ML20237A554

Discusses Resolving Issues of Discrepancy Between Repts in Nuclear Materials Events Database (Nmed) & Repts Submitted to Nmed by Commonwealth of Massachusetts

ML20237A554
Person / Time
Issue date:	05/21/1998
From:	Congel F NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Martin T NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML20237A549	List: ML20237A547 ML20237A554
References
NUDOCS 9808140173
Download: ML20237A554 (2)

Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4 001 hk L.,

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MEMORANDUM TO: Thomas T. Martin, Director Office for Analysis and Evaluation ac of Operational Data -<

FROM: Frank J. Congel, Director

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SUBJECT:

RESOLVING ISSUE OF DISCREPANCY BETWEEN REPORTS IN NMED AND REPORTS SUBMITTED TO NMED BY COMMONWEALTH OF MASSACHUSETTS The integrated Material Performance Evaluation Program (IMPEP) report for the Commonwealth of Massachusetts Agreement State program, which ovaluates the program from March 21,1997 through the end of CY 1997, indicated that only three of nine reports submitted to NRC by the Commonwealth of Massachusetts (which became an Agreement State on March 21,1997) have been entered into the Nuclear Material Events Database (NMED).

Mr. Samuel L. Pettijohn, the NMED project manager, reviewed this issue with the NMED contractor, Idaho National Engineering and Erivironmental Laboratory (INEEL), and consulted with staff from the Office of State Programs, who made an inquiry to the Commonwealth of Massachusetts regarding the method and date the event reports were sent to INEEL. Mr.

Pettijohn found that the INEEL staff did not have a record of receiving the missing event reports, and the Commonwealth of Massachusetts staff did not have a record of sending the reports to INEEL.

Corrective ActiQat 1

The missing event reports were sent to INEEL by the Massachusetts program on April 7,1998, j and INEEL has completed coding the data into the NMED. j 1

Currently, upon receipt of event reports from Agreement States by e-mail or on diskette the  !

INEEL NMED project manager sends an e-mail message acknowledging the receipt of the I reports to the Agreement State. INEEL is modifying this procedure to include the following:

4 An acknowledgment will be sent by regular mailif an Agreement State does not have e-mail capability.

An e-mail acknowledgment will be sent to NRC Regional offices who send event information directly to INEEL.

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• A copy of all acknowledgments will be sent to the AEOD NMED project manager and designated staffin OSP.

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1r(addition, OSP has agreed to:

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' Add the following or equivalent statement to Section 1.1 of the " Handbook on Nuclear )

Material Event Reporting in Agreement States": -

The INEEL acknowledges by e-mail (if available, otherwise by regular I mail) all submissions of event reports sent directly to the INEEL. You should receive acknowledgment by e-mail within two working days or acknowledgment by regular mail within seven working days. If you do not receive acknowledgment of your submission, you may contact the j INEEL by e-mail (GDR@lNEL. GOV) or by regular mail at Idaho National Engineering and Environmental Laboratory, Attention: Gary Roberts, P.O. Box 1625, Idaho Falls, ID 83415.

In the interim, OSP will issue an All Agreement States Letter conveying the above information to the States. A

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Instruct IMPEP teams to compare the number and type of event reports recorded in NMED and the number and type of event reports on record at an Agreement State or NRC Region during IMPEP reviews and Annual Meetings.

The IMPEP teams can verify this information by contacting the NMED project manager, Samuel L. Pettijohn, at 415-6822, or by e-mail at SLP.

cc: R. Bangart, OSP P. Lohaus, OSP l

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NUCLEAR REGULATORY COMMISSION i WASHINGTON, D.C. 20555-0001

% .u o f April 23, 1998 MEMORANDUM TO: Jack W. Roe, Acting Director, DRPM/NRR Donald A. Cool, Director, IMNS/NMSS Elizabeth Q. Ten Eyck, Director, FCSS/

Paul H. Lohaus, Depupty D' James Lieberman, Director, OE Stuart A. Treby, OGC Charles W. Hehl, Director, DRP/RGN-l h- -

James T. Wiggins, Director, DRS/RGN-l A. Randolph Blough, Director, DNMS/RGN-l hkcd) Yg Loren R. Plisco, Director, DRP/RGN-Il Johns P. Jaudon, Director, DRS/RGN-Il by h kort .5o Bruce S. Mallett, Director, DNMS/RGN-II Geoffrey E. Grant, Director, DRP/RGN-ill (h M b John A. Grobe, Director, DRS/RGN-ill N O b N Cynthia D. Pederson, Director, DNMS/RGN-Ill Thomas P. Gwynn, Director, DRP/RGN-IV Arthur T. Howell, Director, DRS/RGN-IV h M'

Ross A. Scarano, Director, DNMS/RGN-IV FROM: Frank J. Congel, Director V N Incident Response Division Office for Analysis and Evaluatio 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 may be reportable as abnormal occurrences (AOs) or "Other Events of interest" for the second quarter for fisca! 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 criteria that were published in the Federal Reaister (April 17,1997: 62 FR 18820).

It is essential to apply the AO criteria coi,ectly and consistently. Due in part to a lack of common understanding of the definition of a misadministration as it applies to the wrong treatment site, an event was erroneously determined to be a potential AO based on the AO criterion IV(a)(1) {I 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 1997'") was resubmitted to the Commission. The Commission agreed with the staff's i interpretation of this criterion as expressed in SECY-98-042, and directed the staff to I

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Jack W. Roe, et. al. disseminate this interpretation to the appropriate staff in Headquarters, the Reg' ions, and the 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, as 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 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,"

please submit a write-up, following Management Directive 8.1," Abnormal Occurrence 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 Abnorma!

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 airection in the SRM on SECY 193, implementation of Section 208 Energy Reorganization Act of 1974; Final Policy Statement," 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 Dotential AO."

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

Attechment: 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, Rll C. M. Hosey, Ril R. D. Lanksbury, Rlli R. J. Caniano, Rlli

C. A. Hackney, RIV F. R. Huey, RIV i

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. 18820 .- Federal Register / Vol. 62, No. 74 / Thursday, April 17, 1997 / Notices standuds, subject to NSSB approval, for successfully protecting the rights of (3) Community representatives from basic skill certificates. They will also racial, ethnic, or religious minorities, education and training institutions, review and endorse the standards for women, individuals with disabilities, or community-based organizations, older persons; and relevant state and local agencies, other specialty certificates established for more narrowly defined occupations (D) individuals with expertise in policy development organizations with within the occupational cluster by measurement and assessment, including expertise in the area of workforce skill relevant experience in designing requirements, individuals with groups other than the voluntary Partnership. unbiased assessments and performance- expertise in measurement and based assessments.

assessment, and non-governmental The enabling legislation requhvs representation of all hoy stakeholder (3) Experts-The partnerships organizations with a demonstread history of successfully protecting the j groups as described herein: described in paragraph (1) may also include such other individuals who are rights of women, individuals with Excerpted from the National Skill Independent, qualified experts in their disabilities, older persons, and racial. ,

Standards Act of1994 fields.

ethnic or religious minonties.

Establishment of Voluntary Specific representatir>n from I

Partnerships to Develop Standards.- The NSSB Pmposed Criteria in Addition community members and institutions to Stotutory Critena Necessaryfor will be determined as is logical for the (1)In General-For each of the Recognit on as a Voluntary Partnership cluster,e.g if training is primarily occupational clusters identified pursuant to subsection (a), the National The NSSB proposes that there will be deliverad in community and career '

Board shall encourage and facilitate the two levels of participation in the col' ges, then representation should establishment of voluntary partnerships Voluntary Pannerships:(1) general include individuals from that community.  !

to develop a skill standards system in membership; and (2) voting The voting members of the Voluntary accordance with subsection (d). membership.

(2) Representatives - Such voluntary Partnerships shall also, to the extent General membership will be open to pannerships shall mclude the full and feasible, be geographically allindividuals interested in representative 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 communications about the (including representatives of large diversity of the United States.

development of a voluntary skill A c Py of the authorizing legislation employers and representat2ves of small standards system nor the cluster. will be availab!e at the hearing.

employers) who have expertise in the Representatives from the trade area of workforce skill requirements, Interested parties may access a copy on associations that have received grants and who are recommended by national the National Skill Standards Board web from the Department of Labor or the site, www.nssb.org or call (202) 254-business organizations or trade Department of Education to establish 8628 to request a copy, associations representing employers in skill standards prior to the date of the occupation or industry for which a enactment of the National Skill Signed at Washlagton, 'C, this 14th day o:

standard is being developed; rnd Standards Act of 1994 are specifically April,1997.

(ii) representatives of trade Edie West, invited to participate at this level, and te en o La or e mm hip e el oo ent o ucatio o ab ish Voting membership will be (FR Doc. 97-9973 Filed 4-16-97; 8:45 ami determined by the general membership sumo ecos waus enactment of this title; through a democratic process.The (B) employee re resentatives who y ting membership will make decisions

• • P* " kio regarding the clust#s skill standards NUCLE AR REGULATORY

,j all h'[g*b (1) ts ividuals recommended by systems.'Be votingleadership must e ext ossible, e CORDSSSION recognized national labor organizations ;to representing employees in the implementmeon of Section 208 Energy 1 The NSSB missiw statement l

" indicates that " voluntary skill standards Reorganization Act of 1974; Revision

[(ii) such other individu d I d is who are will be developed by industry in full to Policy Statement ]

Partnership with education, labor and Aasecv: Nuclear Regulatory j nonmanagerial employees with The NSSB Commission. j signiBeant experience and tenure in community stakeholder.",th its mission expects that,in keeping wi Acnost: Revise policy statement. l such occupation or industry as are statement, the Voluntary Partnerships [

appropriate given the nature and will demonstrate employer leadership, suemeARY:This policy statement structure of employment in the but will make every effort to include presents the revised criteria the occupation or industry; equal numbers from each of the Commission will use in submitting the (C) representatives of- following th ee broadly defined groups annual abnormal occunence (AO)

(i) educationalinstitutions, of stakeholder in the voting leadership: reports to Congress and the public in a (ii) community-based organizations: timely manner as stated in Swtion 20e (iii) State and local agencies with (1) Employer representatives from administrative control or direction over large. medium, small companies, public of the Energy Reorganization Act of 1974, as amended.The AO policy and private employers, and trade education. vocational technical statement incorporates minor changes education, or employment and training: associations.

(2) Worker representatives from irnplement the Commission's directioi (iv) other policy development to develop conforming changes as organizations with expertise in the area recognized nationallabor organizations and expert workers who are necessary and revise criteria IIL. "For of workforce skill requirements; and Fuel Cycle Licensees," to include (v) non-governmental organizations representatives of employee associations. facilities that are not licensed but are with a denionstrated history of

• ATTACHMENT

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Fed:ral Register / Vol. 62. No. 74 / Thursday. April 17, 1997 / Notices 18821

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otherwise regulated and will receive information specified in clauses (1) and NUREG-0090-6 through 10 and l

NRC certification such as gaseous l (2) of this section as reasonably possible NUREG-0090, Volumes 1 through 18.

diffusion plants. The revision clarifics within 15 days ofits receiving The Commission published a further

> the AO criteria for all fuel facilities information of each AO and shall revision to the AO policy statement and including gaseous diffusion plants. provide as wide dissemination to the criteria in the Federal Register on {

l Such revision provides criteria which public as reasonably possible of the December 19,1996 (61 FR 67072) to I are more specific for fuel facilities in information specified in clauses (3) and reflect changes in the Commission's det:rmining those incidents and events (4) as soon as such iriformation becomes policy and changes to the regulations. in ,

thit the Commission considers available. the Staff Requirements Memorandum I significant from the standpoint of public in July 1975,in the exercise of the dated November 7,1996. SECW96-193, b:alth and safety for reporting to authority conferred upon the f approving this most recent revision to l 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 sta'ement are significant from the standpoint of modifications to criteria III., "For Fuel published in the Federal Register Public bealth and safety and are Cycle Licensees." were necessary to (Dec:mber 19,1996; 61 FR 67072) may rep rtable to Congress as AOs the explicitly include fuel cycle facilities be cxarnined at the NRC Public Commission developed interim criteria that are not licensed but are otherwise Document Room. 2120 L Street. NW. f r evaluating licensee incidents or regulated by NRC such as the gaseous (Low;r Level). Washington, DC. events. On the basis of these interim diffusion plants. The NRC staff FOR FURTHER INFORMATION CONTACT: criteria and as required by Section 200 evaluated the criteria applicable to fuel Hirri:t Karagiannis Office for Analysis f the Energy Reorganization Act of cycle facilities and has revised the cnd Evaluation of Operational Data U.S. 1974, as amended, the Commission criteria as follows:

Nucl:ar Regulatory Commission, began issuing quarterly reports to A. AO criteria published December WasLington, DC 20555, telephone: (301) Congress on AOs. These reports.8 19,1996:

415-6377, internet: hxk@nrc gov. " Report to Congress on Abnormal III. For Fuel Cycle Licensees.

Occurrences," have been issued in 1. A required plant shutdown as a SUPPLEMENTARY INFORMATION:

NUREG-75/090 and NUREG-0090-1 result of violating a license condition or I. Background through 5 for the period from January other safety limit.

II. Thi Commission Policy 1975 through September 1976. On the 2. A major condition not specifically L Background basis ofits experience in the preparation considered in the license that requires and issuance of AO reports, the immediate remedial action.

Section 208 of the Energy Commission issued a general statement 3. An event that seriously R; organization Act of 1974 (Public Law of policy that described the manner in compromises the ability of a 93-438,42 U.S.C. 5848), as amended. which it would. as part of the routine confinement system to perform its required the Commission to submit to conduct of its business, carry out its designated function.

Congress each quarter a report listing for responsibi'ities under Section 208 of the B. Revised AO criteria to include th:t penod any AOs at or associated Energy Reorganization Act of 1974, as gaseous diffusion plants:

Wth any facility which is licensed or amended, for identifying Aos and IV. For Fuel Cycle Facilities. ,

otherwise regulated pursuant to the making the requisite information 1. A shutdown of the plant or portion Atomic Energy Act of 1954, as amended. concerning each occurrence available to of the plant resulting from a significant event and/or violation of a law, or pursuant to this Act. In a letter to the Congress and the public in a timely l Sen2) Subcommittee on Ove sight of manner. This general statement of regulation, or a license / certificate Government Management, dated policy was published in the Federal c ndition.

October 1.1993, the NRC recommended Regis'ter on February 24,1977 (42 FR 2. A major condition or si ificant to Congress a change in the AO report 10950) and provided criteria and event not considered in the cense /

publication frequency frorn quarterly to examples of types of events that the certificate that requires immediate yearly. As a result. Senate 790," Reports Commission would use in determining remedial acdon. l Elimination Act." Public Law 104-66, 3

whether a particular event is reportable ,ye t a senously m to w;s signed by President Clinton on to Congress as an AO. The Commission the December 21,1995, changing the AO has since refined this statement of ability of a safety system to perform its rt to a yearly publication. desi8"'ted function that requires refor the purposes of Section 208 of the policy on a number of occasions to reflect changes in regulation and policy. 12nrnedate mmedal acdon to prevent a Energy Reorganization Act of 1974, as On the basis of these criteria, and as criticality, radiological or chemical amended, an AO is an unscheduled incident or event which the required by Section 208 of the Energy Pgse ed that as additional Reorganization Act of 1974, as Commission has determined to be amended, the Commission has issued experience is gained, further changes in significant from the standpoint of public quanerly reports to Congress on AOs m criten,a may W mquir, i health and safety. Each such report shall since March 1977. These reports, Abnormal Occurrence Reporting cont:In: " Report to Congress on Abnormal (1) The date and place of each The AO statement of policy has been Occurrences." have been issued in ccunence; , developed to comply with the (2) The nature and probable legislative intent of Section 208 of the 1 Copies of NtJREGS may be purchased from the con uence of each occurrence; superintendent of tscumenta, u.s. covernment Ene'EY Reo'8anization Act of 1974, as (3 e catise or causes of each Printing Office. (P O. BOX 37082). Washington. DC amended, to keep Congress and the occurrence; and 2m2-932s. copies are also aveil.bte from the public informed of unscheduled (4) Any action taken to prevent Nati nal Technical information Service. 528s Port incidents or events which the Royal Road. Springfield. VA 22161. A copy is j recurrence. available for inspection and/or copying for a fee m. Commission considers significant from )

Thi Cornmission also shall provide as the NRc Public Document Room. 2120 L Street. NW the standpoint of public health and 1 i

wida dissemination to the public of the (Lower Leven, wegion. Dc 2oon safety. The policy reflects a range of l l

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.* ,% j 18822 Federal Register / Vol. 62, No. 74 / Thursday, April 17, 1997 / Notices health and safety concerns and is Commission business and does not Energy Reorganization Act of 1974, as applicable to incidents and events impose requirements on licensees 2 or amended.

involving a single occupational worker certified facilities. Reports will cover An incident or event will be as well as those having an overell certain unschedukd incidents or events considered an AO ifit involves a mam imnac'. on the general public. related to the manufacture, reduction in the degree of protection o the policy statement contains criteria construction, or operation of a facility or the public health or safety. This , type o that include the reporting thresholds for conduct of an activ"y subject to the incident or event would have a determining those incidents and events requirement;, of Parts 20,30 through 36, moderate or more severe impact .n th. )

that are reportable by NRC for the 39,40. 50,61,70,71, or 72 of Chapter public health or safety and could purposes of Section 208 of the Energy I. Title 10. Code of Federal Regulations include, but need not be limited to the Reorganization Act of1974,as (10 CFR). following: i amended.The Commission has Through an exchange ofinformation, (1) Moderate exposure to, or release established the reporting thresholds at a Agreement States provide information of, radioactive material licensed bv or '

level that will ensure that all events that to the NRC on incidents and events otherwise regulated by the Commissim should be considered for reporting to involving applicable nuclear materials Congress will be identified. At the same that have occurred in their States. Those (2) Major degradation of essential time, the thresholds are generally above events reported by Agreement States safety-related equipment; or the normallevel of reporting to NRC to that reach the thresliold for reporting as (3) Major deficiencies in design, exclude those events that involve some an AO are also published in the " Report constmetion, use of, or managemmt variance from regulatory limits, but are to Congress on Abnormal Occurrences." c ntrols for facilities or radioactive not significant from the standpoint of 2. Definition of terms. As used in this material licensed by or otherwise public health and safety, policy statement: regulated by the Commission.

Licensee Reports (a) An " abnormal occurrence" means Criteria by type of event used to .

an unsclIedul,1 incident or event at a detennine which incidents or events This general statement of policy will will be considered for reporting u Aos not change the reporting requirements facility or assodated with an activity j that is licensed or otherwise regulated, are set out in Appendix A of this policy imposed on NRC licensees by statement.

Commissiori regulations, license Pursuant to tbo Atomic Energy Act of conditions, or technical specifications 1954, as amended, or the Energy , 4. Comimssion dissemination of AO (TS). NRC licensees will continue to Reorganization Act of1974,as mformotJon.

submit required reports on a wide amended, that the Commission (a) The Commission will provide as spectrum of events, including events determines to be sigrdficant from the wide a dissemination ofinformation to such as instrument malfunctions and standpoint of public health and safety; the public as reasonably possible.

deviations from normal operating and Information on potential AOs (events procedures that are not significant from (b) An " unintended radiation that may meet the AO criteria) will be the standpoint of the public health and exposure" includes any occupational sent to the NRC Public Document Roorr safety, but do provide data useful to the exposure, exposure to the general and all local public document rooms as Commission in monitoring operating public, or exposure as a result of a soon as possible after the staff trends oflicensed facilities and in medical misadministration (as defined determines that the incident is a comparing the actual performance of in $ 35.2) involving the wrong potential AO. A Federal Register notice these facilities with the potential individual that exmeds the reporting will be issued on each AO report with performance for which the facilities values established in the regulations. copies distributed to the NRC Public were designed and/or licensed. All other reported medical Document Room and alllocal public Information pertaining to all events misadministration will be considered document rooms. When additional reported to the NRC will continue to be for reporting as an AO under the criteria information is anticipated, the notice made available and placed in the public for medical licensees. In addition, will state that the information can be document rooms for public perusal. In unintended radiation exposures include, obtained at the NRC Public Document addition, the NRC publishes annual any exposure to a nursing child, fetus, Room and in all local public documem rooms.

r_eprts on events (NUREG-1272 series), or embryo as a result of an exposure Information can also be obtamed by (other than an occupational exposure to (b) Each year, the Commission will

) i writing to the U.S. Nuclear Regulatory an undeclarea pregnant woman) to a submit a report to Congress listing for j Commission, Public Document Room, nursing mother or pregnant woman that period any AOs at or associated 2120 L Street, NW. (Lower level) above specified values. with any facility or activity which is Washington, DC 20555-0001. In 3. Abnonnoloccurrencegeneral limnaed or otherwise regulated addition, the Commission will continue stotement ofpolicy.The Commission pursuant to the Atomic Energy Act of to issue news announcements on events will apply the following policy in 1954, as amended, or the Energy

that seem to be newsworthy whether or determining whether an incident or Reorganization Act of 1974, as j l not they are reported as AOs. event at a facility or involving an mended.This report will contain the j l IL The Commission Policy-General activity that is licensed or otherwise ate, place, nature, and probable 1 Statement of Policy on implementation regulated by the Commission is an AO consequence of each AO, the muse o,r j of Section 20e of the Energy within the purview of Section 208 of the causes of eachd.0, and any action tami Reorganization Act of1974, as to prevent recurrence.

i i Amended ,jdgur dh,Qi e n,QQnd Appendix A-Abnonnal Occurrence

1. Applicability. Implementation of applicable to licensees and certincate holders. such Criteria Section 208 of the Energy ** 'h* B****** diffu*i n P ants l (CDPs). other criterie Criteria by types of events used to l Reorganization Act of 1974, as [ch$l3%*."l,,*fcYjdb" e' determine which incidents or events will t amended, AbnormalOccurrence si.o be applied to eveare si certified facilities such considered for reporting as / ^ ..

Reports, involves the conduct of as the CDPs. follows:

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rcues e asegmer i ' -

w ut. u 4. . ov. *u f . .v.*a - - > -> *uu-For All Limriaeen for special form (sealed /nondispersible) B Dnign or Saferv Analysis Debnency.

h. H$ nan Exposum to Rodiation From sources. or the smaller of the As or 0 01 times Personnel Error, or Procedurul or the A, values. as hsted in Tabla A-1. for Admsmstrotwe Inadequacy licensed terial ',

normal fonn (unsealed /dispersible) sources 1. Discovery of a maior condition not

1. Any unintended radiation exposure to or for sources for which the form is not an adult (any individual 18 years of age or specifically con <idered in the safety analysis known. Excluded from reporting under this report (SAR) or TS that requires immediate older) resulting in an annual total effective criterion are those events involving sources dc.se equivalent (TEDE) of 250 rnillisievert remedial action.

that are lost, stolen, or abandoned under the 2. Personnel error or procedural (mSv) (25 rem) or more; or an annual sum of following conditions: sources abandoned in deficiencies Sat result in loss of plant the deep dose equivalent (external dose) and accordance with the requirements of to CFR capability t ,,erform essential safety committed dose equivalent (intake of 39.77(c); sealed sources contained in labeled, bactions so that a release of radioactive radioactive material) to any individual organ rugged source housings; recovered sources materials, which could result in exceeding or tissue other than the lens of the eye. bone with sufficient indication that doses in the dose limits of to CFR Part 100 or 5 times marrow and the gonads, of 2500 mSv (250 excess of the reporting thresholds specified the dose limits of to UR Part 50. Appendix rem) or more: or an annual dose equivalent A. GDC 19, could occur from a postulated to the lens of the eye. of 1 Sv (100 rem) or n AO criteria I. A.1 and I.A.2 did not occur during the time the sourts was missing; and transient or accident kg loss of emergency more; or an annual surn of the deep dose core cooling system, loss of control rod unrecoverable sources lost under such equivalent and committed dose equivalent t systemb conditions that doses in excess of the

( rn) r an u si llow-dose rePortirig thmsholds specified in AO criteria III. For Fuel Cycle Facilitica equivalent to the skin or extremities of 2500 1.A.1 and I.A.2 were not known to have ccurnd. 1. A shutdown of the plant or portion of mSv (250 rem) or more. the plant resulting from a significan: event

2. Any unintended radiation exposure to 2. A substantiated case of actual or and/or violation of a law, regulation, or a eny minor (an individualless than is years 8tterDPted theft or diversion of licensed license / certificate condition.

of age) resulting in an annual TEDE of 50 matenal or sabotage of a facility. 2. A major condition or significant event mSv (5 rem) or more, or to en embryo / fetus 3. Any substantiated loss of special nuclear not considered in the license / certificate .nat resulting in a dose equivalent of 50 mSv (5 material or any substantiated inventory requires immediate remedial action.

rem) or more. discrepancy that is ludged to be significant 3. A maior condition or significant event

3. Any radiation exposure that has resulted relative to normallyexpected performance. that seriously compromises the ability of a in unintended permanent functional damage and that is judged to be caused by theft or safety system to perfonn its designated to an organ or a physiological system as diversion or by substantial bmakdown of the function that requires immediate remedial uetennined by a physician. accountability system. action to prevent a criticality, radiological or

4. Any substantial breakdown of physical chemical process har.ard.

B. Discharge or Dispersal of Radsooctive secunty or matenal control (i e., access Material From its intended Phce of control containment or accountability Confinement systems) that significantly weakened the A medical misadministration that.

1. The release of radioactive matenal to an protection against theft, diversion. or (al Results in a dose that is (1) equal to or unrestricted area in concentrations which,if sabotage. greater than 1 gray (Gy)(100 reds) to a maior averaged 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 p ni n of the bone manow. to the lens of the 5000 titnes the values specified in Table 2 of D. Other Events fi e . Those Concernmg eye. or to the gonads, or (2) equal to or greater Appendix B to 10 GR Part 20 unless the & sign. An ym. estrwnon. Testmg. than 10 Gy (1000 rads) to any other organ; licensee has demonstrated compliance with Operation. Use, or Disposal of Lacensed and 5 20.1301 using 56 20.1302 (b)(1) or 201302 F8#'hes r Regulated Maten Isl (b) Represents either (1) a dose or dosage (b) (2) (ii). 1. An accidental criticality (10 CFR thet is at least 50 percent greater than that

2. Radiation levels in excess of the design 70.52(a)). Prescnbed in a wntten directive or(2) a va ues for a package, or the loss of 2. A maior deficiency in design. prescribed dose or dosage that (i) is the confinement of radioactive material resulting construction, control. or operation beving wr ng radiopharmaceutical.' or (iil is

" in one or more of the following: (a) a significant safety implications mquiring delivered by the wrong route of radiation dose rate of to mSv {1 rem) per immediate remedial action. administration, or (iii) is dehvered to the hc 2r or more at i meter (3.28 feet. ' rom the 3 A serious deficiency in management or wr ng treatment site. r (iv) is dehvered by sccenible exte ,al surface of a package procedural controis in major areas. the wrong treatment mode, or (v) is from a containing radioactive material; (b) a 4. Senes of events (where individual

tdiation dose rate of 50 mSv (5 rem) per events am not of major importance). V. Guidelines for "Other Events ofInterest" hour or more on the accessible external recurring incidents, and incidents with surface of a package containing radioactive The Commission may determine that implications for similar facilities (generic events other than AOs may be of interest to matenal and that meet the requirements for incidents) that create a major safety concern. Congress and the public and be included in

^

cr1 o rad package in amounts greater than the ti e tn a II. For Commerdal Nuclear Power Plart Licen8*'8 f ^[{ G d rt as

,g regulatory limits in to UR 71.51(a)(21- be included in the AO report for this purpose A. Malfunction of Focdity. Structures, or are items that rnay possibly be perceived by C. Theft, Divenion. or ioss of Licensed Equipment the public to be of health or safety Morenal. or Sabotage or Security Breach 5 1. Exceeding a safety limit of license significance. Such items would not involve a

1. Any lost. stolen, or abandoned sources technical speciScation (TS) ($ 50,36(c)l. n P tim d {

that exceed 0.01 times the Ai values. as listed 2. Serious degradation of fuelintegnty' in to GR Part 71 Appendix A. Table A-1. primary coolant pressure boundary, or hf Wd W W ed u pnmary containment boundary. abnormal occurrences. An example is an

3. loss of pla .t capability to perform event where upon final evaluation by an NRC 8Information pertaining to certain incidents may be either classined or under consideration for essential safety functions so that a release of Incident Investigation Team, or an classi$ cation bacause of national security Agreement State equivalent response. a radioactive materials. which could result in implications. C.assiEed information will be exceeding the dose limits of 10 UR Part 100 determination is made that the event does

n. .. eld wuen form-!Iy reportmg these incidents in accordance with Section 20e of the Energy or 5 times the dose limits of to GR Part 50.

Appendix A. General Design Criterion (GDC)

• The wrog radiopharmaceutical as used in the Reorganization Act of 1974. as amended. Any Ao criterion 'or medical misadministration refers classitied details regarding these incidents would 19. could occur from a postulated transient to any radioptermaceutical otber than the one

_ be available to the Congress, upon request, under or accident (e g., loss of emergency core listed in the wr1Gn directive or in the clinical appropriate security arrangements. cooling system. loss of control rod system). procedures manual.

s. .s w 18&24 Federal Register ! Vol. 61 No. 74 / Thursday. April 17 1997 , Notices not meet the critena for an abnormal -

occurrence. at Unit 2. Further the staff finds the

! . above sufficient justification for the does not imohe a significant increase in e.

of Dated at April,1997. Rocir.alle. Marviand. this tith day licensee's exigent request p obabihty for the license or consequences of an accident previously evaluated.

For the Nuclear Regulatory Commisston- amendments.

2. The proposed change does not create th, Annette Vietti Cook. Before issuance of the proposed possibility of a new or different kind of license amendments, the Commission * "

Acting Secretatyofthe Commusion ,y l, r a y accident previously IFR Doc. 9N9912 Filed 4-W97; 8 45 aml will have made findings required by the Atomic Energy Act of 1954. as amended This proposal does not create tht saumo coot rses.at-e (the Act)and the Commission's probability of a new or difierent type of 1

regulations. accident from any accider.: previously evaluated. The proposed change only NUCLEAR REGULATORY Pursuant to 10 CFP. 30.91(a)(6) for reconciles the scope of response time resting t

COMMISSION amendments to be granted under described in the surveillance requirements exigent circumstances, the NRC staff with the elimination of selected response

[ Docket Nos. 50-387 and 50. 388] must determine that the amendment ume inung perfonned in accordance with request involves no significant hazards the NRC-approved methodology delineated Pennsylvania Power & Light Company; e nsideration. Under the Commission's ~ in the LTR.

Notice of Consideration of lasuance of regulations in to CFR 50.92, this Implementation means of the LTR methodology Amendments to Facility Operating that operation of the facility in for eliminating selected response tim: testmg License; Proposed No Significant accordance with the proposed also does not create the probability of a r.ew l

i Hazards Consideration Determination, amendment would not (1) involve or different type of accident from any a

and Opportunity for a Hearing accident previously evaluated. A review of significant increase in the probability or ', " d'

,';ndicaesj t

.. uc ear egu atory Commission (the Commission)is consequences of an accident previously M evaluated; or (2) create the possibility of the instruments and relays can be detected P "hw re considering issuance of an amendment a new or different kind of accident from other Technical Specification surveillance (

to Facility Operating License Nos. NPF- any accident previously evaluated; or A review of SSES response time testing 14 and NPP-22, issued to Pennsylvania (3) involve a signific.mt reduction in a history revealed one response time test Power & Light Company (PP&L)(the margin of safety. As required by to CFR failure. This failure would have been licensee) for operatioa of the 50.91(a), the licensee has provided its detectable by the logic system functional rest Susquehanna Steam Electric Station analysis of the issue of no significant for this channel. Redundancy and diversity haza'rds consideration, which is of the affected channels provide additional Units 1 and 2. located in Luzerne 85'"#'"Ch*'*ll*ff'Cdf""C'i "8 *ill Countv. Pennsylvania. presented below:

operate within the acceptance limits assumed The' proposed amendment would m the plant safety analyses.

1. The proposed change does not involve clarify the scope of the surveillance re9uirements for res a significant increase in the probability or PP&L's adherence to the conditions 'isted c nsequences f an accident previously in the NRC SER ISafety Evaluation Rep irtl ofinstrumentation m.Ponse time testing evaluated. for the LTR provides additional assurance the reactor protection system. Isolation actuation .

This proposal does not involve a that sluggish response ofinstruments and system, and emergency core cooling significant increase in the probabihty or relays will be detected by the other required system in the Technical Specifications consequences of an accident previoudv Technical Specification tests. A review of evaluated. The proposed chanas 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),

PP&L's request for a license reconciles descnbed the in the scope requirements surveillaue cf response time testing revealed that the five-second de with the elimination of selected response adversely affect the assumptions in the amendment for each unit under exigent time testing, performed in ac, rdance with respective analyses.

circumstances resulted from its recent the NRC-approved methodology delinestrd Therefom, the proposed change does not discover # that the wording of the TS in the BWROC ! Boiling Water Reactor create the possibility of a new or different surveillance was not reconciled with the Owners Group! Licensmg Topical Reportpreviously kind of accident from any accident evaluated.

tuitiative to eliminate selected response (LTR) NEDO-32291. ' System Analyses for time testing ficm the TSs. Accordingly. Elimination of Selected Response Time 3. The proposed change does not involve tha licensee determined that this Testing Requirements / dated January 1994, a significant reduction in the roargin of safety.

condition was a TS noncompliance and Implementation of the LTR (i.e.. elimination that prompt action to cormet this of response time testing for selected The change does not involve a significant reduction in the margin of safety. The situation vtas necessary because failure instrumentation in the Reactor Protection System. Isolation Actuation System and proposed change only reconciles the scope of to satisfy TS surveillance require;nents EmerBency Core Cooling System) does not response time testing described in the far response time requires that the surveillance requimments with the increase the probability or consequences of various instruments and systems be an accident r malfunc'i 8 I89ul Pment elimination of selected response time testing, performed in scoordance with the NRC-declared inoperrble, resulting in the TS f,Ppsnan to safety as previously evaluated in ap roved methodology delineated in the required entry into cold shutdown for Unit 1 (shutdown from 100% power All SSES component model numbers were i

and the prevention of fuel movemen) t analyzed for the failure mode of a sluggish implementation of the LTR methodology and the imposition of additional respons. As documented in the LTR. each for eliminating selected response time testing component's sluggish response can be also does not involve e significant reduction restrictions for Unit 2 currently in a in the margin of safety. The current response detected by other Technical Specification 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 assumed in the plant safety analyses.

licensee to rely uPoo the existin8 supports the contention that the use of such The analyses conservatively establish the response time testing for Unit 1 in lieu " qualitative" testing does not affect the margin of safety. As desenbod above, the of1: sting at power, and foremg an capability of the associated systems to elimination of selected response time testing unnecessary plant challenge by shutting perform their intended funct2on within their does not affect the capability of the required response time.

down this plant, and also in lieu of associated systems to perfonn their intended Based upon the analysis presented above, function within the allowed response time restricting refueling and other activities PP&L concludes that the proposed action und as the basis for the plaat safety analyses.

Plant and system respora to an initiating I