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Category:NRC TECHNICAL REPORT
MONTHYEARML20009A1201981-06-25025 June 1981 Problem of Human Intrusion:Towards Resolution of Uncertainty ML20008F7591981-04-30030 April 1981 Preliminary Analysis of the Effect of Fatigue Loading and Crack Propagation on Crack Acceptance Criteria for Nuclear Power Plant Components ML19343D2261981-03-31031 March 1981 Plan for Reevaluation of NRC Policy on Decommissioning of Nuclear Facilities ML19345G3091981-02-11011 February 1981 Presentation to Commissions of Nrc:Loft Test Program ML19340D6041980-12-16016 December 1980 Use of Stds in Selecting Sites for Nuclear Power Plants ML19343B0021980-11-30030 November 1980 Analyses of Comments on 10CFR72 ML19343A8631980-10-31031 October 1980 Methodology for Calculating Residual Radioactivity Levels Following Decommissioning ML19351C9211980-09-30030 September 1980 Summary of Public Comments and NRC Analysis Related to Rulemaking on Emergency Planning for Nuclear Power Plants ML19347A8141980-08-31031 August 1980 Environ Assessment for Effective Changes to 10CFR50 & App E to 10CFR50;Emergency Planning Requirements for Nuclear Power Plants ML19344F0451980-08-31031 August 1980 Pipe Cracking Experience in Lwrs ML19343A0791980-07-30030 July 1980 Draft Resolution of Industry Comments to Draft Reg Guide on Ultrasonic Testing of Reactor Vessel Welds During Inservice Examination & Its Value/Impact Statement. Unofficial Comments Encl ML19326D8371980-06-30030 June 1980 Users Guide to Gaspar Code ML20126B4091980-01-31031 January 1980 NRC Staff Preliminary Analysis of Public Comments on Advance Notice of Proposed Rulemaking on Emergency Planning ML19296D0151979-12-21021 December 1979 Criteria Dealing W/Access Controls to Vital Areas ML19250C1341979-09-30030 September 1979 Draft Residual Activity Limits for Decommissioning ML19250C1211979-08-31031 August 1979 Thoughts on Regulation Changes for Decommissioning ML19249E8561979-08-0808 August 1979 Ofc of Stds Development Emergency Planning Action Plan ML19242D4631979-07-19019 July 1979 Rept on NRC Personnel Involved in Development of Nuclear Stds & Stds Organizations & Committees,Re Privacy Act File NRC-15 ML19224A7861979-05-10010 May 1979 Population Dose & Health Impact of Accident at TMI Nuclear Station ML19256F0251979-05-0606 May 1979 Draft Rept, Population Dose & Health Impact of Accident at TMI,790328-0407 ML19224C3321979-04-19019 April 1979 TMI-2 Groundwater Study ML20147D9791978-12-19019 December 1978 Transportation Security Personnel Training Manual. Vol 1. 2A,2B & 3 ML20147H7611978-12-11011 December 1978 Documents Re Assessment by Office of Standards Dev of the Uses of WASH-1400 in the Licensing Process.Includes Memos, Repts,Transcripts,Etc,Noted by Staff as Pertinent ML19289E4371978-12-0808 December 1978 Risk Assessment of Radioactive Waste Isolation in Deep Geologic Formations, from 781204-08 Meeting of Review Group for EPA ML19308A1651978-10-31031 October 1978 Radiological Environ Monitoring by NRC Licensees for Routine Operation of Nuclear Facilities, Task Group Rept ML20150C1191978-10-31031 October 1978 Site Security Personnel Training Manual Vol 1,2,3,& 4 ML19256F8031978-02-28028 February 1978 Interior Intrusion Alarm Sys ML20148K1301978-02-28028 February 1978 Early Site Reviews for Nuclear Power Facilities:Procedures & Possible Technical Review Options,Draft Revision ML19323B3371978-02-23023 February 1978 Solubility of U Compounds at U Mills ML20197D6681977-12-31031 December 1977 Principles & Practices for Keeping Occupational Radiation Exposures at Medical Institutions Alara. Draft Companion to Reg Guide 8.18 ML19326E1321977-06-30030 June 1977 Regulatory & Other Responsibilities as Related to Transportation Accidents ML20049H9821977-05-31031 May 1977 Basic Considerations for Assembling a CLOSED-CIRCUIT Television System ML19296A6101976-04-30030 April 1976 Calculation of Releases of Radioactive Matls in Gaseous & Liquid Effluents from Boiling Water Reactors ML19269E9991975-04-30030 April 1975 Environ Survey of Transportation of Radioactive Matls to & from Nuclear Power Plants:Suppl 1 to WASH-1238 1981-06-25
[Table view]Some use of "" in your query was not closed by a matching "". Category:TEXT-SAFETY REPORT
MONTHYEARML20009A1201981-06-25025 June 1981 Problem of Human Intrusion:Towards Resolution of Uncertainty ML20008F7591981-04-30030 April 1981 Preliminary Analysis of the Effect of Fatigue Loading and Crack Propagation on Crack Acceptance Criteria for Nuclear Power Plant Components ML19343D2261981-03-31031 March 1981 Plan for Reevaluation of NRC Policy on Decommissioning of Nuclear Facilities ML19345G3091981-02-11011 February 1981 Presentation to Commissions of Nrc:Loft Test Program ML19340D6041980-12-16016 December 1980 Use of Stds in Selecting Sites for Nuclear Power Plants ML19343B0021980-11-30030 November 1980 Analyses of Comments on 10CFR72 ML19295E7381980-11-0707 November 1980 Forwards Proposed Fr Notice on Disposition of Critical Mass Energy Project,Et Al Petition for Rulemaking Re Emergency Response,Draft Ltr to Petitioners & Proposed Congressional Ltr to Representative Mk Udall ML19295E7421980-11-0404 November 1980 Recommends Commission Approval of Proposed Rulemaking Qualification of Reactor Operators. Draft Fr Notice, Background & Discussion,Recommendations of SECY-79-330E & Draft Congressional Ltr & Public Announcement Encl ML19343A8631980-10-31031 October 1980 Methodology for Calculating Residual Radioactivity Levels Following Decommissioning ML19351C9211980-09-30030 September 1980 Summary of Public Comments and NRC Analysis Related to Rulemaking on Emergency Planning for Nuclear Power Plants ML19352A3451980-09-30030 September 1980 Recommends That Commission Approve Encl Draft Final Rule on Fire Protection Program for Nuclear Power Plants Operating Prior to 790101 ML19344F0451980-08-31031 August 1980 Pipe Cracking Experience in Lwrs ML19347A8141980-08-31031 August 1980 Environ Assessment for Effective Changes to 10CFR50 & App E to 10CFR50;Emergency Planning Requirements for Nuclear Power Plants ML19280A2551980-08-21021 August 1980 Requests Commission Approval of Final Rulemaking Deleting 10CFR20.304 Re Burial of Small Quantities of Radionuclides. Value Impact Assessment & Rept Justification for Deletion of 10CFR20.304 & Proposed Fr Notice Deleting 20.304 Encl ML19351F0491980-08-15015 August 1980 Recommends Approval of Fr Notice to Respond to DOE Request for Rulemaking to Exempt from Licensing Requirements Smelted Alloys Containing Tc-99 & Low Enriched U as Residual Contamination ML19343A0791980-07-30030 July 1980 Draft Resolution of Industry Comments to Draft Reg Guide on Ultrasonic Testing of Reactor Vessel Welds During Inservice Examination & Its Value/Impact Statement. Unofficial Comments Encl ML19320C7111980-07-0202 July 1980 Proposes Mods to Fr & Final Rule Changes on Emergency Preparedness Submitted for Commission Approval in SECY-80-275.Changes Do Not Effect Cost Estimates.Replacement Pages Encl ML19326D8371980-06-30030 June 1980 Users Guide to Gaspar Code ML19329G1611980-06-25025 June 1980 Replacement Pages 31,25,25a,50,51,51a & 47 Modifying Fr Notice & Final Rule Changes Re Emergency Preparedness ML19320B6631980-06-17017 June 1980 Forwards Revised Schedule for Proposed Rulemaking on Reactor Siting.Discusses Need for Greater Deliberation NUREG-0685, Discusses Finalization of Emergency Planning Rule Changes, Including Consideration of Public Comments.Recommends Fr Publication Re Final Rulemaking.Related Documentation Encl1980-06-0303 June 1980 Discusses Finalization of Emergency Planning Rule Changes, Including Consideration of Public Comments.Recommends Fr Publication Re Final Rulemaking.Related Documentation Encl ML19318A7411980-05-21021 May 1980 Errata Sheet for Page 45 of NUREG/CP-0011, Proceedings of Workshops on Proposed Rulemaking on Emergency Planning for Nuclear Power Plants NUREG-0587, Recommends Issuance of Final Rule 10CFR72 Re Specific Licensing Requirements for Storage of Spent Fuels in Independent Spent Fuel Storage Installation.Draft Fr Notice Encl1980-05-0808 May 1980 Recommends Issuance of Final Rule 10CFR72 Re Specific Licensing Requirements for Storage of Spent Fuels in Independent Spent Fuel Storage Installation.Draft Fr Notice Encl ML19344D7321980-04-30030 April 1980 Proceedings of Workshops on Proposed Rulemaking on Emergency Planning for Nuclear Power Plants ML19323C0611980-02-29029 February 1980 Notifies Commission of Issues Pertinent to Reported Excess Number of Births W/Thyroid Abnormalities Near Tmi.Apparently No Connection Exists Between Thyroid Defects & TMI Radiation ML19309F2451980-02-26026 February 1980 Updates SECY-80-26 Re Amend to Code Requirements for Reporting Therapy Misadministrations.Licensee Is Not Required to Notify Patient Before Consultation W/Physician ML19323B3711980-02-13013 February 1980 Recommends Commission Approve Publication of Proposed Fire Protection Rule in Fr for Public Comment.Forwards Draft Fr Notice & Draft Value/Impact Assessment ML19262C5261980-02-0707 February 1980 Draft Intl Safeguards, for Presentation at DOE Workshop on Nuclear Fuel Cycle & Technical Aspects of Nuclear Weapons Proliferation ML20126B4091980-01-31031 January 1980 NRC Staff Preliminary Analysis of Public Comments on Advance Notice of Proposed Rulemaking on Emergency Planning ML19290D0671980-01-16016 January 1980 Requests Commission Approval of Notice of Final Rulemaking Requiring Medical Licensees to Keep Records of All Misadministrations,Rept Therapy Misadministrations to NRC, Referring Physician & Patient or Responsible Relative ML19294B5911980-01-16016 January 1980 Requests NRC Approval to Publish Proposed Amend for Public Comment.Recommends That NRC Approve Publication of Amend for Comment.Draft Proposed Rule & Congressional Committee Ltr Encl ML19296C8951980-01-10010 January 1980 Revised Pages:4,8,10,Encl 3;1 & 2,Encl 6;3,Encl 7 & 1; Encl 9 ML19296D0151979-12-21021 December 1979 Criteria Dealing W/Access Controls to Vital Areas ML19296C8981979-12-0707 December 1979 Discusses Employee Protection for Individuals Providing Info to Nrc.Recommends Issuance of Joint Nrc/Dept of Labor Memorandum of Understanding Re Discrimination & Procedures ML19296D0181979-11-28028 November 1979 Summarizes Comments Solicited Re Restructuring 10CFR20 Radiation Protection Stds.Recommends Approval of Encl Draft Notice for Issuance in Fr ML19254E8351979-10-15015 October 1979 Discusses Proposed Amends to 10CFR73.55 Re Complementary & Alternative Measures for Protection Against Insider Threat. Recommends Extension Until 801101 for Implementation of Patdown Searches & 2-man Rule Procedures ML19250C1341979-09-30030 September 1979 Draft Residual Activity Limits for Decommissioning ML19250C1211979-08-31031 August 1979 Thoughts on Regulation Changes for Decommissioning ML19210D7551979-08-14014 August 1979 Changes Recommendation of SECY-79-392 in Favor of Modified hybrid-type Hearing Format.Commission Should Approve Continued Negotiations W/Epa & OSHA to Make Arrangements for Acceptable Type of Hearing ML19305B7471979-08-10010 August 1979 Recommends That Commission Approve Encl Draft Notice of Proposed Rulemaking 10CFR51 Re Evaluation of Alternative Sites for Nuclear Generating Stations Under Nepa.Draft Value/Impact Assessment Encl ML19249E8561979-08-0808 August 1979 Ofc of Stds Development Emergency Planning Action Plan ML19254E8381979-07-25025 July 1979 Recommends Extension Until 801101 for Implementation of Patdown searches,2-man Rule Procedures & Compartmentalization ML19242D4631979-07-19019 July 1979 Rept on NRC Personnel Involved in Development of Nuclear Stds & Stds Organizations & Committees,Re Privacy Act File NRC-15 ML19210D9951979-06-14014 June 1979 Seeks Commission Approval for Continued Negotiations W/Epa & OSHA to Conduct Modified legislative-type Hearing on Adequacy of Current Occupational Exposure Stds ML20202F9951979-05-10010 May 1979 Transmits to Commissioners Advance Copies of New National Academy of Sciences Rept on Biological Effects of Ionizing Radiation (Beir III Rept).Pages 9 Thru 56,59 Thru 101,103 Thru 106,108 Thru 121,150 Thru 233 & 247 Thru 341 Omitted ML19224A7861979-05-10010 May 1979 Population Dose & Health Impact of Accident at TMI Nuclear Station ML19256F0251979-05-0606 May 1979 Draft Rept, Population Dose & Health Impact of Accident at TMI,790328-0407 ML19225B2721979-04-27027 April 1979 Info Rept for Commissioners Summarizing Issues Re Seismic & Geologic Siting Regulation,Policy & Practice for Nuclear Power Plants.Background Info Re Geoscience,Engineering Design,Policy & Technical Issues Encl ML19242C9591979-04-26026 April 1979 Seeks NRC Approval to Publish Amend to 10CFR34 as Final Rule Intended to Improve Radiography Safety & Make Regulations More Compatible W/Current Licensing Practices ML19224C3321979-04-19019 April 1979 TMI-2 Groundwater Study 1981-06-25
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Text
CRITERIA DEALING WITH ACCESS CONTROLS TO VITAL AREAS 10 CFR 73.55(a) requires licensees to protect against industrial sabotage by an insider, including an employee (in any position).
10 CFR 73.55(d)(7) states that access to Vital Areas shall be positively controlled and limited to individuals who are authorized access to vital equipment and who require such access to perform their duties.
Specific commitments implementing this regulation are described in each licensee's approved Security Plan.
NRR, in meetings with licensees in March 1977, to discuss 73.55 and the components of an acceptable physical security plan, explained that positive control of access to vital areas consisted of two elements:
one, to be author-ized access to a Vital Area, the individual requesting entry must have the necessary background screening and a need to perform job related functions in the area, and two, to have a need at that specific time to enter the Vital Area to perform a specific function.
This is comparable to gaining access to a classified document; one must have both a clearance and a need-to-know.
In approving security plans, NRR has assumed that the determination of need would be based upon a valid need and not convenience.
Furthermore, access should be authorized to a minimum number of people, and licensees should use a reasonable basis to determine this restricted number of authorized personnel and the frequency of their access.
Acceptance Criterion 5.B of the Security Plan Evaluation Report (SPER)
Workbook, dated January 1978, states that the licensee must commit to providing positive access control to Vital Areas by:
1)
Limiting access only to authorized personnel.
2)
Requiring positive identification prior to entry.
8 0 0 2 29?M 1
Enclosure "B"
3)
Requiring an established need for access.
4)
Maintaining records of entry, exit, and reason for entry.
5)
Providing a system for personnel control within the Vital Area.
NRR Review Guideline #21 suggests that blanket access authorizations should not be granted.
Instead, an acceptable method of indicating Vital Areas to which access is authorized should include a record of each vital area to which the holder of a key card is authorized access, and the key card be encoded to permit access only to those Vital Areas to which an individual has been granted access.
Review Guideline #23 states that for access to a Type I Vital Area, the person must be authorized entry by the shift supervisor or other designated individual who has been informed of the estimated length of time to be spent in the Type I Vital Areas.
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D EtiCLOSURE C
Enclosure "C" UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 July 26, 1979 IE Bulletin No. 79-16 VITAL AREA ACCESS CONTROLS
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Description of Circumstances:
An attempt to damage new fuel assemblies occurred recently at an operating nuclear reactor facility.
During a routine fuel inspection, the licensee discovered that a chemical liquid had been poured over 52 of 64 new fuel assemblies.
Analysis indicates that the chemical liquid was scdium hydroxide, a chemical stored and used dnsite.
The licensee stores new fuel assemblies in dry storage wells en the same elevation as the spent fuel poql within the Fuel Building, a vital area.
Access to the building is controlled by use of a coded keycard which elec-tronically unlocks the alarmed personnel portals.
The licensee issues coded keycards to both licensee and contractor personnel after the successful com-pletion of a background screening program.
In addition, licensee site manage-ment certifies monthly that each individual has the need for a coded keycard in order to perform required duties.
Further access within this building is not limited by other barriers or controls.
As a result of this incident, an initial licensee audit determined that several hundred licensee and centractor personnel had access to this area during the period when the attempt to damage the fuel was made.
The audit also revealed that one coded keycard reader at a vital area portal was inaccurately recording access data at the alana station.
Also discovered during this audit were indications of frequent " tailgating" on access through the portals.
Tailgating occurs when more than one person passes through a portal en one persen's authorized access.
Their passage is therefore not recorded, and unauthorized persons could gain entry in this manner.
Tailgating does not include author-ized access controlled by an escort.
Discussion of Applicable Requirements:
10 CFR 73.55(a) requires the li:ensees to protect against :ndustrial sabotage ccanitted by an insider in any position.
10 CFR 73.55(d)(7) states that access to Vital Areas shall be positively controlled and limited to individuals who arq authorized access to vital equipment and who require such access to perfonn their duties.
Specific commitments ic;nenting this regulation are described in each licensee's approved Security plan.
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- ) dye Q 79 0 70 L
IE Sulletin No. 79-16 July 25,1979 Page 2 of 4 NRR, in their meetings with the licensees in March 1977 to explain 5 73.55 and what would constitute an acceptable plan, explained that positive control of access to a vital area consisted of two elements:
first, that the eerson requesting. entry has the necessary background screening and need to perfom job related functions to be a'.'thorized access to that Vital Area, and second, that he has a need at that specific time to enter to perform a specific func-tion.
This is comcarable to gaining acciss to a classified document; you need both a clearance and a need to know.
In approving security plans, NRR assumes that the determination of need would be based upon a valid need and not convenience.
Furthermore, access should be authorized to a minimum number of people, and licensees should use reason-able altarnatives to minimize the number of personnel and frequency of access.
Acceptance Criterion.5.S of-the Security Plan Evaluatien Report (SPER)
Workbook, dated January 1978, states that the licensee must co= nit to pro-viding positive access control to Vital Areas by:
1)
Limiting access to authorized personnel.
2)
Requiring positive identification prior to entry.
3)
Raquiring an established need for access.
4)
Maintaining records of entry, exit and reason for entry.
5)
A system for control within the Vital Area.
NRR Review Guideline #21 suggests that blanket access authorizations should not be granted by stating that an acceptable method of indicating the Vital Areas to which access is authorized includes a record of each vital area to which the holder is authorized access, and the card is encoded to permit access to enly those Vital Areas to which the individual has been granted access.
Review Guideline J23 states that for access to a Type I Vital Area, the person must be authorized entry by the shift supervisor or other designated individual who has been informed of the estimated length of time to be spent in the Type I Vital Area.
There needs to be some balance attained between operational necessity and the administrative burden of validating the need for access each time entry is to be afforded.
Many licensees grant " permanent access authorization" to all 7
persons requiring access to vital areas, regardless of the frequency or dura-tion of the need.
This is contrary to the regulations and guidelines frcm NRR cited above.
Enclosure "C" O
IE Sulletin No. 79 16' July 25,1979 Page 3 of 4 Acticn to be Taken by Ticensee:
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Establish ci-iteria for granting unescorted access to each vital area, which shall be based upon the following:
a.
A screening program meeting ANSI N18.17.
i I
b.
The individual has a valid need for access to the equipment contained in each vital area to which access is authorized.
Valid need is based upon assigned duties requiring the performance of specific tasks upon or associated with specific equipment located in each vital area to which access is granted.
Valid need to enter cne vital area shall not necessarily indicate that the person has a need to enter any other vital area.
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2.
An access list will be established for each area not to exceed 31 days.
An individual will' be on the access list only for the duration of the task to be p'erformed.
If an individual has a valid need for unescorted access for a single entry or for intermittent occasions during this period, a separate daily access list shall be prepared.
All access lists shall be approved by the station manager (or equivalent) or his designated representative.
3.
Individuals will be. removed from the access list irmediately upon termination of need.
If an individual has not entered the vital area during the effective pericd of the access list (not to exceed 31 days) the need for access should be reassured prior to extending the authoriza-tion.
To ensure that these actions are taken, the access list shall be reviewed and reapproved at least every 31 days.
4.
Void access authorizations for all personnel not satisfying the criteria in la&b and where appropriate, reprogram the key card system and reissue key cards that are coded to implement the above vital area access authori-zation program.
5.
Develop reasonable alternatives so that the number and frequency of access to vital areas can be minimized consistent with safe operations.
5.
Establish emergency procedures where, during an emergency, additional authorized personnel, meeting criteria in la&b, can move freely throughout the vital areas with their entry and exit being recorded.
Upon securing from the emergency, the entry / exit record will be reviewed, and normal access control will be. reestablished. ~
7.
prevent tailgating by one or more of the following:
Enclosure "C"
.I
IE Bulletin No. 79-16 July 26,1979 Page 4 of 4 Establish procedures' that require authorized personnel to prevent a.
other personnel, including those authorized unescorted access, from tailgating.
Ensure all authorized personnel are trained in the prece-dure, and establish a management program that ensures that the prece-dure is properly performed.
i b.
Acquire equipment, such as turnstiles, to prevent tailgating.
Ensure that such equipment will not deny access or egress under emergency conditions.
Station a guard, watchperson or escort at the vital area access portal.
c.
This alternative would be ecst useful when there is a large number and frequency of access, such as occurs with containment during refueling.
'. By any other means _that achieve this objective.
d 8.
Assign corporate responsibility for management oversight of VA access control and require personal involvement to ensure that all interrediate levels of management are properly discharging their responsibilities 'in this regard.
9.
Conduct routine functional tests of the electronic access control system, including each key card reader, to verify (i) its operability and prorer performance, and (ii) the accuracy of the data recorded.
This test should be incorporated into the seven-day test required by 10 CFR 73.55(g).
/
- 10. Report in. writing within 45 days (for facilities with an cperating license) the actions you have taken and plan to take (including a schedule) with regard to Items 1 through 9.
Reper:s should be submitted to the Director of the appropriate NRC Regicnal Office and a copy should be forwarded to the NRC Office of Inspection and Enfercement, Division of Safeguards Inspection, Washington, D.C.
20555.
Approved by GAO, B180225 (RC072); clearance expires 7-31-80.
Approval was given under a blanket clearance specifically for identified generic problems.
Enclosure "C"
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ENCLOSURE D s