the dated November 7.1996, SECY-6-193.

health and safety for reporting to authority conferred upon the approving this most recent revision to Congress. Commission by Congress to determine the AO criteria the Commission directed EFFECTIVE DATE: April 17,1997. which unscheduled incidents or events the NRC staff to determine whether ADDRESSES: The final policy statement are significant from the standpoint of modifications to criteria Ill., "For Fuel published in the Federal Register Public health and safety and are Cycle Licensees," were necessary to (December 19,1996; 61 FR 67072) may reportable to Congress as AOs, the explicitly include fuel cycle facilities be examined at the NRC Public Commission developed interim criteria that am not licensed but are otherwise Document Room. 2120 L Street. NW. for evaluating licensee incidents or regulated by NRC such as the gaseous (Lower Level), Washington. DC. events. On the basis of these interim diffusion plants. The MRC staff FOR FURTHER INFORs4ATION CONTACT:

criteria and as required by Section 208 evaluated the criteria applicable to fuel Harriet Karagiannis, Office for Analysis f the Energy Reorganization Act of cycle facilities and has revised the 1974, as amended, the Commission criteria as follows:

and Evaluation of Operational Data. U.S.

Nuclear Regulatory Commission, began issuing quarterly reports to A. AO criteria published December Washington, DC 20555. teli phone: (301) Congress on AOs. These reprts'.' 19.1996: ,

" Report to Congress on Abnormal III. For Fuel Cycle Licensees.

815-6377. intemet: hxi@ntt. gov. 1. A mquired plant shutdown as a Occurrences." have been issued in SUPPLEteENTARY INFORA4A7 TON: NUREG-75/090 and NUREG-0090-1 result of violating a license condition or I. Background through 5 for the penod from January other safet,y limit. ,

II. The Commission Pobcy 1975 through September 1976. On the 2. A major condition not specifically basis ofits experienco in the reparation considered in the license thht requires L Background and issuance of AO reports, t$e immediate remedial action.

Section 206 of the Energy Commission issued a general statement 3. An event that seriously Reorganization Act of 1974 (Public Law of pclicy that described the manner in compromises the ability of a 93-438,42 U.S.C. 5848). u amended. which it would. as part of the routine confinement system to perform its required the Commission to subr2it to conduct of its business, carry out its designated function.

Congress each quarter a report liste g for responsibilities under Section 208 of the B. Revised AO criteria to include that period any AOs at or associated Energy Reorganization Act of 1974, as gaseous diffusion plants:

w;th any facility which is licensed or amended, for identifying AOs and IV. For Fuel Cycle Facilhies.

otherwise regulated pursuant to the making the requisite information 1. A shutdown of the plant or ponion Atomic Energy Act of 1954, as amended. concerning each occurrence available to of the plant resulting from a signiBcant l event and/or violation of a law, cr pursuant to this Act. In a letter to the Congress and the public in a timely Senate Subcommittee on Ove sight of manner. This general statement of regulation, or a license / certificate  ;

Government Management, dated peticy was published in the Federal cedition. ,

October 1,1993, the NRC recommended Register on February 24,1977 (42 FR

2. A major condition or si ficant to Congress a change in the AO report event not considered in the cense /

10950) and provided criteria and certificate that requires immediate publication frequency from quarterly to examples of types of events that the mmdal acum.

yearly. As a result. Senate 790 " Reports Commission would use in determining 3. A majw con & don w signincant Elimination Act." Public Law 104-66 whether a particular event ;s reportable event that seriously compromises the was signed by President Clinton on to Congress as an AO. %e Commission ability of a saisty system to perfonn its i December 21,1995, changing the AO has since refined this statement of designated function that requires report to a yearly publication. policy on a number of occasions to iznznediate mmedal acum to prevent a For the purposes of Section 208 of the reflect changes in regulation and policy. criticality, radiological or chemical Energy Reorganization Act of 1974, as On the basis of these criteria, and u amended, an AO is an unscheduled required by Section 208 of the Energy Pgse hazard incident or event which the **P*ct a dim Reomanlution Act of 1974, as *xPertence is gained, furbr change in Commission has determined to be amended, the Commission has issued

""* #*S significant from the standpoint of public quarterly reports to Congress on AOs he.alth and safety. Each suct report shall since March 1977. nese inports, Abnormal Occurrence Reporting contain: "Repart to Congress on Absormal The AO statement of policy has been (1) The date and place of each Occurrenen." have been issued in developed to comply with the ccunen g ,

legislative intent of Section 208 of the (2) The nature and probable 1 copies of NURECS may be pMamed from the Ene%I R eo%anization Act of 1974, as Consequence of each occurrence; Superintendent of Documents. U.S. covernment amended, to keep Congress and the (3) Trie cause or causes of each Pnniins o ffice. (P.O. sox arosa). we.bington. Dc occurrence; and 20402422s. cop are al.a e..iiable from the public informed of unscheduled (4) Any action taken to prevent National Technical informadon Servia. s2ss Pan incidents or events which the R yal R ad. Springfield.VA 22161. A copy is Commission considers significant from ITCMI*nce* available for mapection and/or copying for a fee in The Commission aise shall provide as the NRc Public Document itoons 2:2o L street. NW the standpoint of public health and wide dissemination to the public of the (Lower Levell. Wahston. DC 2o037. , safety. The policy reflects a range of

V. W V 7 .-

.M ,L 18822 Federal Rester ~

Commiss4vn tu.wo c ws av Enmv tbrmm .. * ,

m.puse r-qwrw n's ;n acenW health and safets concerns and is -

imendad applicable to mcidents and c ents certded facihties Repnt's .uil coser An incident or esent will be involving a single occupational warmer as well as those having an m etall certain unsdedul-d incidents or es ents considered an AO ifit involves a m related to the manufacture, reduction in the degree of protectmn imnact on the general public.

construction, or oneration of a facility or the public health or safety. This typ,-

the policy statement conta2ns criteria that include the reporting thresholds for conduct of an activ"y subject to the incident or event wouM have a requirements of Parts 20,30 through 36. moderate or more severe impact .n th determining those incidents and events 39,40,50,61. 70, 71. or 72 of Chapter public health or safety and could that are reportable by NRC for the include, but need not be limited to the purposes of Section 208 of the Energy I. Title 10. Code of Fedeml Regulations (10 CFR). fojjowjog.

Reorganization Act of 1974, as amended. The Commission has Through an exchange of information. (1) Moderate exposure to, or releaw established the reporting thresholds at a Agreement States provide information of, radioactive mi.terial licensed by or level that will ensure that all events that to the NRC on incidents and events otherwise regulated by the Commisuu should be considered for reporting to involving applicable nuclear materials (2) Maj.or degradation of essential Congress will be identified. At the same that have occurred in their States. Those safe;y.related equipment: or time, the thresholds are generally above events reported by Agreement States (3) Major deficiencies in design, the normal level of reporting to NRC to that reach the thresimid for reporting as construction, use of, or management exclude those events that involve some an AO are also published in the " Report controls for facilities or radioactive vanance from regulatory limits, but are to Congress on Abnormal Occurrences." material licensed by or otherwise not significant from the standpoint of 2. Definition of terms. As used in this regulated by the Commission.

public health and safety. policy statement: Cnteria by type of event used to  ;

Licensee Reports N An "abno mal occurrence" means determine which incidents or es ents an unsch'edul. i inci tent or event at a wiJl be considered for reporting is Am This general statement of policy will facility or asso-.ated with an activity are set out in Appendix A of this po!ic.

not change the re arting requirements that is licensed or otherwise regulated, imposed on NRC icensees by statement.

pursuant to the Atom 2c Energy Act of Commission regulations. lice'nse 1954, as amended, or the Energy 4. Commission dissemination of AO conditions, or techrucal specifications Reorganization Act of 1974, as information.

(TS). NRC licensees will continue to amended, that the Commission (a) The Commission will provide as submit required reports on a wide determines to be significant from the wide a dissemination ofinformation to spectrum of events. including events standpoint of public heelth and safety; the public as reasonably possible.

such as instrument malfunctions and and Information on potential Aos (events deviations from normal operating that may meet the AO cnterial will be procedures that are not significant from (b) An " unintended radiation exposure" includes any occupational sent to the NRC Public Document Roon the standpoint of the pubhc health and and all local public document rooms as 2 exposure, exposure to the general safety, but do provide data useful to the public, or exposure as a result of asoon as possible after the staff l Commission in monitoring operating determines that the incident is a rnedical misadministration (as defined l trends oflicensed facilities and in in $ 35.2) involving the wrong potential AO. A Federal Register notica comparing the actual performance of individual that exmeds the reporting will be issued on enca AO report with these facilities with the potential values established in the regulations. copies distributed to the NRC Public perfor: nance for which the facilities Document Room and alllocal public /

were designed and/or licensed.

All other reported medical l N si will be considered document rooms. When additional Information pertaining to all events misadmitustrat for reporting as an AO under the enteria information is anticipated, the notice reported to the NRC will continue to be for medical licensees. In addition, will state that the information can be 1

obtained at the NRC Public Document made document available andperusal.

rooms for public placed In in the public unintended radiation exposures include, Room and addition, the NRC publishes annual any exposure to a nursing child, fetus, rooms.

reports on events (NUREG--1272 series). or embryo as a result of an exposure (b) Each year, the Commission will Information can also be obtained by (other than an oaupational exposure to an undeclarea pregnant woman) to a submit a report to Congresa listing for writing to the U.S. Nuclear Regulatory that period any AOs at or associated Co==6 ton, Public Document Room, nursing mother or pregnant woman above specifled Values, with any facility or activity which is 21201. Street, NW. (Iower IAvel) licensed or otherwise regulated

3. Abnorrnaloccurrencegeneral Washington, DC 20555-0001. In pursuant to the Atomic Energy Act of addition, the Commission will continue storernent ofpolicy.N Commission 1954, as amended, or the Energy to issue news announcements on events will apply the following policy in Reorganization Act of 1974, as that seem to be newsworthy whether or determining whether an incident or amended.This report will contain the event at a facility or involving an not they are reported as AOs. date, place, nature, and probable activity that is licensed or otherwise D. m rw-.66 Policy--General regulated by the Commission is an AO consequence of each AO, the muse or Statement of Policy on laplementation within the purview of Section 208 of the causes of eac1.*.0, and any action of Section 20s of b Energy to prevent recurrence.

Reorganization Act of 1974, as ' AP A-Appendix A-AbnormalOccurrence Amended ,j,j,? orF Fu ye 1i Critoria

.pplicable to licensee, and certificate holders. such ,,4 gg

1. Applicability. Implernentation of l the s==ous diffusion P ants (GDPs), other criterte g Section 208 of the Energy ** *

", determine which incidents or events wilt t Reorganization Act of 1974, as Ne $'g*"y'*"j,*.h'"

.i.o d. .ppiw i e..... ., eer,si.d s.citino. .uch rns considered for reporting as F ..

amended. AbnormalOccurrence follows:

as the corn.

Reports involves the conduct of

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l r eaut*t d1 htqthitit e vi b s;,ec.a. . rm w: .s . - lx e ': c e:.m +.

• . J. For All Lionwe. ~% - vg - - -

i f Human Expent~ w k n:: a : - Q , [.;y ea a. , t.w 1 cmed Mat rul _ ,_.y .

1 Any unintenced rea:;ca npos r i , r wr e, mr n - . . . , ,,

- , w.- sAR f 3 a: wm an u r.

an adult lany mdividual 18 years of age or inan bciuded b n pr.q m um3, ,

oldtr) resulting in an annual total effn.t n e meno.; ar,. .n%e mm x,m.s .r.g s - 3 ,

that are Icst, stoien. or abandoned und r tne 2 Personnel error or pntecuraa dose equivalent (TEDE) of 250 millisievert defic.encies tha: result en loss of plan (mSv)(25 rem) or more, or an annual sum of following conditions sources abandoried in capabihty to perform essential safety thi deep dose equivalent (external dose) and accordance with the requirements of to CFM Enctions so that a release of radioactive committed dose equivalent (inta'2e of 39 77(c) scaled sources contained in labeled, matenals. which could resul in exceedmg r:dioactive matenal) to any individual urgan rugged sourte housmgs; recovered sources the dose hmits of to CFR Part 100 or 5 times or tissui other than the lens of the eye. bone with sufficient indication that doses in the dose limits of 10 CFR Part 50. Appendix uttmw and the gonads, of 2500 mSv (250 excess of the reporting thresholds specified A. GDC 19, could occur from a postulated rem) or more; or an annual dose equivalent n AO criteria I A.1 and I.A.2 did not occur transient or accident Q g.. loss of emergency ta th)1:ns of the eye, of 1 Sv (100 rem) or during the time the sourm was missmg; and c re c ling system. loss of control rod more; or an annual sum of the deep dose equiv~ lent and committed dose equivalent t unremverable sources lost under such conditions that doses in excess of the

'Y"I reporting thresholds specified in AO cnteria III. For Fuel Cycle Facilities

( retn) :or an low dose 1.A.1 and I.A.2 were not known to have 1. A shutdown of the plant or portion of equirlent to the skin or extremities of 2500 ccuned. the plant resulting from a significant event mSv (250 rem) or more. 2. A substantiated case of actual or and/or vioiation of a law regulation. or a

2. Any unintended radiation exposure to attempted theft or diversion of licensed license / certificate condition any mifor (an individual less than is years matenal or sabotage of a facility. 2. A major condition or significant event of age) resulting in an annual TEDE of 50 3. Any substantiated loss of special nuclear not considered in the license / certificate .nat rnSv (5 rern) or more, or to an embryo / fetus matenal or any substantiated inventory requires immediate remedial action.

resulting in a dose equivalent of 50 mSv (5 discrepancy that is judged to be significant 3. A maior condition or s gnificant event rem) or more. wmally expected performance. that senously compmmises the abdity of a rdatin safety system to perform its designated

3. Any radiation exposure that has resulted and tb is judged to be caused by theft or n unintended permanent fun.tional damage diversion or by substamiel breakdown of the function that requires .mmediate remed. I to r.n c rgan or a physiological system as accountability *ystem action to prevent a cnt.cality. radiological or cetennined by a physician. enemical process her.ard 4 Any substantal breakdown of pnpical B. Discharge or Duspersal of Radoooctave secunty or matenal control (i e , access ,

Matenal from /ts intended Place of control contairunent or accountabihty A medical misadmmistration that.

Confinement systems) that significantly weakened'the (a) Results in a dose that is (1) equal to or

1. Thi release of radioactive matenal to an protection against theft, diversion, or greater than 1 gray (Gy)(100 reds) to a maior unrestricted area in concentrations w hich. if sabotage. pma f the bone marrow, to the lens of the eviraged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, exceed a Other bnts # e . Those Concerning eye, or to the gonads, or(2) equal to or greater 5000 times the values specified in Table 2 of Design. Analysis. Construceson, Testmg. than to Gy (1000 rads) to any other organ; Appendix B to 10 CFR Part 20. unless the Opention. Use. or Dnsposal oflacensed and lic1nsee has demonstrated comphance wnth F cs/ des r Fegulated Morenalst (b) Represents either (1) e dose or dosage 5 20.1301 using il 201302 (b) (1) or 201302 that is at least 50 percent greater than that 1 An accidental cnticality (10 CFR prescnbed m a wntien directive or(2) a l (b) (2) (ii).

2. Radiation levels in excess of the design 70 52(all. prescnbed dose or dosage that (i) is the l voues for a package,or the loss of 2 A maior deficiency m design. wr ng radiopharmaceutical.* or (iil !s corfin; ment of radioactive matenal resulting construction, cont ol, or operation b sving dehvered by the wrong route of m orn or more of .he following: (a) a significant safety implications requiring administration, or (iii) is dehvered to the r:diition dose rate of to mSv (1 rem) per immediate remedial action. weig treatment sh, or M b MW h 3 A senous deficiency in management or the wr g treatment m de or(vlis from a hc ar or more at i meter (3.28 feet. ' rom the seceuible exte-sal surface of a package procedural controis in maior areas. ' 8 * ""

cont:ining radioactive material; (b) a 4. Senes of events (where indivious!

evente re not of major importance). V. Guidelinee for "Other Eventa ofInterest" r"ation dose rate of 50 mSv (5 *em) per recurnog mcidents, and incidents with The Commission may determine that hour or more on the eccessible external events other than AOs may be of interest to surfsca of a package containing radioactive implications for similar facilities (generic material and that meet the requirements for incidents) that create a mapr safety concern. Congress and the public and be included m "cxclusive use" as defined in to CFR 71.47, an Appendix to the AO re rt as "Other II. For t%==erdal Nuclear Fewer Pfard Events of Interest." Guide es for events to or (c) release of radioactive material from a 1im n**** be included in the AO report for this purpose package in amounts greater than the a e items that may possibly be pertenved by regulatory limits in to CFR 71.51(a)(21 A. Moffunction of Facihty, Structures, or the public to be of health or safety Equipment sigmficance. Such items would not involve a C. Th$ Drversion, or bss of Lscensed Morenal, or Sobotage or Secunty Breach ' 1. Exceedmg a safety hmit of license mapr reduction in the level of protection

1. Any lost, stolen, or abandoned sources technical specification (TSI ($ 50 36(cIl' . pmvided for public health or safety;

2. Serious degradation of fuel integnty that cxceed 0.01 times the Ai values, as listed therefore, they would tiot be reported as pnmary coolant pressute boundary, or abnormaloccurrences. An example is an in to CFR Part 71, Appendix A. Table A-1, Pnmary containment boundary. event where upon final evaluation by an NRC

3. loss of plant capability to perforrn incident Investigation Team, or an information pertainin6 to certain incidents rney essential safety functions so that a release of Agreement State equivalent response, a be cather classend or under consideration for radioactive materials, which could result in claaetacation because of national securit) determination is made that the event does irnplications C.aasi6ed information wm be exceeding the dose limits of 10 CFR Part 100

m. . eld wnen fortruly reparung these incidents of 5 times the does limits of 10 CFR Part 50,

• The wrong radiopharmaceutical as used in the b accordance with Section 2oe of the Energy Appendia A, General Design Cnterion (CDC) Ao criterion for medical misadministration refers Reorganiastion Act of 1974. as amended. Any 19. could occur from a postulated transient to any radiopharmaceutical other than the one cleasined details regarding these incidents would or accident le g., loss of emergency core listed in the written directive or in the chnical be available to the Congrees, upon rquest, under procedures rnenual cooling system, loss of control rod system).

appropriate escurity arrangements.

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• Annette WettoCook. [3efore aua..ce of L i7ropo.ed "' h' h 'F "I ' "'" 'd 'lI"'""' b '"d' "?

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Actmg Secretary of the commmun bcense amendments, the Commission

((1 ed will have made 'indings required by the (FR Doc. A9912 Filed 4-16-K 9 4 5 aml Atomic Energy Act of 1954 as amended This proposal dor act r.rece t h<

sw uocoorr m ie probability of a new or diGerent type of Ithe Act) and the Commission's regulations. accident from any accader.: previously evaluated. The proposed change only NUCLEAR REGULATORY Pursuant to 10 CFP 30.91(a)(6) for reconciles the scope of response time testing COMMISSION amendments to be granted under descnbed in the surveillance requirements exigent circumstances, the NRC staff with the elimination rf selected response (Docket Nos. 50-387 and 50-388] ""# d*termine that the amendment

'2m' '"*8. Pnformed in accordance with request invol'.es no significant hazards the NRC-approved methodology delineated Pennsylvania Power & Ught Company; consideration. Under the Commission's - in the LTR.

Notice of Consideration ofissuance of regulations in to CFR 50 92 this means In.plementation of the LTR methodology Amendments to Facility Operating that operation of the facility in for eliminating selected response time testing License; Proposed No Significant accordance with the proposed also does not creata the probability of a r.ew or different type of accident from any Hazards Consideration Determination' amendment would not (1) involve a accident previously evaluated. A rev.ew of.

and Opportunity for a Hearing significant increase in the probability or e j I^ d' g mj;es [the a c piant g g The U.S. Nucleat Regu1atory P VI 8Y ,, p mmission (the Commission) is evaluated; or (2) create the possibility of the instruments and relays can be detected bs considering issuance of an amendment a new or different kind of accident from other Technical Specification surveillance to Fa:ality Operating Licer ;e Nos. NPF- any accident previously eialuated; or A review of SSES response time testing

13) involve a significant rt. duction in a history revealed one re>ponse time test 14 and NPT-22. issued to t' pennsylvania Power & Light Company (PP&LJ (the margin of safety. As required by 10 CFR failure. This failure would have been licensee) for operation of the detectable by the logic system functional test 50 911a), the licensee has provided its for this channel Redundancy and diversity Susquehanna Steam Electnc Statwn analysts of the issue of no significant f the affected channels provide additional Units 1 and 2. located in Luzerne hazards consideration, which is "'" " 'h * ' 'II

• fI'Cd I""C'*"' "'l l Countv. Pennsvivania. pn,sented below. perste within the acceptance hmits assumea Thipropose'damendment would in the P lant safety analyses. l 1 The proposed change does not involve cl .rify the scope of the surveillance a significant increase in the probabthty or PP&L's adherence to the conditwns listed 1

I requirements for response time testing c n m uencu Ian accident previously in the NRC SER l Safety Evaluation Reportl evaluated. for the LTR provides additional assurance ofinstrumentation in the reactor that sluggish response ofinstruments and protection system. a. solation actuation This proposal does not involve a significant mcrease in the probabihty or relays will be detected by the other required system and emergency core cochng Technical Specification tests. A review of system in the Technical Specifications consequences of an accident nrevioudv evaluated The proposed change only various safety analyses performed as part of (TSs) for each unit (Sections 4.3.1.3. PP&L's to CFR 50.59 safety evaluation 4.3.2.3, and 4.3.3.3). reconciles the scope cf response tirne testing desenbed in the surveillance requirements revealed that the five-second delay did not PP&L's request for a license adversely affect the assumptions in the with the elimination of selected response respective analyses.

cmendment for each unit under esigent time testing, performed in sc. rdance with circumstances resulted from its recent the NRC.spproved methodology delineattd Therefune, the proposed change does not discovery that the wordinE of the TS in the BWROC IBoiling Water Reactor create the possibility of a new or different kind of accident from any accident surveigjance was not reconciled with the Ow ers Group! Licensing Topical Repuit previously evaluated.

initiative to eliminate selected response RTR) EDO-32291. ' System Analyses for 3. The proposed change does not involve time testing from the TSs. Accordingly. Elimination of Selected Response Tirne Testing Requirements / dated January 1994. a significant reduction in the roargin of th) licensee determined that this safety, condition was a TS noncompliance and implementation of the LTR (i.e.. elimination of response tirne testing for selected The change does not involve a significant that prompt action to correct this reduction in the margin of safety. The situation was necessary because failure instrumentation in the Reactor Protection System. Isolation Actuation System and proposed change only reconciles the scope of t3 satisfy TS surveillance trquirements Emergency Core Cooling System) does not response time testing described in the for response time requires ti at the surveillance requirements with the incream the probability or consequences of various instruments and systems be an accident or malfunction of equipment e11rnination of selected response time testing, declared inoperable, resulting in the TS i t to safety as previously evaluated in performed in acrordance with the NRC.

th aP ap ved methodology delineated in the required entry into cold shutdown for Unit 1 (sbutdown from 100% power) All SSES coroponent model numbers were analyzed for the failure mode of a sluggish Implementation of the LTR methodology and the prevention of fuel movement for eliminating selected 'esponse time testing and the imposition of additional response. As documented in tk LTR. each I component's sluggish response can be also does not involve a significant reduction I restrictions for Unit 2 currently in a detected by other Technical Specification in the margin of safety. The current resporse refueling outage. The staff finds that it required tests (functional tests. calibrations times are based on the maximum allowable would be more prudent to permit the and logic system functional %sts). This values ensumed in the plant safety analyses.

licensee to rely upon the existing The analyses conservatively establish the supports the contention that the use of such response time testang for Unit 1 in lieu " qualitative" testing does not affect the margin of safety. As descnbod above, the of testing at power, and forcing an bility of the associated systems to elimination of selected response time testing ca7orm p.

unnecessary plant challenge by shutting required responu time.

their intended function within their does not affect the capability of the associated systems to perforrn their intended down this plant, and also in lieu of function within the allowed response time restricting refueling and other activities Based upon the analysis presented above, ppa L concludes that the proposed action used as the basis for the plaat safety analyses Plant and system response to an initiating

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