ML20149J913
| ML20149J913 | |
| Person / Time | |
|---|---|
| Issue date: | 07/24/1997 |
| From: | Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Bangart R NRC OFFICE OF STATE PROGRAMS (OSP) |
| Shared Package | |
| ML20149J917 | List: |
| References | |
| NUDOCS 9707290148 | |
| Download: ML20149J913 (79) | |
Text
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[ '*t UNITED STATES l
'y j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 300SMM1 vg l
P
%,..'...[t July 24, 1997 I
l
. MEMORANDUM TO: Richard L. Bangart, Director Office of State Programs $
1 N l FROM: Carl J. Paperiello, r Offie d @ ds ah add Safeguar
[@
m g7 co
SUBJECT:
REVISION TO MANAGEMENT DIRECTIVE 5.6, INTEGRATED MATERIALS PERFORMANCE EVALUATION CRITERIA The Office of Nuclear Material Safety and Safeguards (NMSS) has reviewed the proposed draft document, which would present a draft revision to Management Directive (MD) 5.6 to the regions and Agreement States for comment. NMSS concurs subject to the inclusion of the attached pen-and-ink comments. NMSS also understands that the document will be revised to include verbal agreements reached between Janet Lambert of NMSS, and Kathy Schneider of your staff, on the non. common indicator related to uranium recovery programs. l l
Although it was not included in the pa::kage sent for review, NMSS subsequently received an electronic mail comment, that the Office of State Programs would like NMSS to consider .
l consolidating the five existing common performance indicators into one indicator for radioactive materials, with sub-indicators as necessary. NMSS disagrees with this approach for two reasons:
l
- 1. The consolidation would appear to greatly diminish the significance of the materials licensing, materials inspection, and incident response programs. In almost all cases, I these are the most prominent IMPEP program activities in the regions and States. i I
- 2. The current set of common performance indicators was circulated to, and l commented upon, by the regions and Agreement States. These comments helped I reshape MD 5.6 into ite current structure and content. The Directive, in t!ut format, l was presented to the Commission in several papers and briefings. The process has been strongly endorsed by the Commission, the regions, and many Agreement States l as a significant improvement over earlier assessment processes.
NMSS appreciates the opportunity to conunent on the draft revision to MD 5.6.
l l
l
Attachment:
As stated CONTACT: George Deegan, NMSE/IMNS (301) 415-7834 f Y bQ[0}C]Q 5)
eor y % UNITED STATES
~
s# j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. -a -1
(
ALL AGREEMENT STATES OHIO, OKLAHOMA, PENNSYLVANIA TRANSMITTAL OF STATE AGREEMENTS PROGRAM INFORMATION (SP )
Your attention is invited to the enclosed correspondence which contains:
INCIDENT AND EVENT INFORMATION.........
PROGRAM MANAGEMENT INFORMATION...XX REVISION OF MANAGEMENT DIRECTIVE 5.6, "lNTEGRATED MATERIALS PERFORMANCE EVALUATION PROGRAM (IMPEP)"
FOR REVIEW AND COMMENT TRAINING COURSE INFORMATION............
TECHNICAL INFORMATION........................
OTHER..................................................... j V
Supplementary Information: Enclosed for your review and f omments is the revision of Management Directive 5.6, " Integrated Materials Perform ce Evaluation Program (IMPEP)"
(Enclosure 1).
This indicators common performance revisionforincludesthe Agreement descriptions and State and Regions. av The luation criteria draft f descriptions and evaluation criteria for the individual non-performance indicators forhol Cyclef""irProgram and the Site Decommissioning Management Plan were previously
'gM sent to the Regions .for comments by NMSS. The comments and responses can be found in Enclosure 2 and 3. The draft descriptions and evaluation criteria for the individual non-common performance indicators for Low-Level Radioactive Waste Disposal Program, Sealed Source and Device Evaluation Program and the Uranium Recovery Program were previously sent to the Agreement States for comments. The comments and responses can be found in Enclosure 4. As these draft criteria were developed, we have used them during the interim implementation of IMPEP. The evaluation criteria for the Policy Stttement on Adequacy and Compatibility have also been included in this revision. We request your comments by August 20,1997. We plan to finalize MD 5.6 and then implement this revision in future IMPEP reviews.
- .; .. l MEMORANDUM TO
- A. Rtndolph Blough, Director Division of Nuclear Materials Safety, RI 1
y
%fas tt.Co!!sss, Ati%
h.. O. it=, Director Division of Nuclear Materials Safety, Ril a
Arh M s/
Roy J. CanlanotDirec' tor
. Division of Nuclear Materials Safety, Rlli ,
i Ross A. Scarano, Director
- Division of Radiation Safety and Safeguards, RIV
! l 4 FROM: Paul H. Lohaus, Deputy Director i
- Office of State Programs ]
i .
SUBJECT:
REVISION OF MANAGEMENT DIRECTIVE 5.6, "lNTEGRATED
, MATERIALS PERFORMANCE EVALUATION PROGRAM
- (IMPEP)" FOR REVIEW AND COMMENT l
i l AttacSed for your review and comment is the revision of Management Directive 5.6, I
, " Integrated Materials Performance Evaluation Program IIMPEP)." This revision includes
! descriptions and evaluation criteria for the non-common performance indicators for the l Agreement States pagions. The draft descriptions,and eyaluation criteria for the individual nod $e7 ormance indicators for Fuel Cycle Facilities Program and the Site Decommissioning Management Plan were previously sent to the Regions by NMSS. The ;
- j. comments and responses can be found in Attachment 2 and 3. The draft descriptions and i evaluation criteria for the individual non-common performance indicators for Low Level '
- Radioactive Waste Disposal Program, Sealed Source and Device Evaluation Program and
! the Uranium Recovery Program were previously sent to the Agreement States for ;
comments.' The comments and response can be found in Attachment 4. As these draft i criteria were developed, we have used them during the interim implementation of IMPEP.
The evaluation criteria for the Policy Statement on Adequacy and Compatibility have also :
} been included in this revision. We request your comments by August 20,1997. We plan to finalize MD 5.6 and then implemerit this revision in future IMPEP reviews.
i j If you have any questions regarding this correspondence, please contact me at l 301-415-3340 or Kathleen Schneider at 301-415 2320.
l
! Attachments:
l As stated l-i 4
Distribution:
DlR RF SDroggitis PDR (YESf NO_)
IMPEP File DCD (SP03)
Management Directives File #
G-De- p DOCUMENT NAME: G:\KXS\REGMD56.KNS OFFICE OSP fg)[ OSP:DD l NMSS OSP:D l l l NAME KSchneider: rib PLohaus .'. CPaperiello RBangert DATE 07/1/97 07/ /97 07/ /97 07/ /97 ObP FILE CODE: SP-l-5. 5P-M 1
(.:
i PARTll Performance indicators General (A) l A description of the common and non-common performance indicators to be evaluated, as appropriate, for each region and each Agreement State is given in (B) i of this part. The evaluation criteria (i.e., performance standards) against which l l
these indicators are to be assessed are described in Part til of this handbook. These reviews ensure regional programs provide adequate public health and safety and determine program adequacy and compatibility in the Agreement States. The reviews are instrumental in improving State and NRC regional performance, thus !
ultimately leading to improved licensee performance. (1) l l The performance indicators should be used as a starting point of inquiry. This, in l
turn, should lead program evaluators to a,more careful examination of the underlying conditions, or " root causes" of potential problem areas. Evaluators may find correlations exist between two or more performance indicators, in this ;
situation, the impact of individual priormance symptoms could be compounded !
when combined with others. Conversely, a regulatory program measured as l potentially weak against one particular indicator could, nonetheless, be rated as ,
strong overall, if there are sufficient mitigating factors with respect to other j indicators. (2) -
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@UMI For Agreement States, the non-common indicators are legislation and program elements required for compatibility, sealed source and device evaluation program, low level radioactive waste disposal program and uranium recovery program. (4)
Common Performance Indicators (B)
Performance Indicator 1- Status of Materials inspection Program (1)
Periodic inspections of licensed operations are essential to ensure that activities are being conducted in compliance with regulatory requirements and consistent with good safety practices. The frequency of inspections is specified in NRC Inspection Manual Chapter 2800 and is dependent on the amount and kind of material, the
'. type of operation licensed, and the rssults of previous inspections. There must be a j capability for maintaining and retrieving statistical data on the status of the
- . inspection program. Information regarding the number of overdue inspections is a significant measure of the status of an Agreement State or NAC region's materials 1
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inspection progra.n; reviews should also examine specific cases in detail where the -
inspection frequency has been significantly exceeded (i.e., by more than 50 percent). The terms " materials inspection" and " overdue inspection" are defined in i the Glossary to this handbook.
Performance indicator 2- Technical Quality of inspections (2) i l
This performance indicator provides the qualitative balance to Performance indicator 1 above, which looks at the status of the inspection program on a quantitative basis. Review team members will accompany a sample of inspectors at different types of licensed facilities to evaluate tho knowledge and capabilities of regional and Agreement State inspectors. These accon:paniments will usually occur at a time i
l other than the onsite review of the region or Agreement State to afford t fpg" team sufficient time to observe inspectors st different types of licensee /. aest i reviews focu on the scope, completeness, and technical accuracy of completed
! inspections and related documentation. Review teams will conduct in-depth, onsite
! reviews of a cross section of completed inspection reports performed by different inspectors. In addition, review teams will verify that supervisors generally conduct J accompaniments of inspectors on an annual basis to provide management qua!ity assurance.
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l Performance Indicator 3- Technical Staffing and Training (3)
The ability to conduct effective licensing and inspection programs is largely dependent on having a sufficient number of experienced, knowledgeable, well- l trained technical personnel. Under certain conditions, staff turnover could have an l l
adverse effect on the implementation of these programs, and thus could affect l l
public health and safety. (a)
For this performance indicator, qualitative as well as quantitative measures must be l
considered in particular, the reason for apparent trends in staffing must be l l explormd. Is the rate of turnover and the degree of under staffing symptomatic of a chronic problem or is it merely a short term phenomenon? Why is turnover high?
What steps are being taken to address this? What impact is it having on other performance indicators? (b) i Review of staffing also requires a consideration and evaluation of the levels of training and qualification of the technical staff. Newly hired employees must be l technically qualified. Professional staff should normally have a bachelor's degree or l equivalent training in the physical and/or life sciences. Training requirements for NRC license reviewers and inspectors are specified in NRC inspection Manual, Chapter 1246. The requirements include a combination of classroom requirements and practical on-the-job training. Some NRC regions impose additional requirements on certain license reviewers or inspectors, depending upon their individual responsibilities, based on the types of licenses they review and/or inspect. (c)
! In addition, the qualification process for NRC materials program inspectors includes
! demonstration of knowledge of relevant sections of the Code of federal i
1 2
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l In accordance with Management Directive 5.9, " Adequacy and Compatibility of j Agreement State Programs," OSP Internal Procedures, D.7, " Reviewing State !
Regulations" and B.7 (Revision 1), " Compatibility Categories and Health and Safety identification for NRC Regulations and Other Program Elements," the State shall adopt legally binding requirements, such as regulations and other nscessary program elements consistent with the above guidance. (b)
NRC regulations that should be adopted by an Agreement State for purposes of compatibility or health and safety should be adopted in a time frame such that the effective date of the State requirement is not later than three years after the effective date of NRC's final rule. (c) h Performance indk nor 2 - Sealed Source and Device Evaluation Program (2)
Adequate technical es.aluations of sealed source and device (SS&D) d; signs e e
! essential to ensure that SS&Ds used by both licensees and persons exempt from licensing will maintain their integrity and that the design features are adequate to protect public health and safety. Three subelements will be evaluated to determine if the SS&D program is adequate. (a)
- 1. Technical Quality of the Product Evaluation Program -
The technical quality of the product evaluation program, based on an in-depth onsite review of a representative cross section of evaluations performed, i
includes various types of products and types of actions. Product evaluations l l should be technically accurate and ensure that proper prototype tests or l l analyses have been performed and passed for the normal, and likely accidental, l conditions of use, and that the safety features of the device are adequate to protect public heslth and safety. Completed registratioa certificates, and the status of obsolete registration certificates and registration certificates for j products having defects or involved in incidents, must be clearly and promptly ,
transmitted among various interested parties. Vendors' quality assurance and l control programs should be evaluated to ensure that products are built to the !
same specifications as those listed on the registration certificate. The l l commitments made in the registront's application and referenced in the !
registration certificate must be enforceable. To the extent possible, the onsite review should also capture a representative cross-section as completed by each ,
of the reviewers in the State.
- 2. Technical Staffing and Training l
Evaluation of SS&D review staffing and training should be conducted in the same manner as part of the common performance indicator, Technical Staffing and Training, paragraph (B)(2Hal & (b)Me</ t .wtM 4 (eens
- f e n 43 co notessante **tk W. conha of M SS tO resumuss.
l Review of staffing also requires a consideration and evaluation of the levels of i training and qualification of the technical staff. Newly hired employees need to '
{- be technically qualified. Professional staff should have a bachelor's degree or
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equivalent training in the physical and/or life sciences. Reviewers should be able to: (1) understand and interpret, if necessary, appropriate prototype tests which ensure the integrity of the products under normal, and likely accidental, conditions of use; (2) understand and interpret test results; (3) read and understand blueprints and drawings; (4) understand how the device works and how safety features operate; (5) understand and apply the appropriate regulations; (6) understand the conditions of use; (7) understand external dose rates, source activities and nuclide chemical form; and (8) understand and utilize basic knowledge of engineering materials and their properties.
- 3. Evaluation of Defects and incidents Regarding SS&Ds Reviews of SS&D incidents should be conducted in the same manner and as part of the common performance indicator, Response to incidents and Allegations, t., detect possible manufacturing defects and the root causes of l such incidents. The results should be evaluated to determine if other products may be affected by similar problems. ggrognede ac.feMs and no hMe*.J sk*A 1m s. plaes-.
Performance Indicator 3 - Low Level Radioactive Waste Disposal Program (3)
Fivs subelements will be evaluated to determine if the performance of the Agreement States' Low-Level Radioactive Waste Disposal Program is adequate. (a)
- 1. Status of Low Level Radioactive Waste Disposal inspection Periodic inspections of low level radioactive waste disposal facilities, from the l pre operational through the post-closure phase, are essential to ensure that activities are being conducted in compliance with regulatory requirements and consistent with good safety practices. Pre licensing inspections during siting and construction phases are essential to ensure the facility is being sited and
! constructed in accordance with regulatory and license requirements.
Operational phase inspections are essential for ensuring that disposal activities are being conducted in accordance with license conditions and regulatory requirements. Closure and post closure inspections are essential to ensure activities at closure are being conducted in compliance with the regulatory requirements and the facility is performing as expected. The frequency of -
inspections for operating low-level radioactive waste disposal facilities is specified in NRC Inspection Manual Chapter 2800 se yearly. Inspection frequencies for non-operational phase inspections should be established. There must be a capability for maintaining and retrieving statist l cal data on the status of the inspection program for the low-level radioactive waste disposal program.
- 2. Technical Quality of Inspections This subelement provides the qualitative balance to subelement 1 above, which
- looks at the status of the inspection program on a qua'ntitative basis. Inspector
- accompaniments, including onsite resident inspectors, by review team members will be used to evaluate the knowledge and capabilities of Agreement i
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- 5. Response to incidents and Allegations I Reviews of low level radioactive waste program incidents and allegations of g safety concerns should be conducted in the same manner and as part of the l
common performance indicator, Response to incidents and Allegations (unless the Low Level Radioactive Weste Program is organizationally separate from the materials program). ;
Performance indicator 4 - Uranium Recovery Program ywgj(4) y < eaaus.% "I l
Five subelements, as appropriate, will be eva!uated to determine if the performance 1 of the Region IV or an Agreement State's Uranium Recovery Program is adequate.
(a) l
- 1. Status of Uranium Recovery inspection Program '
Periodic inspections of licensed urani'u m recovery operations are essential to
- assure that activities are being conducted in compliance with regulatory i l
requirements and consistent with good safety practices. The frequency of l
( inspections is specified in the NRC Inspection Manual Chapter 2600 for insitu leach mining facilities, and in Chapter 2801 for conventional uranium and thorium mills. Uranium recovery facilities that are on standby or under ;
decommissioning also should be inspected at that frequency. Inspections should occur more frequently if significant regulatory concerns develop, before major changes are made to operations, or if generic problems are identified. j There must be a capability for maintaining and retrieving statistical data on the i status of the inspection program for the uranium and thorium program.
- 2. Technical Quality of Inspections l l
This subelement provides the qualitative balance to subelement 1 above, which ,
looks at the status of the inspection program on a quantitative basis, inspector i accompanimente by review team members will be used to evaluate the knowledge and capabilities of the Region and Agreement State inspectors at uranium recovery facilities. These accompaniments will usually occur at a time other than the onsite review of the Region or Agreement State. An acceptable program for conducting inspections for radioactive materiallicenses includes preparation and use of internal inspection guides and policy memoranda to ensure technical quality in the inspection program (when appropriate, NRC guidance may be used). Reviews of this subelement focus on the scope, completeness, and technical accuracy of completed inspections and related documentation. Review teams will conduct indepth, onsite reviews, of completed inspection reports. In addition, review teams will verify that
- supervisors generally conduct accompaniments of inspectors on an annual i- basis to provide management quality assurance.
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_ _ ~_ . _, _ __ _ _ . - _ _ -
l l 3. Technical Staffing and Training l
L Evaluation of staffing and training should be conducted in the same manner as l .
part of the common performance indicator, Technical Staffing and Training,
( paragraph (B)(2)(a) (b), (c) and (d) (unless the Uranium Recovery Program is l organizationally separate from the materials program). Professional staff should
[ normally have bachelor's degrees or equivalent training in the physical sciences, life or earth sciences, or engitteering. Staff and support contractors qualifications, training and experience should include the disciplines of health physics, civil or mechanical engineering, geology, hydrology and other earth
- sciences, and environmental science.
- 4. Technical Quality of Licensing Actions l An acceptable program for licensing uranium recovery activities ensures that essential elements of NRC licensing requirements for radiation protection, qualifications of personnel, facilities and equipment, operating and emergency '
i -
procedures, financial qualification and assurance, closure and decommissioning procedures, and institutional arrangements are met in a manner sufficient to i establish a basis for licensing action. This may be accomplished through the l preparation and use of internal licensing guides and policy memoranda to assure technical quality in the licensing program (when appropriate, NRC Uranium Recovery Program Policy and Guidance System Guides may be used).
Prelicensing inspection of complex facilities are conducted, when appropriate.
To evaluate the technical quality of the Agreement State licensing program, an l l indepth review of an aspect of the uranium recovery license (such as radiation protection, hydrology, or geotechnical engineering) will be. conducted.
l Technical quality includes r:ot only the review of completed actions, but also an l examination of any ongoing requests and license renewals that may have
! health and safety implications. Technical quality includes review of the States ,
compliance with the statutory requirements or prohioitions in Section 274 of the Atomic Energy Act, as amended.
- 5. Response to incidents and Allegations Reviews of uranium recovery program incidents and allegations of safety concerns should be conducted in the same manner and as part of the common performance indicator, Response to incidents and Allegations (unless the Uranium Recovery Program is organizationally separate from the materials program).
Performance Indicator /- Regional Fuel Cycle inspection Program (6)
Five subelements, as appropriate, will be evaluated to determine if the performance i of the Regional Fuel Cycle inspection Program is adequate. (a)
- 1. Status of Fuel Cycle Inspection Program l
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The small number of fuel cycle facility inspectors who may need training at any' one particular time pose unique challenges to arranging for the proper training of these individuals on a cost-effective basis. The region may have to seek outside training opportunities to provide inspectors with specific safety
. knowledge needed for unique aspects of their facilities (e.g., heavy duty overhead cranes)
. After an inspector is trained and initially qualified to perfom1 inspections in a
! specific technical area, providing additional cross-training opportunities for l inspectors willincrease the ability of the inspection organization to better
! respond to facility incidents, unexpected staff turnover, or other unusual i situations. '
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- 4. Response to Incidents and Allegations l
l The quality, thoroughness, and timeliness of a regulator's response to incidents and allegations can have a direct bearing on public health and safety.
l l- Significant indicators of the overall quality of the fuel cycle facility inspection
! program willinclude detailed written procedures for incident response, and the l maintenance of records and reports of actualincidents, focusing on internal and external coordination, and analytical, investigative, and follow up procedures.
l The Region should exhibit a readiness to respond, in conjunction with Headquarters, to major incidents that may arise at a facility. This willinclude a review of preparations in place at the Region's incident Response Center (e.g.,
identification of individuals with required skills, facility data for use during emergencies, detailed preparations for responding to the highest risk types of incidents postulated for the facility, based upon known facility processes and source terms, etc.).
1 The region, possibly in coordination with Headquarters, should conduct, or participate in, documented follow up self assessments of drills and responses to any major incidents that involved activation of the region's incident
, Response Center.
The region's responses to any allegations involving fuel cycle facilities should i
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be grounded in established inspection procedures and good technical and i regulatory analysis to determine if regulations were followed or may be i deficient and in need of revision with regard to a significant safety issue brought to light by the allegation.
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$ Performente inosc* tor 6 - Site Decommissioning Management Plan (SDMP) (6)
Six subelements, as appropriate, will be evaluated to determine if the performance of the Regional Site Decommissioning Mahagement Plan (SDMP) is adequate. (a) i l
- 1. Quality of SDMP Decommissioning Reviews l
l Planned, significant decommissioning actioris at facilities that are listed on the !
j SDMP are reviewed and approved by the NRC staff in advance of i decommissioning. Decommissioning plan reviews are conducted in accordance i with inspection Manual Chapter 2605, current NRC policies, standard review
] procedures, and other regulatory guidance. Reviews are documented as i outlined in IMC 2605 using, as appropriate, Environmental Assessments,
{ Environmental Impact Statements, Safety Evaluation Reports, checklists, interrogatories, and other written correspondence.
- 2. Financial Assurance for Decommissioning l
} Adequate financial assurance for the decommissioning of SDMP sites has been
! established in accordance with regulatory requirements and spplicable 4- guidance. Financial assurance is provided for estimated costs for an independent, third party to perform decommissioning with the objective of i releasing the site for unrestricted use, unless alternative arrangements have l been approved by the regulator. Financial assurance mechanisms are reviewed and maintained to ensure that they would be executable and provide sufficient funding for decommissioning in the event that the licensee liquidates or is otherwise unable to pay for decommissioning.
- 3. Termination Radiological Surveys Sufficient radiological surveys are required prior to license termination and site release, as outlined in IMC 2605, to ensure that residual radioactivity levels comply with release criteria. Licensee survey results are validated through a closeout inspection or confirmatory survey, as outlined in IMC 2605, given the 13
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l e License reviewers and inspectors are trained and qualified in a reasonable time period.' (e) e Management commitment to training is clearly evident. (f)
Satisfactory with Recommendations for improvement (2)
Review determines the presence of some of the following conditions:
j e Some staff turnover that could adversely upset the balance in staffing the I l
licensing and inspection programs. (a) e Some vacant positions not readily filled. (b) ,
I l e Some evidence of Jack of management attention or actions to deal with staffing problems. (c) e , Some of the licensing and inspection personnel not making prompt progress in completing a!1 of the training and qualification requireme.nts. (d) on ye e se. eeat.
e The training and qualification standards include areas needing impeeved. (e) e Some of the new staff is hired with little education or experience in physical j and/or life sciences, or materials licensing and inspection. (f)
Unsatisfactory (3)
Review determines the presence of chronic or acute problems related to some of the following conditions, which cause concerns about their likely impacts on other performance indicators:
e Significant staff turnover relative to the size of the program. (a) i e Most vacant positions not filled for extended periods. (b) e Little evidence of management attention or actions to deal with staffing problems. (c) l e Most of the licensing and inspecticn personnel not making prompt progress in j completing all of the training and qualification requirements. (d)
For the regions, this means there has been, and continues to be, a clear effort to adhere to the requirements and conditions specified in NRC Inspection Manual, Chapter 1246, and the applicable qualifications journals, or to receive equivalent training elsewhere. For the Agreement States, equivalent requirements should be in 4
place and followed.
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4 greater than three years after the effective date of NRC's final rule. (b)
Unsatisfactory (3) e State no longer has statues that authorize the State to establish a program for the regulation of agreement material and provide authority for the assumption of regulatory responsibility under the Agreement. (a) l e The State is not authorized through its legal authority to license, inspect, and enforce legally binding requirements such as regulations and licenses. (c) e State statues are in conflict with, or do not sufficiently reflect scope of Federal t
statutes. (d) l 1
l e The State does n st have existing legally enforceable measures sei an, !
generally applicable rules, license provisions, or other appropriate measures, j necessary to allow the State to ensure adecuate protection of public health and i safety in the regulation of agreement' material. (e) l e The State has not adopted significant legal binding requirements or regulations !
! in accordance with Management Directive 5 g, " Adequacy and Compatibility of i l Agreement State Programs," OSP Internal Procedures,0.7,
- Reviewing State j Regulations" and B.7 (Revision 1), " Compatibility Categories and Health and Safety identification for NRC Regulations and Other Program Elements." (f) e Most NHC regulations that should be adopted by an Agreement State are !
consister'tly adopted in a time frame such that the effective date of the State !
requirement is significantly greater (many months or years) than three years j after the effective date of NRC's final rule. (g) j Category N (4)
Not applicable.
Non-common Performance Indicator 2 Sealew Source'and Device Evaluation Program (G)
- 1. Technical Quality of the Product Evaluation Program I Satisfactory (1)
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l e Review of(sempleted SS&D e.evaluations -_
e y r r r-::t'.. ::=;!: c'fLatwa get rt rr '!':: indicates that product evaluations are thorough, complete, consistent, of acceptable technical quality, and adequately address the integrity i of the products. (a) e Health and safety issues are properly addressed. . (b) e Registrations include complete summaries of the product evaluations and l
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I ._ .
(c) ,
e All registrations clearly summarize the product evaluation and provide license ,;
reviewers with adequate information to license possession and use of the ,
product. (d) .
an well s.wllte.n V e Defic' ncy letters c'er 'y rtric re;* tea / perY? r and are used at the proper tim e)
/
l ^Asende eA n ......~.
t' On d*$
af: of**JU e .
t::".!p:! ;x:::y the application and proposed certificate of registration is performed by a second individual which supports the finding l
that the product i acceptable for licensing purposes. (It is important to keep in mind that the reviewer must concur with the initial review.) (f) puf
- r * *nt tudmmil e Applicable guidance documents are followed, unless approval to use alternate procedures is obtained from management. (g) e Completed registration certificates, and the status of obsolete registration certificates, are clear and are promptly transmitted to interested parties. (h) e Reviewers ' ensure that registrants have deyeloped and implemented adequate quality assurance and control programs. (k) l e There is a means for enforcing commitments made by registrants in their applications and referenced in the registration certificates by the program. No l
potentially significant health and safety issues can be linked to a specific product evaluation that was improperly conducted. (1) l Satisfactory with Recommendations for improvement (2)
! e Review indicates that some SS&D evaluations do not fully address important health and safety concerns or indicates repeated examples of problems with respect to thoroughness, completeness, consistency, clarity, technical quality, adherence to existing guidance in product evaluations, and addressing the integrity of the products. (a) e Not all registrations clearly summarize the product evaluation and not all provide license reviewers with adequate information to license possession and
, use of the product. (b) e Reviewers do not follow all appropriate guidance documents. (c)
Info.fM Awdit rwasash of the reviewer's evaluation is not always performed by either
/
e management or staff having properpualifications and training. (d)
SStR
.e Completed registration certificates, and the status of obsolete registration certificates, are not always clear or are not always promptly transmitted to 9
m
e i;
4 interested parties. (e) 1 e Not all product evaluations include an evaluation of proposed quality assurance j l and control programs. (h) 4 e Commitments made by registrants in their applications, and referenced in the registration certificates, cannot be enforced for all registrations. (i)
Unsatisfactory (3)
- Review indicates that SS&D evaluations frequently fail to address important health and safety concerns or indicates chronic problema with respect to thoroughness, completeness, consistency, clarity, technical quality, adherence l
.to existing guidance in product evaluations, and adequately addressing the ;
l !
- integrity of the products. (a) j e Registrations often do not clearly summarize the product evaluation and do not 4
' provide license reviewers with adequate information to license possession and use of the product. (b) oAL ,
e Reviewers 4o not follow appropriate guidance documents. (c) l 1
e Completed registration certificates, and the status of obsolete registration 1 certificates, are unclear and are not promptly transmitted to interested parties.
(d) e Product evaluations often do not include an evaluation of proposed quality assurance and control programs. (e) e Commitments made by registrants in their applications, and referenced in the registration certificates, often cannot be enforced. (f) e The review has identified potentially significant health and safety issues linked to a specific product evaluation. (g)
Category N (4)
Not applicable.
- 2. Technical Staffing and Training Satisfactory (1)
The technical review and audit are performed by staff having proper training and qualifications.
Satisfactory with Recommendations for improvement (2) 10 t ',
en
4 1
Some reviewers do not have the proper qualifications and training. '
Unsatisfactory (3)
Technical review of the reviewer's evaluation is either not performed or not performed by management or staff having proper qualifications and training.
Category N (4)
Not applicable. .
1 1
- 3. Evaluation of Defects and incidents Regarding SS&Ds I i
i Satisfactory (1) i 4
The SS&D evaluation program routinely evaluates the root causes of defects and Incidents involving SS&D evaluations and takes appropriate actions, including madMdah notification of gg" partiesM eks replalo<yag.g, U(([3M Satisfactory with Recommendations for Improvement (2) l The SS&D evaluation program does not fully evaluate the root causes of all defects and incidents involving SS&D evaluations, or when performed, the programs do not always take appropriate actions, including notification of interested parties.
Unsatisfactory (3)
The SS&D evaluation program does not ensure evaluation of the root causes of defects and incidents involving SS&D evaluations, or if performed, does not ensure appropriate actions are taken, including notification of interested parties.
Category N (4)
Not applicable.
Non-common Performance Indicator 3- Low Level Weste Radioactive Waste Disposal Program (H)
- 1. Status of Low Level Radioactive Waste Disposal'aspection Satisfactory (1)
- Low level waste disposal licensees are inspected at regular intervals in accordance with frequencies prescribed in NRC IMC 2800. (a)
- Deviations from these schedules are normally coordinated between working staff and management. (b) 11 9
+
L . arrangements have been not always been approved by the regulator. (b) e Financial assurance mechanisms are not being consistently reviewed and maintained to ensure that they would be executable and provide sufficient l
funding for decommissioning in the event that the licensee liquidates or is i otherwise unable to pay for decommissioning. (c) i Category N (4) .
l Special conditions exist that provide justification for withholding a rating for one or i more Evaluation Criteria.
- 3. Termination Radiological Surveyt Satisfactory (1) l @For nearly.all SDMP sites, sufficient radio!ogical surv ys are being performed prior g l to license termination and site release, as outlined in g 2605, to ensure that residual radioactivity levels comply with release critennicensee survey results are 1 l routinely validated through a clossout inspection or coI1firmatory survey, as outlined bab in IMC 2605, given the extent and significance of any residual contamination. (b)
Satisfactory with Recommendations for improvement (2) e For most SDMP, sites sufficient radiological surveys are being performed prior to license termination and site release, as outlined in IMC 2605, to ensure that residual radioactivity levels comply with release criteria. (a) l e Licensee survey results are usually validated through a closeout inspection or confirmatory survey, as outlined in IMC 2605, given the extent and significance of any residual contamination. (b)
Unsatisfactory (3)
Sufficient radiological surveys are not vonsistently being performed prior to license termination and site release, as outlined in IMC 2605, to ensure that residual l radioactivity levels comply with release criterMr survey results are not normally V
l validated through a closeout inspection or coTIfirmatory survey, as outlined in IMC i 2605, given the extent and significance of any residual contamination.
Category N (4)
Special conditions exist that provide justification for withholding a rating for one or more Evaluation Criteria.
! 4. Inspections l
! Satisfactory (1) 32 r
9
.4 i
i l
i ATTACHMENT 1 REVISION 'OF MANAGEMENT DIRECTIVE 5.6 INTEGRATED MATERIALS PERFORMANCE EVALUATION PROGRAMS (IMPEP) 4 6
W .
~
1 U.S. NUCLEAR REGULATORY COMMISSION l
[ Volume 5: Governmental Relations and Public Affairs (NMSS/OSP) i i
INTEGRATED ."ATERIALS PERFORMANCE EVALUATION PROGRAM (IMPEP)
DIRECTIVE 5.6 l
Pokcy (5.6-01) i it is the policy of the U.S. Nuclear Regulatory Commission to evaluate the Regional materials programs and Agreement State radiation control programs in an integrated manner using common and non-common performance indicators, to ensure that public health and safety is being adequately protected.
Objectives (6.6-02) e To establish the process by which the Office of Nuclear Material Safety and Safeguards and the Office of State Programs conduct their periodic assessments to determine the adequacy of their programs in the NRC Regions and Agreement States. (021) e To provide NRC and Agreement State management with a systematic and integrated approach to evaluate the strengths and weaknesses of their nuclear materiallicensing and inspection programs. (022) e To provide significant input to the management of the regulatory decision-making process, and indicate creas in which NRC and the Agreement States should dedicate more resources or management attention. (023)
Organizational I esponsibilities and Delegations of Authority (5.6-03)
Deputy Executive Director for Regulatory Programs (DEDR)
(031) e Oversees the integrated materials performance evaluation program (IMPEP). (a) e Chairs management review boards. (b) e Signs final reports issued to each Region and Agreement State. (c) l l
! 1 .
t
Director, Office of Nuclear Material Safety and Safeguards (NMSS) and Director, Office of State Programs (OSP)
(032) e implement the IMPEP within NMSS and OSP. Provide staffing support and training for review teams. (a)
~
e Establish a' schedule and develop a detailed review regimen for conducting the reviews in each Region and Agreement State. (b) e Monitor the IMPEP process; evaluate and develop IMPEP policy, criteria, and methodology, and assess the uniformity and adequacy of the implementation of the program. (c) e issue draft reports and prepare final reports for each Region and State for consideration by management review board and signature by the DEDR. (d) e Participate on management review boards. (e) e Coordinate with Agreement States to staff IMPEP reviews and the management review board with appropriate Agreement State representatives. (f)
General Counsel (033)
Participates on management review boards.
Director, Office for Analysis and Evaluation of Operational Data (AEOD)
(034)
Participates on management review boards.
Regional Administrators (035)
Impleme'nt the IMPEP within their respective Regions. Provide staffing support for review teams, as needed.
Applicability (5.6-04)
The policy and guidance in this directive and handbook apply to all NRC employees who are responsible for and participate in the IMPEP.
2
1 Handbook j (5.6-05)
Handbook 5.0 describes the performance indicators that will be used, the '
performance standards against which these indicators will be evaluated, and the frequency arid process sequence to be employed. The " Glossary" in the handbook also defines some of the key terminology.
References. l (5.S-06) l Code of FederalRegulations,10 CFR
- NRC Inspection Manual, Chapter 0610, " Inspection Reports." l
- j. ' NRC Inspection Manual, Chapter 1246, " Formal Qualification Program in the Nuclear Material and Safeguard Program Area."
1 NRC Inspection Manual, Chapter 2600, " Fuel Cycle Facility Operational Safety and i Safeguards inspection Program."
NRC Inspection Manual, Chapter 2604, " Licensee Performance Review."
NRC Inspection Manual, Chapter 2605, " Decommissioning Procedures For Fuel Cycle and Materials Licensees."
NRC Inspection Manual, Chapter 2800, " Materials inspection Program."
NRC Inspection Manual, Chapter 2801, "11e.(2) Byproduct klaterial Disposal Site and Facility inspection Program."
NRC Inspection Manual, inspection Procedure 87104, " Decommissioning Inspection Procedure For Materials Licensees."
NRC Inspection Manual, inspection Procedure 88104, " Decommissioning Inspectio'n Procedure For Fuel Cycle Facilities."
NRC Management Directive 5.9, " Adequacy and Compatibility of Agreement State Programs."
" Final Po!!cy Statement on Adequacy and Compatibility of Agreement State Programs," dated [ insert effective date).
" Final ' Statement of Principle and Policy for the Agreement State Program
- and
' Procedures for Suspension and Termination of an Agreement State Program,'"
dated [ insert effective date).
'3
4
. a INTEGRATED MATERIALS PERFORMANCE EVALUATION PROGRAM (fMPEP)
HANDBOOK 5.6
PARTI Evaluation Evaluation Frequency (A)
NRC will review the performance of each Region and each Agreement State on a periodic basis. The schedule for conducting each Regional or Agreement State visit will be developed by the Office of Nuclear Material Safety and Safeguards (NMSS) and the Office of State Programs (OSP) in coordination with the Regions and States.
Approximately 10 to 12 reviews will be scheduled in most years. Under normal conditions, this would allow evaluations of NRC Regions every 2 years, and Agreement States every 4 years. However, these frequencies can be adjusted downward, on the basis of the findings from the last review, or in light of significant program changes in a particular State or Region. In addition, this schedule provides for review of certain NMSS Headquarters functions on an as-needed basis.
l Evaluation Process Sequence (B)
The typical evaluation process sequence for the IMPEP reviews is summarized below:
1
- Develop review schedule for the year. (1) l e Assemble and train team members. (2) I e Designate team leader and members for each scheduled review. (3) I e Transmit questionnaires to affected Regions and States. (4)
- Provide copy of questionnaire responses and most current information on the Region or Agreement State to team members. (5) l
- Assess a sample of inspections at different types of licensed facilities by accompanying inspectors. (6)
- Conduct onsite portion of IMPEP, using the criteria specified in this handbook I and any performance review procedures. (7)
- Prepare draft IMPEP report, with recommendation for overal! performance evaluation, for office director's signature. (8) e issue the draft report to Region or State. (9)
- Review and consider written comments received from the Regions or Agreement States. (10)
- Prepare proposed final report for consideration by the management review board (MRB). (11)
- Conduct MRB meeting. (12) e issue final reports, include the written comments received from the Region or Agreement State and any changes to the report based on consideration of the written responses, and a summary of MRB findings. (13) 1
PART11 Performance Indicators General (A) 4 A description of the common and non-common performance indicators to be '
evaluated, as appropriate, for each Region and each Agreement State is given in (B) of this part. The evaluation criteria (i.e., performance standards) against which these indicators are to be assessed are described in Part ll1 of this handbook. These reviews ensure Regional programs provide adequate public health and safety and determine program adequacy and compatibility in the Agreement States. The reviews are instrumental in improving State and NRC Regional performance, thus I ultimately leading to improved licensee performance. (1)
The performance indicators should be used as a starting point of inquiry. This, in turn, should lead program evaluators to a more careful examination of the underlying conditions, or " root causes" of potential problem areas. Evaluators may ;
find correlations exist between two or more performance indicators, in this !
situation, the irnpact of individual performance symptoms could be compounded I when combined with others. Conversely, a regulatory program measured as ,
potentially. weak against one particular indicator could, nonetheless, be rated as I strong overall, if there are sufficient mitigating factors with respect to other !
indicators. (2) !
Certain non-reactor functions that continue to be conducted from NRC Headquarters, such as fuel cycle licensing, uranium and thorium milling licensing, I sealed source and device reviews, and low-level radioactive waste disposal
~
licensing, are excluded from the set of common indicators because they are not l common to Regional and Agreement State activities. These are incorporated, as ;
appropriate, as non common indicators contributing to a performance-based l evaluation of a program. (3)
For Agreement States, the non-common indicators are legislation and program i elements required for compatibility, sealed source and device evaluation program, low-level radioactive waste disposal program and uranium recovery program. (4)
Common Performance Indicators (B)
Performance Indicator 1 - Status of Materials inspection Program (1)
Periodic inspections of licensed operations are essential to ensure that activities are being conducted in compliance with regulatory requirements and consistent with good safety practices. The frequency of inspections is specified in NRC Inspection Manual, Chapter 2800, and is dependent on the amount and kind of material, the type of operation licensed, and the results of previous inspections. There must be a capability for maintaining and retrieving statistical data on the status of the inspection program. Information regarding the number of overdue inspections is a 1
. - . ~ -- - - -- -. . _- .. .. . . - . - --- __ - .
significant measure of the status of an Agreement State's or NRC Region's i materials inspection program; reviews should also examine specific cases in detail where the inspection frequency has been significantly exceeded (i.e., by more than 50 percent). The terms " materials inspection" and " overdue inspection" are defined
+
in the Glossary to this handbook.
- Performance Indicator 2 - Technical Quality of Inspections (2)
This performance indicator provides the qualitative balance to Performance Indicator l 1 above, which looks at the status of the inspection program on a quantitative basis. Review team members will accompany a sample of inspectors at different types of licensed facilities to evaluate the knowledge and capabilities of Regional
$- and Agreement State inspectors. These accompaniments will usually occur at a time other than the onsito review of the Region or Agreement State to afford the review team sufficient time to observe inspectors at different types of licensee facilities. There reviews focus on the scope, completeness, and technical accuracy I
of completed inspections and related documentation. Review teams will conduct indepth, onsite reviews of a cross-section of completed inspection reports >
4 performed by different inspectors In addition, review teams will verify that supervisors generally conduct accompaniments of inspectors on an annual basis to provide management quality assurance.
Performance Indicator 3 - Technical Staffing and Training (3)
The ability to conduct effective licensing and inspection programs is largely dependent on having a sufficient number of experienced, knowledgeable, well-trained technical personnel. Under certain conditions, staff turnover could have an l adverse effect on the implementation of these programs, and thus could affect public health and safety. (a)
]
For this performance indicator, qualitative as well as quantitative measures must be considered, in particular, the reason for apparent trends in staffing must be ;
explored. Is the rate of turnover and the degree of under-staffing symptomatic of a chronic problem or is it merely a short-term phenomenon? Why is turnover high?
What steps are being taken to address this? What impact is it having on other performance indicators? (b)
Review of staffing also requires a consideration and evaluation of the levels of training and qualification of the technical staff. Newly hired employees must be technically qualified. Professional staff should normally have a bachelor's degree or equivalent training in the physical and/or life sciences. Training requirements for NRC license reviewers and inspectors are specified in NRC inspection Manual, I Chapter 1246. The requirements include a combination of classroom requirements I and practical on the-job training. Some NRC Regions impose additional requirements on certain license reviewers or inspectors, depending upon their individual responsibilities, based on the types of licenses they review and/or inspect.
(c) 2
i=
e in addition, the qualification process for NRC materials program inspectors includes demonstration of knowledge of relevant sections of the Code of Federa/
Regulations, completion of a qualifications journal, and appearance before a qualifications board. Although Agreement States need not follow NRC Inspection Manual, Chapter 1246, they should have an equivalent program for training and qualification of personnel, and it should be present and adhered to in Agreement State prograrns. ,The evaluation standard measures the overall quality of training )
available to, and taken by, materials program personnel. The staff should be afforded opportunities for training that are consistent with the needs of the program, such as attendance at counterpart meetings, university programs and national conventions. (d) l l
Performance Indicator 4 - Technical Quality of Licensing Actions (4) '
An acceptable program for licensing radioactive materialincludes: preparation and use of internal licensing guides and policy memoranda to ensure technical quality in the licensing program (when appropriate, NRC Guides may be used); prelicensing inspection of complex facilities; and supervisory review, when appropriate. (a)
This performance indicator evaluates the technical quality of the licensing program, based on an indepth onsite review of a representative cross-section of licensing actions, and various types of licenses. Technical quality includes not only the review of the application and completed actmns, but also an examination of any .
renewals that have been pending for more than a year because the failure to act on such requests may have health and safety implications. To the extent possible, the onsite review should also capture a representative cross-section as completed by each of the reviewers in the Region or State. (b)
Performance Indicator 5 - Response to Incidents and Allegations (5)
The quality, thoroughness, and timeliness of a regulator's response to incidents and allegations of safety concerns can have a direct bearing on public health and safety. i A careful assessment of incident response and allegation investigation procedures, ;
actual implementation of these procedures, internal and external coordination, and investigative and follow-up procedures will be a significant indicator of the overall ciuality o] the program.
Non-common Performance Indicators (C)
Performance indicator 1 - Legislation and Program Elements Required for Compatibility (1)
State statutes should authorize the State to establish a program for the regulation of agreement material and provide authority for the assumption of regulatory responsibility under the Agreement. The statutes must authorize the State to promulgate regulatory requirements necessary to provide reasonable assurance of protection of public health and safety. The State must be authorized through its legal authority to license, inspect, and enforce legally binding requirements such as 3
. ._ . - - - - -. . ~ _ . . - .- - .- .
4 regulations and licenses. State statutes should be consistent with Federal statutes, as appropriate. (a) in accordance with Management Directive 5.9, " Adequacy and Compatibility of Agreement State Programs," OSP Internal Procedures, D.7, " Reviewing State Regulations" and B 7 (Revision 1), " Compatibility Categories and Health and Safety Identification f,or NRC Regulations and Other Program Elements," the State shall adopt legally binding requirements, such as regulations and other necessary 4 program elements consistent with the above guidance. (b)-
NRC regulations that should be adopted by an Agreement State for purposes of compatibility or health and safety should be adopted in a time frame such that the effective date of the State requirement is not later than three years after the i
effective date of NRC's final rule. (c)
Other program elements that have been designated as necessary for maintenance of an adequate and compatible program should be adopted and implemented by an Agreement State within 6 months of such designation by NRC (d)
Perforrnance Indicator 2 - Sealed Source and Device Evaluation Program' (2) l Adequate technical evaluations of sealed source and device (SS&D) designs are essential to ensure that SS&Ds used by both licensees and persons exempt from licensing will maintain their integrity and that the design features are adequate to protect public health and safety. Three subelements will be evaluated to determine if the SS&D program is adequate.
'l
- 1. Technical Quality of the Product Evaluation Program (a)
The technical quality of the product evaluation program, based on an indepth <
onsite review of a representative cross-section of evaluations performed, includes various types of products and types of actions. Product evaluations I should be technically accurate and ensure that proper prototype tests or analyses have been performed and passed for the normal, and likely accidental, conditions of use, and that the safety features of the device are adequate to
~ l protect public health and safety. Completed registration certificates, and the !
status of obsolete registration certificates and registration certificates for l products having defects or involved in incidents, must be clearly and promptly transmitted among various interested parties. Vendors' quality assurance and control programs should be evaluated to ensure that products are built to the i same specifications as those listed on the registration certificate. The l commitments made in the registrant's application and referenced in the l registration certificate must be enforceable. To the extent possible, the onsite 1 Agreement States with authority for Sealed Source and Device Evaluation Programs will need to have a program in place, regardless of whether or not the Agmement is performing SS&D reviews.
4 l
l review should also capture a sepresentative cross-section as completed by each of the reviewers in the State.
- 2. Technical Staffing and Training (b)
Evaluation of SS&D review staffing and training should be conducted in the same manner and as part of the common performance indicator, Technical Staffing and Training, paragraph (B)(3)(a) & (b), except with a focus on training commensurate with the conduct of the SS&D reviews. (i) i 4
Review of staffing also requires a consideration and evaluation of the levels of training and qualification of the technical staff. Newly hired employees need to be technically qualified. Professional staff should have a bachelor's degree or equivalent training in the physical and/or life sciences. Reviewers should be able to: (1) understand and interpret, if necessary, appropriate prototype tests which ensure the integrity of the products under normal, and likely accidental, l conditions of use; (2) understand and interpret test results; (3) read and understand blueprints and drawings; (4) understand how the device works and how safety features operate; (5) understand and appiy the appropriate regulations; (6) understand the conditions of use; (7) understand external dose rates, source activities and nuclide chemical form; and (8) understand and utilize basic knowledge of engineering materials and their properties. (ii)
- 3. Evaluation of Defects and incidents Regarding SS&Ds (c)
Reviews of SS&D incidents should be conducted in the same manner and as part of the common performance indicator, Response to incidents and ;
Allegations, to detect possible manufacturing defects and the root causes of such incidents. The iesults should be evaluated to dete'rmine if other products may be affected by similar problems. Appropriate action and notifications should take place.
Performance Indicator 3 - Low-Level Radioactive Waste Disposal Program (3)
Five subelements will be evaluated to determine if the performance of the Agreement States' Low-Level Radioactive Waste Disposal Program is adequate.
- 1. Status of Low-Level Radioactive Waste Disposal inspection (a)
Periodic inspections of low-level radioactive waste disposal facilities, from the pre-operational through the post-closure phase, are essential to ensure that activities are being conducted in compliance with regulatory requirements and consistent with good safety practices. Inspections during siting and construction phases are essential to ensure the facility is being sited and constructed in accordance with regulatory and license requirements.
Operational phase inspections are essential for ensuring that disposal activitics are being conducted in accordance with license conditions and regulatory requirements. Closure and post-closure inspections are essential to ensure 5
activities at closure are being conducted in compliance with the regulatory requirements and the facility is performing as expected. The frequency of inspections for opera. ting low-level radioactive wasta disposal facilities is specified in NRC inspection Manual, Chapter 2800, as yearly. Inspection frequencies for non-operational phase inspecthns should be established. There must be a capability for maintaining and retriev'ng statistical data on the status of the inspection program for the low-level radioactive waste disposal p ogram.
- 2. Technical Quality of Inspections (b)
This subelement provides the qualitative balance to subelement 1 above, which looks at the status of the inspection program on a quantitative basis, inspector accompaniments, including onsite resident inspectors, by review team members will be used to evaluate the knowledge and capabilities of Agreement State inspectors at low-level radioactive waste disposal ft.cilities during the inspections discussed in subelement 1 above. These accompaniments will usually occur at a time other than the onsite review of the hegion or.
Agreement State. Reviews in this area focus on the scope, completeness, and technical accuracy of inspections and reisted documentation. Review teams will conduct indepth, onsite reviews of completed inspection reports.
- 3. Technical Staffing and Training (c)
Evaluation of staffing and training should be conducted in the same manner and as part of the common performance indicator, Technical Staffing and Training, paragraph (B)(3)(a) (b), (c) and (d) (unless the Low-Level Radioactive Waste Program is organizationally separate from the materials program). The staffing (which can include contractual support or support from other state agencies) should be sufficient to enable the program to complete review of a new application within 15 months, if practicable, per the Low-Level Radioactive Waste Policy Amendments Act. Professional staff should normally have bachelor's degrees or equivalent training in the physical, life or earth sciences,
. or engineering. Staff and support contractors qualifications, training and experience should also include the disciplines of health physics, civil or mechanical engineering, geology, hydrology and other earth sciences, and environmental science.
- 4. Technical Quality of Licensing Actions (d)
An acceptable program for licensing low-level radioactive waste disposal f acilities ensures that the proposed waste disposal f acilities will meet State licensing requirements for waste product and volume, qualifications of personnel, site characterization, performance assessment, facilities and equipment, operating and emergency procedures, financial qualifications and assurances, closure and decommissioning procedures and institutional arrangements in a manner sufficient to establish a basis for licensing action.
This may be accomplit,hed through the preparation and use of internal licensing guides, policy memoranda, or use of NRC equivalent guides. Licensing 6
4
- .- -- _ . . ~ - - .- - -- - - . - - -
decisions should be adequately documented through safety evaluation reports, or similar documentation of the license review and approval process.
Opportunities for public hearings are provided in accordance with applicable State administrative procedure laws during the process of licensing a low-level radioactive waste disposal facility. Pre-licensing interactions with the applicant should be conducted to ensure clear communication of the regulatory requirements. (i)
To evaluate the technical quality of the licensing program, a review of a technical aspect of a radioactive waste disposal licensing action (such as health physics, hydrology, structutal engineering, etc.) will be conducted in addition to
. an evaluation of the license ieview process. Technical quality includes not only the review of completed actions, but also an examination of any ongoing requests for licenses or renewals that may have health and safety implications.
(ii)
- 5. Response to incidents and Allegations (e)
Reviews of low-level radioa::tive waste program incidents and allegations of safety concerns should be conducted in the same manner and as part of the common performance indicator, Response to incidents and Allegations (unless the Low-Level Radioactive Waste Progre.m is organizationally separate from the materials Frogram).
Performance Indicator 4 - Uranium Recovery Program (4)
%Fiv$ subelements, as appropriate, will be evaluated to determine if the performance of the Region IV or an Agreement State's Uranium Recovery Program is adequate.
- 1. Status of Uranium Recovery inspecticn Program (a) !
' Periodic inspections of licensed uranium recovery operations are essential to assure that activ'r ties are being conducted in compliance with regulatory requirements and consistent with good safety practices. The frequency of inspections is specified in the NRC Inspection Manual, Chapter 2600, for insitu leac'h mining facilities, and in NRC Inspection Manual, Chapter 2801, for conventional uranium and thorium mills. Uranium recovery facilities that are on standby or under decommissioning also should be inspected at that frequency.
Inspections should occur more frequently if significant regulatory concerns ,
develop, before major changes are made to operations, or if generic problems are identified. There must be a capability for maintaining and retrieving statistical data on the status of the inspection program for the uranium and thorium program.
- 2. Technical Quality of Inspections (b)
This subelement provides the qualitative balance to subelement 1 above, which looks at the status of the inspection program on a quantitative basis. Inspector 7
i i
I l
accompaniments by review team members will be used to evaluate the knowledge and capabilities of the Region and Agreement State inspectors at uranium recovery facilities. These accompaniments will usually occur at a time other than the onsite review of the Region or Agreement State. An acceptable program for conducting inspections for radioactive materiallicenses includes preparation and use of internal inspection guides and policy memoranda to l
ensure technical quality in the inspection program (when appropriate, NRC guidance may be used). Reviews of this subelement focus on the scope, completeness, and technical accuracy of completed inspections and related documentation. Review teams will conduct indepth, onsite reviews of completed inspection reports. In addition, review teams will verify that j supervisors generally conduct accompaniments of inspectors on an annual l
basis to provide management quality assurance.
]
- 3. Technical Staffing and Training (c)_
l Evaluation of staffing and training should be conducted in the same manner and i as part of the common performance indicator, Technical Staffing and Training, paragraph (B)(3)(a) (b), (c) and (d) (unless the Uranium Recovery Program is I organizationally separate from the materials program). Professional staff should 1 normally have bachelor's degrees or equivalent training in the physical sciences, life or earth sciences, or engineering. Staff and support contractors qualifications, training and experience should include the disciplines of health l physics, civil or mechanical engineering, geology, hydrology and other earth .
sciences, and environmental science.
- 4. Technical Quality of Licensing Actions (d) l l
An acceptable program for licensing uranium recovery activities ensures that essential elements of NRC licensing requirements for radiation protection, ,
qualifications of personnel, facilities and equipment, operating and emergency j procedures, financial qualification and assurance, closure and decommissioning procedures, and institutional arrangements are met in a manner sufficient to establish a basis for licensing action. This may be accomplished through the preparation and use of internal licensing guides and policy memoranda to -
ass 0re technical quality in the licensing program (when appropriate, NRC i Uranium Recovery Program Policy and Guidance System Guides may be used).
Prelicensing inspection of complex facilities are conducted, when appropriate.
(i)
To evaluate the technical quality of the Agreement State licensing program, an indepth review of an aspect of the uranium recovery license (such as radiation protection, hydrology, or geotechnical engineering) will be conducted.
Technical quality includes not only the review of completed actions, but also an examination of any ongoing requests and license renewals that may have health and safety impiications. Technical quality includes review of the State's compliance with the statutory requirements or prohibitions in Section 274 of :
the Atomic Energy Act, as amended. (ii) l 8 .,
i
)
i
- l
- 5. Response to incidents and Allegations (e)
Reviews of uranium recovery program incidents and allegations of safety concerns should be conducted in the same manner and as part of the common performance indicater, Response to incidents and Allegations (unless the Uranium Recovery Program is organizationally separate from the materials program)..
Performance Indicator 5 - Regional Fuel Cycle Inspection Program (5)
Five subelements, as appropriate, will be evaluated to determine if the performance of the Regional Fuel Cycle Inspection Program is adequate.
- 1. Status of Fuel Cycle inspection Program (a) j i
Periodic inspections of licensed operations are essential to ensure that activities are being conducted in compliance with regulatory requirements and license commitments, and in an overall safe and adequate manner. (i)
The appropriate frequencies of inspections for established procedures are discussed in NRC Inspection Manual, Chapter 2600. NRC Inspection Manual, Chapter 2600-04.02, provides the responsible Headquarters and Regional l offices flexibility to adjust the frequencies, focus, and intensiveness of '
inspections for different functional areas at a licensed facility, taking into account the complexity, risk level, and previous operating history of the facility.
These adjustments are generally determined by consensus of Headquarters and Regional management during the Licensee Performance Review (LPR) process, )
or in response to significant facility events or conditions between LPRs. (ii)
The level of resources provided for an inspection may also be adjusted.
Unexpected external influences (e.g., turnover of key staff, diversion of staff for AIT inspections in response to incidents, accretion of new regulatory responsibilities without timely provision of additional resources) may occasionally affect the frequencies with which routine inspections can be l conducted, or level of resources available for routine inspections. These should be documented and reviewed on a regular basis, and integrated into each facility's portion of the Fuel Cycle Master inspection Plan. The Master Inspection Plan should also include scheduling of LPRs according to the frequencies specified in NRC Inspection Manual, Chapter 2604. (iii)
Inspection scheduling and planning should consider the resource requirements for both routine and reactive inspection effort, preparation for and documentation of inspections, and participation in other programmatic duties, ,
such as training, licensee performance review, licensing support, participation in, or support for, enforcement conferences, etc. This planning should permit adequate time for inspectors to complete inspection reports in sufficient time j so that the reports can be issued in accordance with the timeliness requirements contained in NRC Inspection Manual, Chapter 0610. Other 9
planning and scheduling factors include concern for unusual impacts on licensees, and exchanges of inspection resources between different Regions.
The established fuel cycle inspection schedule for the Region should reflect these considerations. (iv)
Regional management should monitor the Region's inspection program to determine,th.at the current program is being implemented in accordance with the requirements of the fuel facility inspection program described in NRC Inspection Manual, Chapter 2600, the documented inspection plan for each facility, and overall Regional objectives. There should be a capability for maintaining and readily retrieving (without additional analytical effort) the necessary information for demonstrating the extent to which established inspection program objectives are being met. (v)
There should be a means for maintaining and readily retrieving Regional performance information for each facility. This information may reside in inspection reports, correspondence files, the inspection Follow-up System, the Nuclear Materials Events Database (NMED), etc. Where there are several different inspectors inspecting each facility, the Region may find it more practical to maintain its own summary information files (e.g., site issues
. matrices, incident analysis summaries, enforcement histories), to assemble the kind of information needed to support the Fuel Cycle Licensee Performance i
Review Program and to justify any changes in the inspection program for a facility as they occur. (This would prevent the loss of summary information valuable to the LPR, which is normally provided by the inspectors, if they are not available at the time the LPR is conducted.) Such programmatic changes should be documented at the time they are made. LPRs should be conducted in cooperation with Headquarters according to the schedule included in the Fuel Cycle Master inspection Plan. (vi)
The reviewer should examine specific instances in which established inspection program objectives appear not to be met, and determine if mitigating circumstances may have been documented to offer justification for departures from the established plans. (vii)
- 2. Technical cuality of Inspections (b)
This subelement provides the qualitative balance to the subelement 1 above, which looks at the status of the inspection program on a quantitative basis. (i)
Reviews of programs under this performance indicator subelement focus on the s': ope, completeness, and technical accuracy of completed inspections and related documentation. The reviewer will conduct indepth, onsite reviews of a cross-section of completed inspection reports, selecting from among those performed by different inspectors, if applicable. The reviewer may also interview the respective inspectors, if available. (ii)
The reviewer will verify that supervisors conduct accompaniments of 10
inspectors on an annual basis to provide management quality assurance. (iii)
Inspection efforts should focus on the performance of the licensee in assuring the safety and safeguarding of operations. Inspection reports should reflect this focus by addresshg licensee performance issues for plant operations posing the greatest safety or safeguards risks and where previous performance issues have been identified as requiring greater attention, consistent with the inspectiorj program previously documented for the facility. (iv)
Conversely, the results of inspections should be summarized and appropriately documented for later reference (e.g., for support of the Licensee Performance Review Program). (v)
Only qualified NRC inspectors are to conduct inspections on their own. When inspector trainees or contractors are included in an inspection visit, at least one qualified NRC inspector should be designated to lead the inspection. In such cases, the qualified inspector leading the inspection should provide guidance to such personnel, to ensure that their activities are appropriate to an NRC inspection. (vi)
- 3. Technical Staffing and Training (c)
The ability to conduct effective inspection programs is largely dependent on having a sufficient number of experienced, knowledgeable, well-trained technical personnel. Fuel cycle inspectors generally require extensive training in specialized technical areas, in addition to meeting academic requirements.
This often results in significant time delays before newly hired inspectors can become certified as qualified NRC Fuel Cycle inspectors. Under certain l conditions, staff turnover could have an adverse effect..on the implementation of a Region's fuel cycle inspection program, and thus could affect public health and safety. For small programs, their viability may depend upon the continued l availability of a single individual with skills and experience that would be difficult to replace with another individual. (i)
Plans should be in place to replace the functional capabilities required for each aspect of the program (perhaps by contributions from several different individuals), in case a key inspector becomes unavailable (e.g., cross-training of other staff in the same organization; identification of individuals with required skills and qualifications in other NRC organizations; identification of possible outside contractors with suitable experience or expertise to augment specified types of inspections, if needed, etc.) (ii)
For this performance indicator subelement, qualitative as well as quantitative measures must be considered in particular, the reason for apparent trends in staffing must be explored, is the rate of turnover or the degree of under-staffing symptomatic of a chronic problem, or is it merely a short-term phenomenon? Why is turnover high? Are inspectors being overburdened? Is high turnover related to a morale problem? What steps are being taken to address the basic problem? What impact is high turnover hcving on other 11
performance indicator subelements? (iii)
Review of staffing also requires a consideration and evaluation of the levels of training and qualification of the technical staff and management. New hires need to be technically qualified. Professional staff should normally have bachelor's degrees or equivalent training in the physical and/or life sciences, or related engin.eering fields. Training requirements for NRC fuel facility specialist inspectors are specified in NRC Inspection Manual, Chapter 1246. The requirements include a combination.of classroom requirements and practical on-the-job training. In addition, the qualification process includes demonstration of knowled0e of relevant sections of the U. S. Code of Federal Reaulations, completion of a Qualifications Journal, and satisfactory review before a Qualifications Board. There are also refresher training and retraining requirements, including taking new fuel cycle related courses as they are developed. (iv)
The small number of fuel cycle facility inspectors who may need training at any one particular time pose unique challenges to arranging for the proper training of these individuals on a cost-effective basis. The Region may have to seek outside training opportunities to provide inspectors with specific safety knowledge needed for unique aspects of their facilities (e.g., heavy duty overhead cranes). (v)
After an inspector is trained and initially qualified to perform inspections in a specific technical area, providing additional cross-training opportunities for inspectors-will increase the ability of the inspection organization to better respond to facility incidents, unexpected staff turnover, or other unusual situations.' (vi) ,
~4. Response to incidents and Allegations (d)
The quality, thoroughness, and timeliness of a regulator's response to incidents and allegations can have a direct bearing on public health and safety. (i)
Significant indicators of the overall quality of the fuel cycle facility inspection program will include detailed written procedures for incident response, and the maintenance of records and reports of actualincidents, focusing on internal and external coordination, and analytical, investigative, and follow-up procedures. (ii)
The Region should exhibit a readiness to respond, in conjunction with
. Headquarters, to major incidents that may arise at a facility. This willinclude a review of ' preparations in place at the Region's incident Response Center (e.g.,
' identification of individuals with required skills, facility data for use during emergencies, detailed preparations for responding to the highest risk types of incidents postulated for the facility, based upon known facility processes and source terms, etc.). (iii) 12
i The Region, possibly in coordination with Headquarters, should conduct, or participate in, documented follow-up self-assessments of drills and responses ;
to any major incidents that involved activation of the Region's incident :
! Response Center. (iv)
- l l
The Region's responses to any allegations involving fuel cycle facilities should be ground,ed in established inspection procedures and good technical and regulatory analysis to determine if regulations were followed or may be '
l deficient and in need of revision with regard to a significant safety issue brought to light by the allegation. (v) l Performance indicator 6 - Site Decommissioning Management Plan (SDMP) (6)
Six subelements, as appropriate, will be evaluated to determine if the performance of the Regional Site Decommissioning Management Plan (SDMP) is adequate.
- 1. Quality of SDMP Decommissioning Reviews (a)
Planned, significant decommissioning actions at facilities that are listed on the SDMP are reviewed and approved by the NRC staff in advance of decommissioning. Decommissioning plan reviews are conducted in accordance with NRC Inspection Manual, Chapter 2605, current NRC policies, standard review procedures, and other regulatory guidance. Reviews are documented as outlined in NRC Inspection Manual, Chapter 2605 using, as appropriate, !
Environmental Assessments, Environmental Impact Statements, Safety l Evaluation Reports, checklists, interrogatories, and other written correspondence.
- 2. Financial Assurance for Decommissioning (b)
Adequate financial assurance for the decommissioning of SDMP sites has been established in accordance with regulatory requirements and applicable guidance. Financial assurance is provided for estimated costs for an independent, third party to perform decommissioning with the objective of l releasing the site for unrestricted use, unless alternative arrangements have i bee'n approved by the regulator. Financial assurance mechanisms are reviewed j and maintained to ensure that they would be executable and provide sufficient i funding for decommissioning in the event that the licensee liquidates or is otherwise unable to pay for decommissioning.
- 3. Termination Radiological Surveys (c)
Sufficient radiological surveys are required prior to license termination and site release, as outlined in NRC Inspection Manual, Chapter 2605, to ensure that residual radioactivity levels comply with release criteria. Licensee survey l results are validated through a closeout inspection or confirmatory survey, as !
outlined in NRC Inspection Manual, Chapter 2605, given the extent and significance of any residual contamination. I l
l 13 i
. ._. . _ . _ _ . ~ . . _ . . . . . . _ _ _ _ _. _ ._ _ _ _ _ _ _ _ _
. l
- 4. Inspections (d)' l j Decommissioning projects are inspected in accordance with established I frequencies and with written inspection procedures to confirm the safety of )
- decommissioning procedures. Inspections are documented and carried out in l
- . accordance with inspection Procedures 87104 and 88104. Inspections focus j' on safety pf licensee procedures, release of effluents to the environment, j .public and worker exposure,'and suitability of decontaminated areas and structures for release, t 5. . Staff Qualifications (e)
License reviewers and inspectors are qualified through training and experience j to review the safety of decommissioning. Qualifications for license reviewers 1 and inspectors are established and reviewed. Staff members are qualified to l perform licensing reviews and inspections related to decommissioning through training and documented work experience. Non-qualified staff members are subject to the direct supervision of qualified managers; this supervision is
! cvidenced by concurrence on inspection reports and licensing documentation.
i .
- 6. SDMP Milestones (f)
The decommissioning milestones summarized in the SDMP are bein'g met if - ,
not, delays are identified and there is a mechanism in place to ensure that any appropriate corrective actions are taken. Policy issues affecting the decommissioning of SDMP sites are being identified. Staff is updating the SDMP database in a timely manner.
14
PART lli Evaluation Criteria NRC Regions and Agreement States will be evaluated in their ability to conduct effective licensing and inspection programs using the common and non-common performance indicators as appropri. ate, described in Part 11 of this handbook. The evaluation criteria for each performance indicator are given below.
Common Performance Indicator 1 - Status of Materials inspection Program (A)
Satisfactory (1)
- Core licensees (those with inspection frequencies of 3 years or less) are inspected at regular intervals in accordance with frequencies prescribed in NRC Inspection Manual, Chapter 2800. (a)
- Deviations from these schedules are normally coordinated between working staff and management. Deviations are generally the result of joint decisions that consider the risk of licensee operation, past licensee performance, and the need to temporarily defer the inspection (s) to address more urgent or more critical priorities. (b)
- There is a plan to reschedule any missed or deferred inspections or a basis established for not rescheduling. (c)
- Inspections of new licensees are generally conducted within 6 months of license approval, or in accordance with NRC Inspection. Manual, Chapter 2800 Section 04-03 for those new licensees not possessing licensed material. (d) j
- A large majority of the inspection findings are communicated to licensees in a timely manner (30 calendar days as specified in NRC Inspection Manual, Chapm 0610-10). (e)
Satisfactory with Recommendations for Improvement (2)
- More than 10 percent of the core licensees are inspected at intervals that exceed the NRC Inspection Manual, Chapter 2800, frequencies by more than
] 25 percent. (a) e inspections of new licensees are frequently not conducted within 6 months of license approval. (b)
- Many of the inspection finding are delayed, or not communicated to licensees within 30 days. (c) 1 i
i
. -- .-- - - _ _ . . - _ . = _ - - _- .
1
. i Unsatisfactory (3)
, o More than 25 percent of the core licensees are inspected at intervals that i
exceed the NRC Inspection Manual, Chapter 2800, frequencies by more than ;
25 percent. (a) l
- Inspections of new licensees are frequently delayed, as are the inspection l findings. (b) !
J Category N (4)
Special conditions exist that provide adequate justification for withholding a rating.
For example, an unforeseen event or emergency with significant health and safety I consequences may have required a temporary diversion of resources from the core l inspection program. However, these programmatic adjustments are well-thought i out, and properly coordinated with Office of Nuclear Material Safety and Safeguards l (NMSS) or Agreement State management. j l
Common Performance Indicator 2 - Technical Quality of Inspections (B)
Satisfactory (1) e l Review team members accompanying inspectors combined with an onsite )
, review of a representative cross-section of completed inspection reports indicates inspection findings are usually well-founded and well-documented throughout the assessment. (a) r
- A review of inspector field notes or completed reports indicates that most i inspections are complete and reviewed promptly by supervisors or management. (b) ]
l 5 '
- Procedures are in place and normally used to help identify root causes and poor licensee performance. (c)
- In most instances, follow-up inspections address previously identified open items and/or past violations. (d)
- Inspection findings generally lead to appropriate and prompt regulatory action.
(e) e Supervisors accompany nearly allinspectors on an annual basis. (f)
Satisfactory with Recommendations for improvement (2) e Review indicates that some inspections do not address potentially important health and safety concerns or it indicates periodic problems with respect to completeness, adherence to procedures, management review, thoroughness, technical quality, and consistency. (a) 2
- Review indicates that findings in inspection reports and inspection files are, on occasion, not well-founded or well-documented. (b)
- Review does not demonstrate an appropriate level of management review. (c)
- Accompaniment of inspectors by supervisors is performed non-systematically.
(d) ,
- Follow-up actions to inspection findings are often not timely. (e)
Unsatisfactory (3)
- Review indicates that inspections frequently fail to address potentially important health and safety concerns or it indicates chronic problems exist with respect to completeness, adherence to procedures, management review, thoroughness, technical quality and consistency. (a)
- Supervisors infrequently accompany inspectors. (b) !
l
- Follow-up actions to inspection findings are often not timely and appropriate.
(c)
Category N (4) i I
Not applicable.
Common Performance Indicator 3 - Technical Staffing and Training (C)
~
Satisfactory (1) j l
Review indicates implementation of a well-conceived and balanced staffing strategy throughout the assessment period, and demonstrates the qualifications of the technical staff. This is indicated by the presence of most of the following features:
- Balance in staffing the licensing and inspection programs. (a)
- Few,'if any, vacancies, especially at the senior-level positions. (b)
- Prompt management attention and review, such as development of a corrective action plan to address problems in high rates of attrition or positions being vacant for extended periods. (c)
- Qualification criteria for hiring new technical staff have been established and are being followed. (Staff would normally be expected to have bachelor's degrees or equivalent training in the physical and/or life sciences. Senior personnel should have additional training and experience in radiation protection commensurate with the types of licenses they issue or inspect.) (d) 3
l
- License reviewers and inspectors are trained and qualified in a reasonable time period.2 (e)
- Management commitment to training is clearly evident. (f)
Satisfactory with Recommendations for improvement (2) )
Review determ'ines the presence of some of the following conditions:
- Some staff turnover that could adversely upset the balance in staffing the licensing and inspection programs. (a)
- Some vacant positions not readily filled. (b) 1
- Some evidence of lack of management attention or actions to deal with staffing problems. (c)
- Some of the licensing and inspection personnel not making prompt progress in completing all of the training and qualification requirements. (d)
- The training and qualification standards include areas needing improvement. (e)
- Some of the new staff is hired with little education or experience in physical and/or life sciences, or materials licensing and inspection. (f) l Unsatisfactory (3) j Review determines the presence of chronic or acute problems related to some of the following conditions, which cause concerns about their likely impacts on other performance indicators:
- Significant staff turnover relative to the size of the program. (a) *
- Most vacant positions not filled for extended periods. (b)
- Little evidence of management attention or actions to deal with staffing problems. (c)
- Most of the licensing and inspection personnel not making prompt progress in completing all of the training and qualification requirements. (d) 2 For the Regions, this means there has been, and continues to be, a clear effort to adhere to the requirements and conditions specified in NRC Inspection Manual, Chapter 1246, and the applicable qualifications journals, or to receive equivalent training elsewhere. For the Agreement States, equivalent requirements should be in place and followed.
4
4
- New staff members are hired without having scientific or technical backgrounds that would equip them to receive technical training. (e)
Category N (4)
Special conditions exist thgt provide justifintion for withholding a rating. For 4
example, there has been a substantial management effort to deal with staffing problems. NMSS or Office of State Programs (OSP) has been kept informed of the situation, and discernable recent progress is evident.
- Common Performance Indicatcr 4 - Technical Quality of Licensing (D)
Satisfactory (1)
- Review of completed licenses and a representative sample of licensing files l indicates that license reviews are generally thorough, complete, consistent, and of acceptable technical quality. (a)
- Health and safety issues are properly addressed. (b)
- License reviewers have the proper signature authority for the cases they review independently. (c) .
- Special license tie-down conditions are usually stated clearly and are inspectable. (d)
- Deficiency letters clearly state regulatory positions and are used at the proper time. (e)
- Reviews of renewal applications demonstrate thorough analysis of a licensee's inspection and enforcement history. (f)
- Applicable guidance documents are available to reviewers and are followed. (g)
- No potentially significant health and safety issues can be linked to licensing practices. (h)
Satisfactory with Recommendations for improvement (2)
Review indicates that some licensing actions do not fully address health and safety concerns or indicates repeated examples of problems with respect to thoroughness, completeness, consistency, clarity, technical quality, and adherence to existing guidance in licensing actions.
Unsatisfactory (3)
Review indicates that licensing actions frequently fail to address important health and safety concerns or indicates chronic problems with respect to thoroughness, 5
. l 4
completeness, consistency, clarity, technical quality, and adherence to existing
- guidance in licensing actions.
Category N (4)
Not applicable.
Common Performance Indicator 5 - Response to incidents and Allegations (E) d Satisfactory (1) e incident response and allegation procedures are in place and followed in nearly all cases. (a) e Actions taken are appropriate, well coordinated, and timely in most instarices.
(b) e Level of effort is usually commensurate with potential health and safety ;
, significance of an incident. (c) '
e Investigative procedures are appropriate for an incident. (d) e Corrective (enforcement or other) actions are adequate!y identified to licensees promptly'and appropriate follow-up measures are taken to assure prompt compliance. (e) e Follow up inspections are scheduled and completed, if necessary. (f) e Notification to NMSS, the Office for Analysis and Evaluation of Operational Data (AEOD), or OSP, and others as may be appropriate, is usually performed in a timely f ashion. (g) 1 Satisfactory with Recommendations for improvement (2) e incident response and allegation procedures are in place but occasionally not practiced in a detailed fashion. (a) e Performance is marginal in terms of resolving potential public health and safety f
issues, but not as well coordinated, complete or timely as would be required under the " Satisfactory" performance standard. (b) e Infrequent failure to notify NMSS, AEOD, or OSP, and others, as appropriate, of incidents. (c)
Unsatisfactory (3) e Review indicates frequent examples of response to incidents or allegations to be incomplete, inappropriate, poorly-coordinated, or not timely. As a result, 6
> l I
potential health and safety problems persist. (a)
(b)
Category N (4) )
Not applicable.' ~
Non-common Performance Indicator 1 - Legislation and Program Elements Required for Compatibility (F) ;
i Satisfactory (1) I
- State statutes authorize the State to establish a program for the regulation of .
agreement material and provide authority for the assumption of regulatory j responsibility under the Agreement. (a)
]
l
- The statutes authorize the State to promulgate regulatory requirements i necessary to provide reasonable assurance of protection of public hesith and ;
safety. (b) !
- The State is authorized through its legal authority to license, inspect, and enforce legally binding requirements such as regulations and licenses. (c) ]
I
- State statutes are consistent with Federal statutes, as appropriate. (d)
- The State has existing legally enforceable measures such as generally applicable rules, license provisions, or other appropriate measures, necessary to j allow the State to ensure adequate protection of public health and safety in the l regulation of agreement material. (e)
- The State has adopted legal binding requirements, regulations, and other program elements in accordance with Management Directive 5.9, " Adequacy and Compatibility of Agreement State Programs," OSP Internal Procedures, i D.7, " Reviewing State Regulations" and B.7 (Revision 1), " Compatibility '
Categories and Health and Safety identification for NRC Regulations and Other Program Elements," with only minor discrepancies. (f)
- NRC regulations, that should be adopted by an Agreement State for purposes of compatibility or health and safety, are adopted in a time frame such that the effective date of the State requirement is not later than three years after the effective date of NRC's final rule. (g)
- Other program elements that have been designated as necessary for maintenance of an adequate and compatible program should be adopted and implemented by an Agreement State within 6 months of such designation by NRC. (h) 7
l l
l Satisfactory with Recommendations for improvement (2) e The State has adopted legal binding requirements, regulations, and other j
^
program elements in accordance with Management Directive 5.9, " Adequacy and Compatibility of Agreement State Programs," OSP Internal Procedures, D.7, " Reviewing State Regulations" and B.7 (Revision 1), " Compatibility !
Categories and Health and Safety identification for NRC Regulations and Other i Program Elements," but there are compatibility or health and safety 4
discrepancies that need to be addressed. (a) l e Several NRC regulations that should be adopted by an Agreement State are adopted in a time frame such that the effective date of the State requirement is greater than three years after the effective date of NRC's final rule. (b)
- Several program elements that have been designated as necessary for maintenance of an adequate and compatible program have been adopted and implemented by the Agreement State in a time frame greater than 6 months of such designation by NRC. (c)
Unsatisfactory (3) 4 e State no longer has statutes that authorize the State to establish a program for i
the regulation of agreement material and provide authority for the assumption l of regulatory responsibility under the Agreement. (a) e The State is not authorized through its legal authority to license, inspect, and enforce legally binding requirements such as regulations and licenses. (b)
~
j e State statutes are in conflict with, or do not sufficiently reflect scope of Federal statutes. (c)
- e The State does not have existing legally enforceable measures such as generally applicable rules, license provisions, or other appropriate measures, necessary to allow the State to ensure adequate protection of public health and safety in the regulation of agreement material. (d) e The State has not adopted significant legal binding requirements, regulations, i and other program elements in accordance with Management Directive 5.9,
" Adequacy and Compatibility of Agreement State Programs," OSP Internal Procedures, D.7, " Reviewing State Regulations" and B.7 (Revision 1),
" Compatibility Categories and Health and Safety identification for NRC
, Regulations and Other Program Elements." (e)
- e Most NRC regulations that should be adopted by an Agreement State are l consistently adopted in a time frame such that the effective date of the State 1
requirement is significantly greater (many months or years) than three years after the effective date of NRC's final rule. (f) a 1
8 i
i l
1 I
!
- Most program elements that have been designated as necessary for maintenance of an adequate and compatible program have been adopted and i
implemented by the Agreement States in a time frame significantly greater
- (many months or years) than 6 months of such designation by NRC. (g)
Category N (4) i l
Not applicable [ !
. Non-common Performance Indicator 2 - Sealed Source and Device Evaluation Program (G) l
- 1. Technical Quality of the Product Evaluation Program (1)
Satisfactory (a)
- Review of a representative sample of SS&D evaluations completed during the review period indicates that product evaluations are thorough, complete, consistent, of acceptable technical quality, and adequately address the integrity-of the products. (i)
- Health and safety issues are properly addressed. (ii)
- Registrations include complete summaries of the product evaluations and include appropriate signature (s) having the proper qualifications and training with documentation that confirms that an independent technical review was conducted by a second reviewer. (iii)
- All registrations clearly summarize the product evaluation and provide license reviewers with adequate information to license possession and use of the product. (iv)
- Deficiency letters clearly state regulatory positions and are used at the proper time. (v)
- An independent technical review of the application and proposed certificate of registration is performed by a second individual which supports the finding that the product is acceptable for licensing purposes. (It is important to keep in mind that the independent technical reviewer must concur with the initial review.) (vi)
- Applicable guidance documents are followed, unless approval to use alternate procedures is obtained from management. (vii)
- Completed registration certificates, and the status of obsolete registration-certificates, are clear and are promptly transmitted to interested parties. (viii)
- Reviewers ensure that registrants have developed and implemented adequate quality assurance and control programs. (ix) 9 I
- There is a means for enforcing commitments made by registrants in their applications and referenced in the registrstion certificates by the program. No potentially significant health and safety issues can be linked to a specific product evaluation that was improperly conducted. (x)
Satisfactory with Recommendations for improvement (b) t
- Review indicates that some SS&D evaluations do not fully address important
, health and safety concerns or indicates repeated examples of problems with respect to thoroughness, completeness, consistency, clarity, technical quality, j adherence to existing guidance in product evaluations, and addressing the integrity of the products. (i)
- Not all registrations clearly summarize the product evaluation and not all provide license reviewers with adequate information to license possession and
- use of the product. (ii)
- Reviewers do not follow all appropriate guidance documents. (iii) l l-
- Independent review of the reviewer's evaluation is not always performed by either management or staff having proper SS&D qualifications and training. (iv)
- Completed registration certificates, and the status of obsolete registration certificates, are not always clear or are not always promptly transmitted to interested parties. (v) 4
- Not all product evaluations include an evaluation of proposed quality assurance and control programs. (vi) j
- Commitments made by registrants in their applications, and referenced in the l registration certificates, cannot be enforced for all registrations. (vii)
Unsatisfactory (c)
- Rev,iew indicstes that SS&D evaluations frequently fail to address important health and safety concerns or indicates chronic problems with respect to thoroughness, completeness, consistency, clarity, technical quality, adherence to existing guidance in product evaluations, and adequately addressing the integrity of the products. (i)
- Registrations often do not clearly summarize the product evaluation and do not provide license reviewers with adequate information to license possession and use of the product. (ii)
- Reviewers often do not follow appropriate guidance documents. (iii) 10
.. - - - = -. - ~ . . . . - . _
1 4
. e Completed registration certificates, and the status of obsolete registration certificates, are unclear and are not promptly transmitted to interested parties.
(iv) e Product evaluations often do nnt include an evaluation of proposed quality assurance and control programs. (v)
- e Commitments made by registrants in their applications, and referenced in the registration certificates, often cannot be enforced. (vi) e The review has identified potentially significant health and safety issues linked to a specific product evaluation. (vii)
{ Category N (d) i Not applicable.
- j. 2. Technical Staffing and Training (2)
Satisfactory (a) 3 The technical review and audit are performed by staff having proper training and qualifications.
Satisfactory with Recommendations for Improvement (b)
Some reviewers do not have the proper qualifications and training.
Unsatisfactory (c) i Technical review of the reviewer's evaluation is either not performed or not
, performed by management or staff having proper qualifications and training.
I' Category N (d)
- Not applicable.
- 3. Evaluation of Defects and incidents Regarding SS&Ds (3)
. Satisfactory (a)
- The SS&D evaluation program routinely evaluates the root causes of defects and j incidents involving SS&D evaluations and takes appropriate actions, including modifications of SS&D sheets and notification of affected parties and other i regulatory authorities.
- 11
Satisfactory with Recommendations for improvement (b)
The SS&D evaluation program does not fully evaluate the root causes of all defects l and incidents involving SS&D evaluations, or when performed, the programs do not always take appropriate actions, including notification of interested parties.
Unsatisfactory,(c)
The SS&D eeltation program does not ensure evaluation of the root causes of defects and incidents involving SS&D evaluations, or if performed, does not ensure appropriate actions are taken, including notification of interested parties.
Category N (d)
Not applicable.
Non-common Performance Indicator 3 - Low-Level Waste Radioactive Waste Disposal Program (H) 1
- 1. Status of Low-Level Radioactive Waste Disposal Inspection (1)
Satisfactory (a)
- Low-level radioactive waste disposal licensees are inspected at regular intervals in accordance with frequencies prescribed in NRC Inspection Manual, Chapter 2800.(i)
- Deviations from these schedules are normally coordinated between working staff and management. (ii)
- The inspection findings are communicated to licensees in a timely manner (30 calendar days as specified in NRC Inspection Manual, Chapter 0610-10). (iii)
- All non-operationa' phase inspections are conducted at the State's prescribed frequency. (iv)
Satisfactory with Recommendations for improvement (b)
- The licensee is inspected at intervals that exceed the NRC Inspection Manual, Chapter 2800, frequency by more than 25 percent. (i)
- All non-operational phase inspections are conducted at intervals that exceed the State frequencies by more than 25 percent. (ii)
- Some of the inspection findings are delayed, or not communicated to licensees within 30 days. (iii) 12
Unsatisfactory (c)
- The licensee is inspected at intervals that exceed the NRC Inspection Manual, Chapter 2800, frequency by more than 100 percent. (i)
- Non-operational phase inspections are conducted at intervals that exceed the State frequencies by more than 100 percent. (ii)
- Inspection findings are frequently delayed. (iii)
Category N (d)
Not applicable.
- 2. Technical Quality of Inspections Satisfactory (2)
Satisfactory (a) i e Accompaniments of inspectors combined with an onsite review of completed inspection files indicate inspection findings are usually well-founded and well-documented throughout the assessment period. (i)
- A review of inspector field notes or completed reports, as appropriate indicates that most inspections are complete and reviewed promptly by supervisors or management. (ii)
- Procedures are in place and normally used to help identify root causes and poor licensee performance. (iii) e in most instances, follow-up inspections address previously identified open items and/or past violations. (iv) e inspection findings generally lead to appropriate and prompt regulatory action.
(v)
- Sup'ervisors accompany nearly allinspectors on an annual basis. (vi)
Satisfactory with Recommendations for Improvement (b)
- Review indicates that low-level radioactive waste disposal inspections do not fully address potentially important health and safety concerns or it indicates periodic problems with respect to completeness, adherence to procedures, management review, thoroughness, technical quality, and consistency. (i) i
- Review indicates that findings in inspection reports and inspection files are, on occasion, not well-founded or well-documented. (ii) 13 l
l I
1 l
1
- The review does not demonstrate an appropriate level of management review. l I
(iii)
- Accompaniments of inspectors by supervisors are performed non-systematically. (iv) e' Follow-up ac.tions to inspection findings are often not timely. (v)
Unsatisfactory (c)
- Review indicates that inspections (including construction phase and closure < monitoring phase) frequently fail to address potentially important health l and safety concerns or it indicates chronic problems exist with respect to l completeness, adherence to procedures, management review, thoroughness, technical quality and consistency. (i)
- Accompaniments of inspectors are infrequently performed. (ii) l
- Follow-up actions to inspection findings are often not timely and appropriate. I (iii)
Category N (d)
Not applicable.
- 3. Technical Staffing and Training (3)
Satisfactory (a)
- Review indicates that the qualifications of the technical staff are commensurate with expertise identified as necessary to regulate a low-level radioactive waste disposal facility. (i)
- The management has developed and implemented a training program for staff.
(ii) ,
- Staffing trends that could have an adverse impact on the quality of the program are tracked, analyz'ed and addressed. (iii)
Satisfactory with Recommendations for Improvement (b)
- There is some staff turnover that could adversely impact the low-level radioactive waste disposal program. (i)
- Some vacant positions are not readily filled. (ii)
- There is some evidence of lack of management attention or action to deal with
' staffing problems. (iii) 14
i
- Some of the licensing and inspection personnel in the Low-Level Radioactive
, Waste Disposal Program are not making prompt progress in completing all of the training and qualification requirements. (iv) a
- The training and qualification standards include areas that could be improved.
, (v)
~
(
- Some of the new staff is hired with little education or experience in physical
, and/or life sciences, materials licensing and inspection, civil or mechanical i
engineering, geology, hydrology and other earth sciences, and environmental i
science. (vi)
Unsatisfactory (c)
- There is significant staff turnover relative to the size of the program. (i)
- Most vacant positions are not filled for extended periods. (ii)
- There is little evidence of management attention or actions to deal with staffing problems. (iii) l
- Most of the licensing and inspection personnel are not making prompt progress in completing all of the training and qualification requirements. (iv) 1
- New staff members are hired without having education or experience in physical and/or life sciences, materials licensing and inspection, civil or mechanical engineering, geology, hydrology and other earth sciences, and environmental science. (v)
Category N (d)
Not applicable. l 1
- 4. Technical Quality of Licensing Actions (4)
Satisfactory (a)
- Pre-licensing interactions with the applicant are occurring on a regular basis. (i)
- Special license tie-down conditions are usually stated clearly and are inspectable. (ii)
- Deficiency letters clearly state regulatory positions and are used at the proper time. (iii)
- Reviews of amendments and renewal applications demonstrate thorough analysis of a licensee's inspection and enforcement history, if applicable. (iv) 15
- Applicable guidance documents are available to reviewers in most cases, and are generally followed. (v)
- . Public hearings in accordance to the State administrative laws have occurred.
(vi)
- Review of certain technical aspects of the low-level radioactive waste license files indicates that aspect of the license review is generally thorough, complete, consistent, and of acceptable technical quality. (vii)
- Health and safety issues are properly addressed. (viii)
- An evaluation of the license review process indicates hat the process is thorough and consistent. (ix)
- No potentially significant health and safety issues can be linked to licensing practices. (x)
Satisfactory with Recommendations for improveraent (b) ,
l
- Review indicates that some technical aspects of licensing do not fully address l health and safety concerns or indicates problems with respect to thoroughness, ;
completeness, consistency, clarity, technical quality, and adherence to existing guidance in licensing actions. (i)
- Some aspects of the public hearings are not consistent with State administrative law or do not address some aspects of the licensing of a low-level radioactive waste disposal facility. (ii)
Unsatisfactory (c) !
. l
- Review indicates that technical aspects of the licensing actions frequently fail I to address important health and safety concerns or indicates chronic problems I with respect to thoroughness, completeness, consistency, clarity, technical quality, and adherence to existing guidance in licensing actions. (i)
- Public hearings are not consistent with State administrativa law or fail to address aspects of the licensing of a low-level radioactive waste disposal f acility. (ii)
Category N (d)
Not applicable.
16
+
- 5. Response to incidents and Allegations (5)
Satisfactory (a)
Meets the performance for " Satisfactory" for the Response to incidents and Allegations (,ommon performance indicator criteria, E (1), as applied to the Response to it)cidents and Allegations subelement for Low-Level Radioactive Waste Disposal Program.
Satisfactory with Recommendations for improvement (b)
Meets the performance for " Satisfactory with Recommendations for Improvement" for the Response to incidents and Allegations common performance indicator criteria, E (2), as applied to the Response to incidents and Allegations subelement for Low-Level Radioactive Waste Disposal Program.
Unsatisfactory (c)
Meets the performance for " Unsatisfactory" for the Response to incidents and Allegations common performance indicator criteria, E (3), as applied to the Response to Incidents and Allegations subelement for Low-Level Radioactive Waste Disposal Program.
Category N (d) j l
Not applicable. 1 Non-common Performance Indicator 4 - Uranium Recovery Program (1)
- 1. Status of Uranium Recovery inspection Program (1)
Satisfactory (a) e Uranium recovery licensees are inspected at least once a yesr as prescribed in NRC Inspection Manual, Chapters 2801 and 2600. (i) e Deviations are generally the result of decisions which consider the risk of licensee operation, past licensee performance, and the need to temporarily defer the inspection (s) to address more urgent or more critical priorities. (ii) e There is plan to reschedule any missed or deferred inspections or a basis established for not rescheduling. (iii) e inspection findin0s are communicated to licensees at the exit briefings and confirmed formally in writing in a timely manner (30 calendar days as specified in NRC Inspection Manual, Chapter 0610-10). (iv) i 17 l l
l Satisfactory with Recommendations for Improvement (b) e The licensees are inspected at intervals which exceed the NRC Inspection Manual, Chapter 2801, frequencies for conventional uranium mi!!s or the NRC Inspection Manual, Chapter 2600, frequencies for insitu leach facilities by more than 25% (i) e Some of the inspection findings are delayed, or not communicated to licensees within 30 days. (ii) l I
Unsatisfactory (b) e The licensees are inspected at intervals which exceed the NRC Inspection Manual, Chapter 2801, frequencies for conventional uranium mills or NRC Inspection Manual, Chapter 2600, frequencies for insitu leach facilities by more l than 100%. (i) l i
e inspections findings are frequently delayed. (ii)
Category N (c)
Not applicable.
I
- 2. Technical Quality of Inspections (2) l l
l Satisfactory (a) e Accompaniments of inspectors combined with an onsite review of a ,
representative cross-section of completed inspection files indicate inspection l findings are usually well-founded and well-documented throughout the assessment period. (i) e Licensing history and status are incorporated into the inspection program as demonstrated through accompaniments and procedures in place. (ii) e A review of inspector field notes or completed reports indicates that most inspections are complete and reviewed promptly by supervisors or management. (iii) e Procedures are in place and normally used to help identify root causes and poor licensee performance. (iv) e in most instances, follow-up inspections address previously identified open items and/or past violations. (v) e Inspection findings generally lead to appropriate and prompt regulatory action.
(iv) 18
E e Supervisors accompany nerarly allinspectors on an annual basis. (vii)
Satisfactory with Recommendations for Improvement (b)
- Review indicates that uranium recovery inspections occasionally do not address potentially important health, safety, and environmental concerns or it indicates periodic problems with respect to completeness, adherence to procedures,
, management review, thoroughness, technical quality and consistency. (i) u e Review indicates that findings in inspection reports and inspection files are, on
- occasion, not well-founded or well-documented, and the review does not j demonstrate an appropriate level of management review. (ii) e Accompaniment of inspectors by supervisors is performed non-systematically.
(iii) i e Follow-up actions to inspection findings are often not timely. (iv)
Unsatisfactory (c)
- Review indicates that uranium recovery inspections frequently fail to address potentially important health, safety, and environmental concerns or it indicates chronic problems exist with respect to completeness, adherence to procedures, management review, thoroughness, technical quality and consistency. (i)
- Accompaniments of inspectors are infrequently performed. (ii) j e Follow-up actions to inspection findings are often not ti_mely and appropriate.
1 (iii)
Category N (d)
Not applicable.
J
- 3. Technical Staffing and Training (3)
Satisfactory (a)
- Review indicates that the qualifications of the technical staff are commensurate with expertise identified as necessary to regulate uranium recovery facilities.
(i) e The management has developed and implemented a training program for staff.
(ii)
- Staffing trends that could have an adverse impact on the quality of the program are tracked, analyzed and addressed. (iii) 19
i Satisfactory with Recommendations for Improvement (b) 3 e There is some staff turnover which adversely impacts the uranium recovery program. (i) i
'
- Some vacant positions, necessary for continued program effectiveness, are not readily fill _ed., (ii) 4 e There is some evidence of lack of management attention or action to deal with staffing problems. (iii) i e Some of the uranium recovery licensing and inspection personnel are not making prompt progress in completing all of the training and qualification requirements. (iv) e The training and qualification standards include areas that could be improved, j
(v) i
- Some of the new staff are hired with little education or experience in physical and/or life sciences, materials licensing and inspection, civil or mechanical engineering, geology, hydrology and other earth sciences, and environmental j- science. (vi)
Unsatisfactory (c) e
) There is significant staff turnover relative to the size of the program. (i) e Most vacant positions are not filled for extended periods. (ii) j 4 e There is little evidence of management attention or action to deal with staffing i problems. (iii) e Training program is not in place. (iv)
{
e Most of the licensing and inspection personnel are not making prompt progress in c'ompleting all of the training and qualification requirements. (v)
, o New staff members are hired.without having education or experience in physical and/or life sciences, materials licensing and inspection, civil or 3 mechanical engineering, geology, hydrology and other earth sciences, and j environmental science. (vi)
Category N (d) ;
Not applicable.
20
- 4. Technical Quality of Licensing Actions (4)
Satisf actory (a)
- Review of completed licenses and a representative sample of licensing files indicates that license reviews are generally thorough, complete, consistent, and of acceptable technical quality. (i)
- Health, safety, and environmental issues are properly addressed. (ii) e License reviewers almost always have the proper signature authority for the
. cases they review. (iii) l
- Special license tie-down conditions are usually stated clearly and are l inspectable. (iv) e Deficiency letters clearly state regulatory positions and are used at the proper time. (v)
- Reviews of renewal applications demonstrate thorough analysis of a licensee's inspection and enforcement history. (vi) e Applicable guidance documents are available to reviewers in most cases, and are generally followed. (vii) e No potentially-significant health and safety issues can be linked to licensing practices. (viii)
Satisfactory with Recommendations for improvement (b)
Review indicates that some licensing actions do not fully address health, safety, and environmental concerns or indicates repeated examples of problems with respect to ,,
thoroughness, completeness, consistency, clarity, technical quality and adherence l to existing guidance in licensing actions.
Unsatisfactory (c) l' Review indicates that licensing actions frequently fail to address important health, safety, and environmental concerns or indicates chronic problems with respect to i thoroughness, completeness, consistency, clarity, technical quality and adherence i to existing guidance in licensing actions, j I'
Category N (d)
Not applicable.
21
- 5. Response to incidents and Allegations (5)
Satisfactory (a)
Meets the performance for " Satisfactory" for Response to incidents and Allegations common performance indicator criteria, E (1), as applied to the Response to incidents and , Allegations subelement for the Uranium Recovery Program.
Satisfactory with Recommendations for improvement (b)
Meets the performance for " Satisfactory with Recommenda'. ions for improvement" for the Response to incidents and Allegations common performance indicator criteria, E (2), as applied to the Response to incidents and Allegations subelement for the Uranium Recovery Program.
Unsatisfactory (c)
Meets the performance for " Unsatisfactory" for the Response to incidents and Allegations common performance indicator criteria, E (3), as applied to the Response to incidents and Allegations subelement for the Uranium Recovery Program.
Category N (d)
Not applicable.
Non-common Performance Indicator 5 - Regional Fuel Cycle inspection Program (J)
- 1. Status of Fuel Cycle Inspection Program (1) 1 Satisfactory (a)
- Licensee facilities are inspected at regular intervals in accordance with frequencies prescribed in NRC inspection Manual, Chapter 2600, with appropriate documented adjustments to reflect licensee performance and the inherent risk of licensee operations. The schedules for facility inspections are appropriately updated and maintained in the Fuel Cycle Master Inspection Plan.
The inspections scheduled for each facility are consistent with the requirements of NRC Inspection Manual, Chapter 2600, with appropriate adjustments. There are few differences between the inspections planned and scheduled for the current fiscal year, and the inspection program currently intended for eerb i facility for the fiscal year. Changes in the Fuel Cycle Master inspectior an are documented when they occur and generally are the result of joint et . ions between management and staff in the Regions and Headquarters. Changes in the Region's inspection program for each facility are well-documented and primarily based on the inherent risks of licensee operation, past licensee performance, and the need to address more urgent or more critical priorities or deal with unforeseen resource limitations. (i) 22
1
- There is evidence that Regional management periodically ascertains the status l of the inspection program and acts swiftly to resolve problems affecting performance, when necessary. Management is confident that the existing inspection schedule adequately reflects the Regiun's stated objectives for each facility's inspection program. Management also is aware of the comparison between planned inspections and actual performance of inspections, and is confident _that the objectives for each facility's inspection program are being met. (ii) 1
- There is clear evidence of an ongoing process to reschedule any missed or deferred inspections, and to optimize the ability to meet the stated objectives, (iii) .
- The scheduling and performance of inspections optimizes the utilization of inspection resources so that inspectors are permitted sufficient time to prepare for and document inspections. The percentage of time inspectors spend on routine inspections, reactive inspections, preparation and documentation, and othei programmatic activities, is close to that originally planned in accordance with stated objectives. Significant departures kom what was originally planned, and the reasons for their occurrence, are documented as they become apparent. (iv)
- Inspection findings are communicated to licensees in a timely manner (normally within 30 calendar days, or 45 days for team inspections, as specified iri NRC Inspection Manual, Chapter 0610-10, unless there are legitimate doculented reasons for delays). (v)
- The Region adequately maintains documentation of licensee performance in support of the Licensee Performance Review Program. (vi)
Satisfactory with Recommendations for Improvement (b)
- Licensees are inspected at greater intervals than specified in NRC Inspection Manual, Chapter 2600, absent timely written documentation of the intention to do so. Objectives for the inspection of some of the Region's facilities are not documented in an inspection plan for each facility, or they are not in sufficient detail to adequately express the inspection requirements for each facility in terms of licensee performance or inherent facility risk. The inspections scheduled in the Fuel Cycle Master Inspection Plan for a facility do not correspond to the objectives previously documented for the facility's inspection program, and the reasons for the discrepancies have not been documented adequately. The inspections scheduled in the Fuel Cycle Master inspection Plan for one or more facilities do not reflect the requirements contained in NRC Inspection Manual, Chapter 2600, and no timely documentation exists to justify the discrepancies. (i)
- Reliable documentation regarding the conduct of the Region's inspection program cannot be readily produced, and the Re.gion cannot confirm within a 23
e I i
reasonable time that the inspection program meets the requirements of NRC Inspection Manual, Chapter 2600, or the objectives previously documented for f
each f acility's inspection program. (ii) e Regional management is slow to react to problems affecting performance of planned inspections, with the result that the inspections contained in the Fuel Cycle Master inspection Program no longer correspond to the inspection direction needed to focus on changes in licensee performance. (iii)
I e Some inspectors are underutilized or over-utilized for routine inspections to the extent that their or. site inspection hours do not correspond to the Region's stated objectives for utilization of inspection resources, with no adequate documentation to justify the discrepancies. (iv) e Some of the inspection findings are delayed, or not communicated to licensees within 30 days (45 days for team inspections), without adequate documentation of justification or legitimate reasons for such delays or deletions (as in the case of pending escalated enforcement). (v) e Documentation in support of the observations required to be formulated for the Licensee Performance Review Program do not exist, or are not easily located. ,
(vi) i Unsatisfactory (c) e Licensees are inspected at intervals that frequently exceed the NRC Inspection ;
Manual, Chapter 2600, frequencies, irrespective of licensee performance or facility risk, without adequate documentation or justification for such departures. (i) e Objectives for each f acility's inspection program have not been documented, or do not adequately consider NRC Inspection Manual, Chapter 2600, requirements, licensee performance, or the inherent risk of licensee operations.
(ii) !
e Management cannot readily demonstrate that the existing Regional fuel cycle inspection schedule, in combination with the recent history of completed inspections, support the inspection objectives described in the inspection '
programs for each facility. (iii) e inspections of licensees or communications of the inspection findings are frequently delayed, without adequate documentation or justification. (iv) j 3
e The Region does not adequately maintain documentation necessary to document licensee performance in suppcrt of the Licensee Performance Review Program. (v) e Observations provided to support the 1.icensee Performance Review Program l 24 l
1
4 cannot be supported by existing documentation. (vi)
Category N (d)
Special conditions exist that provide adequate justification for withholding a rating.
For example, an unforeseen event or emergency with significant health and safety consequences _may have required a temporary diversion of resources from the core 2
inspection program. However, these programmatic adjustments are well-founded and properly coordinated with NMSS management.
, 2. Technical Quality of inspections (2)
Satisfactory (a) e An onsite review of a representative cross-section of completed inspection files indicates inspection findings are usually well-founded and well-documented throughout the assessment period. (i) e A review of completed inspection reports indicates that most inspections are complete, consistent with the requirements of NRC Inspection Manual, Chapter 0610, and reviewed promptly by supervisors or management. (ii) e inspection efforts focus on the safety or safeguards significance of licensee performance, while maintaining alertness to possible trends and patterns of poor licensee performance. Plant operations addressed and performance areas emphasized correspond closely to the objectives documented for the Region's inspection program for the f acility. (iii) e in most instances, follow-up inspections address previously identified open items and/or past violations. (iv) e Inspection findings generally lead to prompt and appropriate regulatory action.
(v) e Allinspections are conducted or led by qualified NRC inspectors. Contractors and' inspector trainees, augmenting inspections, are provided proper guidance by the inspection leader during onsite inspections, resulting in good integration of the efforts of these personnel with those of the other qualified inspectors.
(vi) e Supervisors accompany allinspectors on at least an annual basis, with greater emphasis on the less-experienced inspectors. (vii)
Satisfactory with Recommendations for improvement (b) e Review indicates that findings in inspection reports and inspection files are, on occasion, not well-founded or well-documented, or the review demonstrates an inappropriate level of management review. (i) 25
< 1
- Review indicates that some inspections do not address potentially important
. health and safety concerns, or indicates recurring problems with respect to j
completeness, adherence to procedures, management review, thoroughness, technical quality, or consistency, relative to the requirements specified in NRC inspection Manual, Chapter 0610. (ii) i i
- Inspection efforts do not always focus on the safety or safeguards significance i
of licensee performance. Inspection reports do not attempt to address possible
, trends or patterns of poor licensee performance. Plant operations addressed and performance areas emphasized do not always correspond closely to the i
objectives documented in the Region's inspection program for the facility. (iii)
- An instance occurs in which a contractor or inspector trainee, augmenting an !
inspection, is not provided proper guidance by the inspection leader during an i onsite inspection, resulting in inappropriate activity by the contractor that is not immediately corrected when discovered. (iv)
- Accompaniments of inspectors by supervisors are not performed systematically to assure at least annual frequency, but the more recently hired, inexperienced inspectors are accompanied at least annually. (v) I
- Follow-up actions to inspection findings often are not timely, or not ;
appropriate. (vi)
Unsatisfactory (c)
- Review indicates that inspections frequently fail to address potentially important health and safety concerns, or indicates that. chronic problems exist with respect to completeness, adherence to procedures, management review, thoroughness, technical quality and consistency, relative to the requirements specified in NRC Inspection Manual, Chapter 0610. (i)
- Inspection efforts typically do not focus on the safety or safeguards significance of licensee performance. Inspection reports do not attempt to address possible trends or patterns of poor licensee performance. Plant
~
operations addressed and performance areas of emphasis typically bear little correspondence to the objectives documented in the Region's inspection program for the facility, or such documentation does not exist. (ii)
- More than one instance occurs in which a contractor, augmenting an inspection, is not provided proper guidance by the inspection leader during an onF'te inspection, resulting in inappropriate activity by the contractor that is not immediately corrected when discovered. (iii)
- An inspection is conducted solely by an individual who is not a qualified NRC inspector, or is led by an individual who is not a qualified NRC inspector. (iv)
- Accompaniments of inspectors are performed infrequently, and those that are 26
performed fail to involve the more recently hired, less experienced inspectors.
(v)
- Follow-up actions to inspection findings are often not timely or appropriate. (vi)
Category N (d)
~
Not applicable.
- 3. Technical Staffing and Training (3)
Satisfactory (a)
Review indicates implementation of a well-conceived and balanced staffing strategy throughout the assessment period, and demonstrates the qualifications of the technical staff. This is indicated by the presence of most of the following features.
- Prompt management attention and review to recognize staffing or training problems (e.g., high rates of attrition, positions being vacant for extended periods, lack of adequate training opportunities), and to develop appropriate corrective action plans. (i)
- Qualification criteria for hiring new technical staff have been established and are being followed. Staff would normally be expected to have bachelor's degrees or equivalent training in the physical and/or life sciences. Senior personnel should have additional training and experience beyond their original area of specialization to reflect the broader area of responsibility in their organization. (ii)
- Inspectors are trained and qualified in a reasonable time period, despite difficulties which may be encountered in the availability of training opportunities provided by NRC, or of alternative outside training opportunities determined by the Division of Fuel Cycle Safety and Safeguards (FCSS) to meet requirements specified in NRC Inspection Manual, Chapter 1246. Training plans and schedules for qualification are established, maintained, and personally reviewed by the inspector and management. (iii)
- Management ensures that inspectors avail themselves of opportunities for required training infrequently provided by NRC, or identifies to FCSS alternative outside training opportunities that can be determined by FCSS to meet NRC Inspection Manual, Chapter 1246, requirements, resulting in trainees reaching qualification without undue delays. (iv) 3 For the Regions, this means there has been and continues to be, a clear effort to adhere to the requirements and conditions specified in NRC Inspection Manual, Chapter 1246, and the applicable " Qualifications Journals," or to receive equivalent I training elsewhere. J 27
- Management ' commitment to training is clearly evident. (v)
- Inspectors are provided cross-training opportunities to develop skills necessary to substitute for or assist other inspectors in functional areas outside their normal assignments. (vi) i
- Inspectors are current with regard to required retraining and refresher training.
(vii)
- Records are kept to keep track of how training requirements are satisfied for those requiring training, provide reminders of when refresher training is due,
. and to provide reliable and accurate statistics on the status'of the training program. (viii) l i
Satisfactory with Recommendations for Improvement (b) l l
- Some unanticipated staff turnover has occurred, that could adversely affect the ability of remaining staff to conduct the inspection program, and management has not taken immediate steps to adjust inspection planning accordingly, or begin the process of replacement. (i)
)
l
- Some vacant positions have not been readily filled. (ii) l l
- Some evidence of management attention or actions to deal with staffing problems that may have arisen, but problem still persists. (iii)
- Some of the inspection personnel are not making reasonable progress in l completing the training (or retraining) and qualification requirements, despite allowing for difficulties in arranging for NRC inspection Manual, Chapter 1246, required courses infrequently provided by NRC. (iv)
- Management permits several instances to occur, in which inspectors do not avail themselves of opportunities for required training infrequently provided by NRC, resulting in extensions of the time needed for trainees to reach qualification. (v)
- The Region's training and qualification standards do not completely correspond to functional requirements for inspections. (vi)
- Minor difficulties arise when attempting to accurately determine the status of training, retraining, and refresher training requirements and accomplishments for those requiring such training. (vii)
- Some of those requiring retraining or refresher training are not current - there is an effort to track and schedule the required training, but there is no documentation to explain why the necessary training has not been provided.
(viii) 28
~ -. - ~. . . . - - - - - -. .
Unsatisfactory (c)
Review determines the presence of chronic or acute problems related to some of the following conditions, which cause concerns about their likely impacts on other subelements of this performance indicator.
i e Significant u_nanticipated staff turnover relative to the size of the program, the
- causes of which cannot all be attributed to normal attrition. (i)
- Many vacant positions remain unfilled for extended periods. (ii) j i'
- Little evidence is exhibited of management attention or actions to deal with
, staffing problems found to exist. (iii)
- Many of the inspection personnel have not met their schedules for qualification, or met refresher training requirements, falling short of written plans and j schedules to do so. (iv) l
- Some opportunities for taking NRC Inspection Manual, Chapter 1246, required l
- training courses infrequently provided by NRC, or alternative outside training ]
, opportunities identified by FCSS as meeting such requirements, were not !
attended by inspectors needing such courses for qualification, contributing to failure of inspector trainees to meet established schedules for qualification. (v) j'
- New staff members are hired without having adequate scientific or technical 4
backgrounds. (vi) 4
- Management is unable to determine within a reasonable time the status of
!- training, retraining, and refresher training for those requiring such training. (vii)
]
- Inadequate or no tracking or scheduling for those requiring retraining or 1
refresher training. (viii)
- Newly hired inspector trainees are not provided sufficient onsite training experience, or they are not provided proper guidance by inspection leaders or
- sup'ervisors while directly contributing to inspections. (ix) j
)
- Management consistently withdraws inspection personnel from required training activities to participate in other activities, with the result that established schedules for qualification of inspection personnel are not met. (x)
Category N (d)
Special conditions exist that provide justification for withholding a rating. For example, there has been a substantial management effort to deal with staffing problerns, or the mission of the organization has changed too rapidly for training programs to adjust. NMSS has been kept informed of the situation, and discernable recent progress is evident.
29
! (n i
e l
- 4. Response to incidents and Allegations (4)
Satisfactory (a) e Incident response and allegation procedures are in place. (i) l
- Incident r_esponse and allegation procedures are appropriately followed in nearly all cases. Actions taken are well-coordinated with Headquarters, as appropriate, and timely in most instances. Level of effort investigating incidents is usually commensurate with potential health and safety significance t of incident. (ii) J e Corrective (enforcement or other) actions are adequately identified to licensees promptly, and appropriate follow-up measures are taken, in coordination with Headquarters, as appropriate, to ensure prompt compliance and protection of public health and safety. (iii) e Follow-up inspections are scheduled, if necessary, and completed within a reasonable time. Notification to NMSS, AEOD, and others, as may be appropriate, are usually provided in a timely fashion. (iv) e Preparations for the Region's portion of the response to major incidents are appropriate to the types of incidents that may occur at the Region's facilities.
Sufficient documentation exists to identify individuals with required skills and experience to be summoned to respond in an emergency, and potential Regional participants have been trained to respond to worst case scenario incidents. (v)
~
e Procedures are in place to periodically check for completeness of materials needed for emergency response and to occasionally update these materials when circumstances change (e.g., staff turnover, completion of training requirements by staff who would respond, change in processes conducted at facilities, or addition or deletion of a facility). (vi) e The Region's portion of self-assessment activities following a drill or actual eve'nt are comprehensive in recognizing problems that arose during the subject activity. Recommendations for improvement arising in self-assessment studies are tracked to ensure further study or implementation. (vii)
- e. Inspection activity conducted as follow up to receipt of allegations is technically sound and successful in determining the safety implications of the allegations, as appropriate. (viii)
Satisfactory with Recommendations for improvement (b) e The Regional portions of incident response and allegation procedures are in place, but occasionally are not adhered to in detail. (i) 30
4
- Resolution of potential public health and safety issues is marginal, with problems in coordination, or timeliness. (ii)
- Preparations for the Regional portions of emergency response lag behind !
changes in circumstances (as described above). Some lapses in training, ;
background, or experience needed to deal with identified types of incidents l requiring _res_ponse, or some types of incidents have been analyzed at the i Region's facilities but are not recognized in the Region's portion of emergency ;
response plans. (iii) l
- Region's portion of self-assessment activities following a drill or actual event are shallow in some areas, in not recogniz.ing or further analyzing problems that arose during the subject activity. Some recommendations for improvement in self-assessment studies are not tracked to ensure further study or !
implementation. (iv)
- Regional portion of inspection activity conducted as follow up to receipt of allegations fails to completely address the safety implications of the allegations.
(v)
Unsatisfactory (c) l
- Review indicates frequent examples of Regional portion of response to incidents or allegations to be incomplete, inappropriate, poorly-coordinated, or not timely. As a result, the identified potential health and safety problems persist. (i)-
- Through Regional direction, excessive effort is allocated to the investigation of relatively minor safety issues to the detriment of addressing more significant ones. (ii)
- There is a failure of the Region to adequately prepare for significant incidents that could occur at the Region's facilities, despite existing documentation or analyses that indicate they could occur. (iii)
- Inspection activity is not conducted as a follow up to receipt of an allegation, though there was a clear need to investigate the safety implications of the allegations. (iv)
Category N (d)
Not applicable.
31
Non-common Performance Indicator 6 - Site Decommissioning Management Plan (SDMP)
(K)
- 1. Quality of SDMP Decommissioning Reviews (1) l Satisfactory (a)
Nearly all deco'mdlissioning plans are reviewed in accordance with NRC Inspection Manual, Chapter 2605, and these reviews are documented as outlined in NRC Inspection Manual, Chapter 2605.
Satisfactory with Recommendations for improvement (b)
J Most decommissioning plans are reviewed in accordance with NRC Inspection Manual, Chapter 2605 and these reviews are documented as outlined in NRC Inspection Manual, Chapter 2605.
Unsatisfactory (c)
Decommissioning plans are not being consistently reviewed in accordance with NRC Inspection Manual, Chapter 2605, or documented as outlined in NRC Inspection Manual, Chapter 2605.
Category N (d)
Special conditions exist that provide justification for withholding a rating for one or i more evaluation criteria.
- 2. Financial Assurance for Decommissioning (2)
Satisfactory (a) e For nearly all sites, financial assurance is provided for the estimated costs for an independent, third party to perform decommissioning with the objective of releasing the site for unrestricted use. (i) e For sites where financial assurance has not been provided, alternative arrangements have been approved by the regutator. (ii) e Financial assurance mechanisms are reviewed and maintained to ensure that they are executable and provide sufficient funding for decommissioning in the event that the licensee liquidates or is otherwise unable to pay for decommissioning. (iii)
Satisfactory with Recommendations for improvement (b) e For most sites, financial assurance is provided for the estimated costs for an independent, third party to perform decommissioning with the objective of 32
4 j.
I i releasing the site for unrestricted use. (i) e For most sites where financial assurance has not been provided, alternative ;
i arrangements have been approved by the regulator. (ii) .
e e For most sites, financial assurance mechanisms are reviewed and maintained to j ensure that they are executable and provide sufficient funding for l decommissioning in the event that the licensee liquidates or is otherwise unable ,
to pay for decommissioning. (iii)
)
j Unsatisfactory (c) i
- - e Financial assurance is not consistently provided for the estimated costs for an independent, third party to perform decommissioning with the objective of 1 releasing the site for unrestricted use. (i) e For sites where financial assurance has not been provided, alternative arrangements have not been always approved by the regulator. (ii) e Financial assurance mechanisms are not being consistently reviewed and maintained to ensure that they would be executable and provide sufficient funding for decommissioning in the event that the licensee liquidates or is otherwise unable to pay for decommissioning. (iii)
Category N (d)
Special conditions exist that provide justification for withholding a rating for one or more evaluation criteria.
- 3. Termination Radiological Surveys (3)
Satisfactory (a) l e For nearly all SDMP sites, sufficient radiological surveys are being performed prior to license termination and site release, as outlined in NRC Inspection Manual, Chapter 2605, to ensure that residual radioactivity levels comply with release criteria. (i) e Licensee survey results are routinely validated through a closecut inspection or confirmatory survey, as outlined in NRC Inspection Manual, Chapter 2605, given the extent and significance of any residual contamination. (ii)
Satisfactory with Recommendations for improvement (b) !
e For most SDMP sites, sufficient radiological surveys are being performed prior to license termination and site release, as outlined in NRC Inspection Manual, Chapter 2605, to ensure that residual radioactivity levels comply with release criteria. (i) 33
e Licensee survey results are usually validated through a closecut inspection or confirmatory survey, as outlined in NRC Inspection Manual, Chapter 2605, given the extent and significance of any residual contamination. (ii)
Unsatisfactory (c)
Sufficient radiological surveys are not consistently being performed prior to license termination and site release, as outlined in NRC Inspection Manual, Chapter 2605, to ensure that residual radioactivity levels comply with release criteria, or survey results are not normally validated through a closecut inspection or confirmatory survey, as outlined in NRC Inspection Manual, Chapter 2605, given the extent and significance of any residual contamination.
Category N (d)
Special conditions exist that provide justification for withholding a rating for one or more evaluation criteria.
- 4. Inspections (4)
Satisfactory (a) e At nearly all SDMP sites, inspections are carried out in accordance with established frequencies. (i) e SDMP sites are inspected at least once during decommissioning, and at all jificant milestones in the decommissioning process, in addition to the close out inspection prior to license termination. (ii) !
e Inspections are documented and carried out in accordance with inspection procedures 87104 and 88104. (iii)
Satisfactory with Recommendations for Improvement (b) e At most SDMP sites, inspections are carried out in accordance with established j frequencies. (i) e SDMP sites are inspected at least once during decommissioning, and at most significant milestones, in addition to the close out inspection prior to license termination. (ii) e At most SDMP sites, inspections are documented and carried out in accordance l with inspection procedures 87104 and 88104. (iii) i Unsatisfactory (c) l e ' Inspections are not consistently being carried out in accordance with established frequencies. (i) 34
. _ _ - - _ _ _ ___ - - _ _ _ _ _ _ _ _ _ .. m .
d
- SDMP sites a're not inspected at least once during decommissioning, or at significant milestones, in addition to the close out inspection prior to license termination. (ii) 1
- Inspections are not consistently being documented and carried out in accordance with inspection procedures 87104 and 88104. (iii)
Category N (d) '
Special conditions exist that provide justification for withholding a rating for one or more evaluation criteria.
- 5. Staff Qualifications Satisfactory (a)
- Qualifications for license reviewers and inspectors are established and reviewed annually. (i)
- Nearly all staff members are qualified to perform licensing reviews and inspections related to decommissioning through training and documented work experience. (ii)
- Non-qualified staff is subject to the direct supervision of qualified managers; this supervision is evidenced by concurrence on inspection reports and licensing documentation. (iii) l Satisfactory with Recommendations for Improvement (b)
- Qualifications for license reviewers and inspectors are established and reviewed every 2 - 3 years. (i)
- Most staff members are qualified to perform licensing reviews and inspections related to decommissioning through training and documented work experience.
(ii) .
- Non-qualified staff is usually subject to the direct supervision of qualified managers; this supervision is evidenced by concurrence on inspection reports and licensing documentation. (iii)
Unsatisfactory (c)
- Qualifications for license reviewers and inspectors are not established or if established, these qualifications are not reviewed. (i)
- The majority of staff is not qualified to perform licensing reviews and inspections related to decommissioning through training and documented work experience. (ii) 35
e Non-qualified staff is not typically subject to direct supervision of qualified managers. (iii)
Category N (d)
Special conditions exist that provide justification for withholding a rating for one or ,
more of the evaluation criteria, i 1
- 6. SDMP Milestones (6) l Satisfactory (a) e At nearly all SDMP sites, the decommissioning milestones summarized in the SDMP are being met or delays are identified and a mechanism is in place to ensure that any appropriate corrective actions are taken. (i)
-e Policy issues affecting decommissioning of SDMP sites are being identified. (ii) e Staff is updating the SDMP database in a timely manner. (iii)
Satisfactory with Recommendations for Improvement (b) i e For most SDMP sites, the decomrnissioning milestones summarized in the SDMP are being met or delays are identified and a mechanism is in place to I ensure that any appropriate corrective actions are taken. (i) e Staff routinely identifies policy issues affecting the decommissioning of SDMP sites in a timely manner. (ii) e Staff is updating the SDMP database for most sites in a timely manner. (iii)
Unsatisfactory (c) e The decommissioning milestones summarized in the SDMP are not routinely being met or delays are not being identified and a mechanism is not in place to ens'u re that any appropriate corrective actions are taken. (i) e Policy issues affecting the decommissioning of SDMP sites are not typically being identified in a timely manner. (ii) e Staff is not routinely updating the SDMP database in a timely manner. (iii)
Category N (d)-
Special conditions exist that provide justification for withholding a rating for one or more evaluation criteria.
36
PART IV Programmatic Assessment General (A)
A management review board (MRB) will make the overall assessment of each NRC Region's or Agreement State's program, on the basis of the proposed final report and recommendations prepared by the team that conducted the review of that Region or State, including any unique circumstances. i1)
The MRB will consist of a group of senior NRC managers, or their designees, to include the: (2)
- Deputy Executive Director for Regulatory Programs (a)
- Director, Office of Nuclear Material Safety and Safeguards (b) l
- Director, Office of State Programs (c) l i
- Director, Office for Analysis and Evaluation of Operational Data (d) i i
- General Counsel (e) l The Agreement States also will be invited to nominate a representative to participate in MRB meetings, as a non-voting Agreement State liaison. In this capacity, the State representative would have full authority to receive applicable documentation and engage in all MRB discussions except for any that might involve
~
3 the Agreeme.nt State liaison's own State. The Agreement State liaison would not have voting authority; this function is reserved solely to NRC. (3) J l
For an NRC Region, the MRB will only assess the adequacy of the program to l protect public health and safety. The nature of NRC findings regarding NRC's l Agreement State review process is described below. (4)
Findings for Agreement State Programs (B) )
Finding 1 - Adequate to Protect Public Health and Safety and Compatible (1)
- If NRC finds that a State program has met all the Agreement State program review criteria or that only minor deficiencies exist, the Commission will find that the State's program is adequate to protect public health and safety. (a)
- If the NRC determines that a State program does not create conflicts, gaps, or disruptive duplication in the collective national effort to regulate Atomic Energy Act materials, the program would be found compatible. (b) 1
. . . - _. - . =- - - - - . . ~
Finding 2 - Adequate to Protect Public Health and Safety and Not (;ompatible (2)
If NRC finds that a State program has met all the Agreement State program i
review criteria or that only minor deficiencies exist, the Commission will find that the State's program is adequate to protect public health and safety. (a) ;
- If NRC deter. mines that a State program creates unnecessary gaps, conflicts, or disruptive duplication in the collective effort to regulate Atomic Energy Act materials, the program would be found not compatible. (b)
] Finding 3 - Adequate, But Needs improvement and Compatible (3) l
- If NRC finds that a State program protects public health and safety, but is deficient in meeting some of the review criteria, NRC may find that the State's l l program is adequate, but needs improvement. NRC would consider, in its l
determination, which deficiencies noted during the review that the State has to
]
address. (a) l I
1
- In cases where less significant State deficiencies previously identified have l j- been uncorrected for a significant period of time, NRC also may find that the program is adequate but in need of improvement. (b)
If the NRC determines that a State program does not create conflicts, gaps, or disruptive duplication in the collective national effort to regulate Atomic Energy Act materials, the program would be found compatible. (c) inding 4 - Adequate, But Needs improvement and Not Compatible (4)
- If NRC finds that a State program protects public health and safety, but is deficient in meeting some of the review criteria, NRC may find that the State's l 3 program is adequate, but needs improvement. NRC would consider, in its j i determination, which deficiencies noted during the review that the State has to -
address. (a)
}
- In cases where less significant State deficiencies previously identified have I bee'r] uncorrected for a significant period of time, NRC also may find that the program is adequate but in need of improvement. (b) 9 e if NRC determines that a State program creates unnecessary gaps, conflicts, or disruptive duplication in the collective effort to regulate Atomic Energy Act materials, the program would be found not compatible. (c) a
- Finding 5 - Inadequate to Protect Public Health and Safety and Compatible
- If NRC finds that a State program is significantly deficient in some or all the review criteria, NRC would find that the State's program is inadequate to protect public health and safety. (a) 2
- If the NRC determines that a State program does not create conflicts, gaps, or disruptive duplication in the collective national effort to regulate Atomic Energy Act materials, the program would be found compatible. (b)
Finding 6 - Inadequate to Protect Public Health and Safety and Not Compatible e if NRC finds that a State program is significantly deficient in some or all the review criteria, NRC would find that the State's program is inadequate to protect public health and safety. (a) i e if NRC determines that a State program creates unnecessary gaps, conflicts, or disruptive duplication in the collective effort to regulate Atomic Energy Act
- materials, the program would be found not compatible. (b)
Findings for NRC Regional Programs (C) 1 The MRB findings for Regional programs will be the same as those listed above for Agreement States with the exclusion of the findings for compatibility.
3
l 4
Glossary it is necessary to note that some Agreement States or NRC Regions may not define l these terms identically, in such cases, the review team will highlight any differences in its review, but draw its conclusions and make its assessments based on the definitions used by that State or Region at the time of the review.
Allegation. A declaration, statement, or assertion of impropriety or inadequacy '
4 associated with regulated activities, the validity of which has not been established.
This term includes all concerns identified by sources such as the media, individuals,
- or organizations, and technical audit efforts from Federal, State, or local government a
offices regarding activities at a licensee's site. Excluded from this definition are matters being handled by more formal processes such as 10 CFR 2.206 petitions, hearing boards, anpeal boards, and so forth.
1 1
Fuel Cycle inspections. The definition of " Inspections" in 10 CFR 170.3 should be used to determine what constitutes a fuel cycle inspection. The term includes both routinely scheduled and reactive inspections.
j incident. An event or condition that has the possibility of affecting public health and safety such as described in 10 CFR 20.2201,10 CFR 20.2202,10 CFR .
! 20.2203,10 CFR 20.2204,10 CFR 30.50,10 CFR 34.25,10 CFR 34.30,10 CFR 35.33,10 CFR 36.83,10 CFR 39.77,10 CFR 40.60,10 CFR 70.50,10 CFR 71.97, or the equivalent State regulations. ;
Materials inspection. The definitions in 10 CFR 170.3, and in NRC Inspection l Manual, Chapter 2800, Sections 03.03 and 07.01, should be used to determine what constitutes an inspection. In addition, Agreement State hand-delivay of new licenses may constitute initial inspections. The term includes' both routinely scheduled and reactive inspections. I I
4 Materials Licensing Action. Reviews of applications for new byproduct materials l licenses, license amendments, renewals, and license terminations.
Overdue inspections. Currently, NRC defines this term based on guida ce in NRC inspection Manual, Chapter 2800, especially Sections 04.03 (a), and 05.01 through 05.04. Many States use different definitions. For purposes of this Directive, a
, materials license will be considered overdue for inspection in the following cases:
A new licensee that possesses licensed material has not been inspected within 6 full months of receipt of licensed material, within 6 months of beginning licensed activities, or within 12 months of license issuance, whichever comes first.
l -
An existing core license is more than 25 percent beyond the interval defined in NRC Inspection Manual, Chapter 2800, Enclosure 1. An existing non-core license is more than 1 year beyond the interval. (An inspection will not be considered overdue if the inspection frequency j
', 1
. . . . . . . - . -..- - - -. ~ . .- - . . . ~ ~ - - . - - - .
l-s-*
p has been extended in accordance with NRC Inspection Manual, Chapter 2800, Section 05.01, based on good licensee performance.)
Determinations of overdue inspections will not be based on any l inspection frequencies, established by States or Regions, that are lJ more stringent than those contained in NRC Inspection Manual, Chapter 2800. The frequencies provided in NRC Inspection Manual, Chapter 2800, will generally be used as the yardstick for determining i if an inspection is overdue.
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