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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20210E5881999-06-30030 June 1999 Comment Supporting Draft Reg Guide DG-1074, Steam Generator Tube Integrity. Northern States Power Endorses Comments Transmitted by NEI Ltr ML20199C2721997-10-27027 October 1997 Comment Supporting Proposed Rules 10CFR50 & 73, Proposed Amends to NRC Requirements for Emergency Preparedness & Security DD-97-18, Director'S Decision DD-97-18 Re 970528 Petition Filed by Prairie Island Indian Community Requesting That USNRC Take Action to Determine That NSP Violated Requirements of 10CFR72.122(i).Request Denied Due to Listed Reasons1997-08-29029 August 1997 Director'S Decision DD-97-18 Re 970528 Petition Filed by Prairie Island Indian Community Requesting That USNRC Take Action to Determine That NSP Violated Requirements of 10CFR72.122(i).Request Denied Due to Listed Reasons ML20216G2821997-08-26026 August 1997 Petition for Rulemaking PRM-72-4 to Suspend for Cause Northern Station Power Co Matl License SNM-2506 Needed to Operate Independent Spent Fuel Storage Installation at Prairie Island Nuclear Generating Plant ML20148Q5641997-06-23023 June 1997 Order Prohibiting Involvement in NRC Licensed Activities (Effective Immediately).Prohibits Jl Barnhart from Any Involvement in NRC-licensed Activities for Period of 5 Yrs from Date of Order ML20140E4721997-05-28028 May 1997 Petition by Prairie Island Indian Community,Per 10CFR2.206, Requesting That NRC Determine That NSP Violated Requirements of 10CFR72.122(I) by Using License SNM-2506 for ISFSI Prior to Establishing Conditions for Safely Unloading TN-40 ML20138K1511997-05-0606 May 1997 Comment Supporting Proposed Rule 10CFR73 Re Changes to Nuclear Power Plant Security Requirements ML20148R2451997-04-24024 April 1997 Demand for Info Re Jl Barnhart Contract Employee at NSP, Working Under Temporary Unescorted Access Authorization. NRC Needs Info to Determine Whether Enforcement Action Should Be Taken to Ensure Future Compliance W/Requirements ML20134P6241996-11-26026 November 1996 NRC Staff Response to Florence Township Motion for Dismissal & Request for Hearing.Concludes That Motion Should Be Denied for Reasons Set Forth.W/Certificate of Svc ML20129D4771996-10-15015 October 1996 NRC Response to Petition for Leave to Intervene of Minnesota Dept of Public Svc.* Dept Should Be Permitted to Participate as Interested State,If Another Petition Granted. W/Certificate of Svc & Notice of Appearance ML20117E4051996-08-0909 August 1996 Comment Supporting Proposed Rule 10CFR26 Re Fitness for Duty Rule ML20117K0031996-05-0101 May 1996 Order,Granting Dismissal of Motions by Nsp,Public Utilities Commission & Environ Quality Board for Protective Orders Per Discovery & Plaintiff Motion for Temporary Injunction ML20094J0471995-10-11011 October 1995 Comment on Proposed Rules 10CFR60,72,73 & 75 Re Safeguards for Spent Fuel or High Level Radwaste ML20085E5261995-06-0606 June 1995 Comment Supporting Proposed Rule 10CFR73 Re Changes to NPP Security Requirements Associated W/Containment Access Control ML20083K2731995-04-28028 April 1995 Comment on Proposed Rule 10CFR50 Re Primary Reactor Containment Leakage Testing for water-cooled Power Reactors. Urges NRC to Support Rev to NEI 94-01 Which Will Allow Use of Two Reduced Pressure Type a Tests as Prerequisites ML20077M6181994-12-30030 December 1994 Comment Re Proposed Rule 10CFR50 Re Low Power Operations for Np Reactors.Util Believes That Pr Will Have Higher Impact than Described in Regulatory Analysis,As Pr Will Extend Refueling Outages at All Plants ML20071H4161994-06-30030 June 1994 Comment Supporting Petition for Rulemaking PRM-20-23 Re Reduction of Radioactive Emission from 100 Mrems to 1 Mrem/Yr ML20059K5201994-01-26026 January 1994 Demand for Info to Determine Whether Commission Can Have Reasonable Assurance That Other Burns Employees & Managers Will Carry Out Licensed Activities W/O Discriminating Against Individuals Re Safety Issues ML20062M4001993-12-30030 December 1993 Comment Supporting NUMARC Position on Proposed Rule 10CFR73 Re Protection Against Malevolent Use of Vehicles at NPPs ML20045G0941993-04-21021 April 1993 Comment on Proposed Rules 10CFR50,52 & 100 Re Nuclear Power Plant Instrumentation for Earthquakes.Nothing Exists Between Monitor Recording Time & CAV Methodology ML20090J9581992-03-12012 March 1992 Comment on Proposed Rule 10CFR51 Re Environ Review of Applications to Renew Operating Licenses for Nuclear Plants. Licensee Endorses NUMARC Comments ML20087F7221992-01-14014 January 1992 Comments on Draft Reg Guide DG-8005, Assessing External Doses from Airborne Radioactive Matls. Disagrees W/Statement That Airborne Concentration Measurements Unreliable ML20086R7431991-12-12012 December 1991 Comment on Draft Reg Guide DG-8006, Control of Access to High & Very High Radiation Areas in Nuclear Power Plants ML20246D8811989-06-30030 June 1989 Comment Supporting Proposed Rule 10CFR50, Acceptance of Products Purchased for Use in Nuclear Power Plant Structures,Sys & Components ML20235T7391989-02-23023 February 1989 Comment Opposing Proposed Rules 10CFR50 & 55 Re Educ & Experience Requirements for Senior Reactor Operators & Supervisors at Nuclear Power Plants ML20210B8061987-05-0101 May 1987 Order.* NRC 861020 Order Directing Licensee to Show Cause Why OL Should Not Be Modified to Prohibit Use of Radios,Tapes,Television Sets or Other Audible Entertainment Devices Recinded & Proceeding Dismissed.Served on 870501 ML20212N5501987-03-0606 March 1987 NRC Staff Explanation of Health & Safety Basis for Prohibition of Electronic Entertainment Devices in Nuclear Power Plant Control Rooms.* ML20212N5771987-03-0606 March 1987 Affidavit of Jm Taylor Re Health & Safety Basis for Staff Prohibition on Electronic Entertainment Devices in Control Rooms.* Certificate of Svc Encl ML20211D0291987-02-13013 February 1987 Order.* Staff Directed to File W/Commission & Serve on Petitioners & Licensees Detailed Explanation of Health & Safety Basis for 861020 Order Re Use of Audio Equipment in Control Rooms by 870306.Carr Views Encl.Served on 870217 ML20214C4131986-11-12012 November 1986 Affidavit of DE Gilberts Re Enforcement Action 86-164 & NRC 861022 Order to Show Cause Concerning Use of Radios in Control Rooms ML20215J1421986-10-20020 October 1986 Order to Show Cause Why Radios or Other Electrical/ Electronic Equipment Used to Provide Background Music in Control Rooms Should Not Be Removed (Ref IE Info Notice 85-053 & Circular 81-02) ML19332A0381980-09-0404 September 1980 Response in Opposition to State of Mn 800828 Motion to Hold Spent Fuel Pool Mod Proceeding in Abeyance Pending Mn Pollution Control Agency Board 800923 Meeting.Accepting Settlement During Meeting Very Remote.W/Certificate of Svc ML19331D8841980-08-28028 August 1980 Motion to Hold Proceedings in Abeyance Until 800923,when Mn Pollution Control Agency Will Act on Settlement. Settlement,If Adopted,Would Result in Withdrawal of Hearing Request ML19331D8861980-08-28028 August 1980 Affidavit Stating That Proposed Settlement Will Be Placed on Next Mn Pollution Control Agency Monthly Meeting Agenda or Considered at Special Meeting for Affirmative Majority Vote of Board Members ML19321B2701980-07-25025 July 1980 Responds to State of Mn 800424 Suppl to Petition to Intervene & 800721 Amended Contentions.Supporting Documentation,Notices of Appearance of Je Siberg & Dl Bernstein on Behalf of Util & Certificate of Svc Encl ML19321B0571980-07-21021 July 1980 Amended Contentions 1 & 2 & Withdrawal of Contention 3.Amend Request Does Not Contain Safety Analysis Re Spent Fuel Storage & Does Not Contain Analysis of Spent Fuel Pool Expansion Consequences.Certificate of Svc Encl ML19316A8941980-04-24024 April 1980 Suppl to 800408 Petition to Intervene Stating Contentions Alleging Absence of Safety Analysis in License Amend Request.Loss of Water in Spent Fuel Pool Is Not Analyzed in Application ML19309G1141980-04-17017 April 1980 Response in Opposition to State of Mn 800409 Request for Hearing & Petition to Intervene.No Rationale or Supporting Authorities Cited as Basis for Request Not to Issue Amend Until State Proceedings Are Completed.W/Certificate of Svc ML19305E1941980-03-31031 March 1980 Notice of Appearance in Proceeding ML19305E1761980-03-31031 March 1980 Request for Hearing and Petition to Intervene Re Spent Fuel Pool Mod.License Amend Should Not Be Issued Until State of Mn Administrative Proceedings Are Completed Re Licensee Application for Certificate of Need & Environ Evaluation ML19249D6901979-07-10010 July 1979 Requests That Decision in State of Mn Vs NRC Be Implemented. Holding Affirms ALAB-445 Decision Re Consideration of Storage of Radwaste During Licensing Proceedings 1999-06-30
[Table view] Category:PUBLIC COMMENTS ON PROPOSED RULES & PETITIONS FOR
MONTHYEARML20210E5881999-06-30030 June 1999 Comment Supporting Draft Reg Guide DG-1074, Steam Generator Tube Integrity. Northern States Power Endorses Comments Transmitted by NEI Ltr ML20199C2721997-10-27027 October 1997 Comment Supporting Proposed Rules 10CFR50 & 73, Proposed Amends to NRC Requirements for Emergency Preparedness & Security ML20138K1511997-05-0606 May 1997 Comment Supporting Proposed Rule 10CFR73 Re Changes to Nuclear Power Plant Security Requirements ML20117E4051996-08-0909 August 1996 Comment Supporting Proposed Rule 10CFR26 Re Fitness for Duty Rule ML20094J0471995-10-11011 October 1995 Comment on Proposed Rules 10CFR60,72,73 & 75 Re Safeguards for Spent Fuel or High Level Radwaste ML20085E5261995-06-0606 June 1995 Comment Supporting Proposed Rule 10CFR73 Re Changes to NPP Security Requirements Associated W/Containment Access Control ML20083K2731995-04-28028 April 1995 Comment on Proposed Rule 10CFR50 Re Primary Reactor Containment Leakage Testing for water-cooled Power Reactors. Urges NRC to Support Rev to NEI 94-01 Which Will Allow Use of Two Reduced Pressure Type a Tests as Prerequisites ML20077M6181994-12-30030 December 1994 Comment Re Proposed Rule 10CFR50 Re Low Power Operations for Np Reactors.Util Believes That Pr Will Have Higher Impact than Described in Regulatory Analysis,As Pr Will Extend Refueling Outages at All Plants ML20071H4161994-06-30030 June 1994 Comment Supporting Petition for Rulemaking PRM-20-23 Re Reduction of Radioactive Emission from 100 Mrems to 1 Mrem/Yr ML20062M4001993-12-30030 December 1993 Comment Supporting NUMARC Position on Proposed Rule 10CFR73 Re Protection Against Malevolent Use of Vehicles at NPPs ML20045G0941993-04-21021 April 1993 Comment on Proposed Rules 10CFR50,52 & 100 Re Nuclear Power Plant Instrumentation for Earthquakes.Nothing Exists Between Monitor Recording Time & CAV Methodology ML20090J9581992-03-12012 March 1992 Comment on Proposed Rule 10CFR51 Re Environ Review of Applications to Renew Operating Licenses for Nuclear Plants. Licensee Endorses NUMARC Comments ML20087F7221992-01-14014 January 1992 Comments on Draft Reg Guide DG-8005, Assessing External Doses from Airborne Radioactive Matls. Disagrees W/Statement That Airborne Concentration Measurements Unreliable ML20086R7431991-12-12012 December 1991 Comment on Draft Reg Guide DG-8006, Control of Access to High & Very High Radiation Areas in Nuclear Power Plants ML20246D8811989-06-30030 June 1989 Comment Supporting Proposed Rule 10CFR50, Acceptance of Products Purchased for Use in Nuclear Power Plant Structures,Sys & Components ML20235T7391989-02-23023 February 1989 Comment Opposing Proposed Rules 10CFR50 & 55 Re Educ & Experience Requirements for Senior Reactor Operators & Supervisors at Nuclear Power Plants 1999-06-30
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y 00CKETED Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East
'95 NOV 13 P3 :18 wen.unne ssoa9 0FFICE OF SECRETARY DOCKETING & SERVICE November 10, 1995 BRANCH DOCKET NUMBERnn PROPOSED RULE rlltn,a:,%76 i (Wa 4ao79')
Secretary U S Nuclear Re ulato Commission Washington, DC 20555-0001 Comments on Proposed Rule Changes - Safeguards for Spent Nuclear Fuel or ~
Hich-Level Radioactive Waste (60 FR 42079 of Aunust 15. 1995)
Northern States Power Company has reviewed the Federal Register notice of August 15, 1995 referenced above, and would like to offer comments as '
indicated in Attachment 1 to this letter.
If you have any questions, please direct them to David Axt at 612-388-1121 Extension 4880.
Michael D Wadley Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg Attachment 1 - Comments to the Nuclear Regulatory Commission from Northern States Power Company - November 10, 1995 9511150068 951011 PDR PR 60 60FR42079 PDR O pt
'- Attachment 1 Comments to the Nuclear Regulatory Commission from Northern States Power Company l November 10,1995
Subject:
Safeguards for Spent Nuclear Fuel or High-Level Radioactive ;
Waste (60 FR 42079 of August 15,1995)
Issue #1: No Credible Target-Threat Association for ISFSis When considering basic security risk assessment methodology, a target must be credible before it can linked to a corresponding threat. With regards to sabotage, a target is unattractive unless the sabotage act can produce undesired consequences.
For nuclear power plants, these undesired consequences are codified as a 10 CFR, Part 100 release, resulting from radiological sabotage. On the other hand, sabotage scenarios and consequence analyses commissioned by the NRC and other organizations, to date, conclude that a Part 100 release from an ISFSI dry cask system is highly improbable and quantitatively not feasible.
In the NRC's Part 72 Proposed Rule Making of May 31,1989 it does, however, state that:
l
. . . consequence modeling assumptions more severe. . .are possible if l unconstrained sabotage resources or protracted loss of control of the storage site are allowed.
Such an act, however, would require an enormous amount of time, tools, equipment .
and several saboteurs. Even if such a scenario were successfully carried out, the saboteur would still not achieve a Part 100 release. It is therefore reasonable to conclude that ISFSI casks should be afforded protection commensurate with the target sabotage consequences and threat (or lack thereof).
According to a former Sandia National Laboratories employee, who personally oversaw penetration tests of dry casks, there are two plausible sabotage scenarios which could breach an ISFSi cask (given unconstrained sabotage resources and a protracted time period). One scenario involves explosives; however, the particular explosive package is:
- Extremely difficult to set-up
. Would take a combined total of approximately 130 lbs of explosives & projectile
. Must be positioned, leveled and aimed precisely
. Must be fired from the optimum distance
. Will miss a target the size of a standard cask about 80% of the time in the second scenario,' the saboteur would need a specific type of military oxygen torch. This particular torch system is, however, accessible only to a distinct military -
organization, and it would require the saboteur to be exposed to the potential radiological release as well as the tremendous heat given off by the oxygen torch.
Nonetheless, the saboteur in both scenarios would still not achieve a Part 100 release.
lasue #2: Use of Deadly Force Contradiction 1 Security Officers are justified in using deadly force in order to protect the public against - 1 radiological sabotage (Part 100 release) by the design basis threat. This is justifiable.
There is linkage between sabotage consequences and potential threats. On the other l hand, NRC doctrine (verbally communicated) is that security personnel are not required l to use deadly force in protecting an ISFSI cask. This would seem to indicate a Part l 100 release - the basis for 10 CFR Part 73 security criteria - is not feasible by sabotaging an ISFSI cask. This contradiction, in and of itself, would indicate that the application of Part 73 level security is duplicitous and indeed excessive.
Issue #3: NRC Security inspection Burden NRC inspection efforts for nuclear reactor sites are manpower intensive. If ISFSI security licensing criteria parallel a nuclear site (10 CFR Part 73) then, from an inspection standpoint, the licensing of an off-site ISFSI or an ISFSI in the owner controlled area (OCA) is analogous to creating several new nuclear power plants. Like most of the private sector, the NRC faces manpower cut-backs and shrinking resources. Notwithstanding the rational of Issues 1 and 2 above, how then will the NRC handle the increased inspection efforts imposed by the additional ISFSis?
Summary The absence of a credible target-threat combination for ISFSI dry cask systems ignores basic fundamental vulnerability assessment rationale. The proposed amendments to part 73.51 which specify safeguard requirements for ISFSis are categorically excessive. Dry casks cannot realistically be stolen, maligned or sabotaged in any way which would produce a 10 CFR Part 100 release. The' correlation of reactor and ISFSI site security criteria is baseless and would therefore result in unnecessary licensee expenditures, j
\
Responses to Specific Proposed Rule Questions l l
l
- 1. Would the proposed amendments impose any signi6 cant additional costs for I
safeguards of currently stored spent nuclear fuel beyond what is now incurred for that purpose?
Response: Yes. For ISFSis located outside of a licensee's owner controlled area i (OCA), the licensee would need to provide two (2) watchpersons around the clock.
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a . ;
O i
This is approximately 20,000 man-hours a year. Depending on the LLEA agreement, l the licensee may also need to provide a dedicated response force which is appendix .
"B" trained and certified. j l
- 2. Is there reason to expect the costs to future licensees to differ substantially from those of currentlicensees?
Response: Yes, for those facilities which might be required to re-locate their ISFSis to outside their OCA. The costs would increase for reasons stated in question #1 above.
- 3. NIA.
4.- Are the costsjustified by the benefits that would be afforded by the proposed amendments? Are there althmatives that would afford essentially the same benefits, but be more cost effective?
Response: No, the costs are not justified; the benefits are excessive and unnecessary l for those reasons stated in issues 1,2 & 3, above. Yes. One alternative would require l that the NRC: (1) not lump all spent nuclear fuel storage facilities together, mandating l' one blanket set of security criteria, (2) develop physical protection criteria which is tailored for the threat-target combination. For dry cask storage facilities, see the attached recommended ISFSI Physical Protection Alternatives.
- 5. NIA.
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i l
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Attachment 1a ISFSI Physical Protection Alternatives EW 7 51 REQUIREMENT' * - * '
e >
- 1. Two physical barriers: Two physical barriers: perimeter, The level of protection offered by pmtected area perimeter fence, nuisance fence with posted "No a protected area and isolation defined by 73.2, with isolation Trespassing" signs, with locked zone perimeter fence does not zone & the cask itself as second access. correspond with the target-threat barrier combination; the protection it does provide is negligible
- 2. Illumination around protected illumination just around the casks same as above area perimeter (along with intrusion detection &
CCTV)
- 3. Complete protected area see above same as above i
perimeter intrusion detection system
- 4. Random patrols not less than Random patrols only by LLEA or With CCTV and detection system every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> authorized security personnel. directly enveloping the casks, and no credible threat, deterrence value of patrols is negligible
- 5. Security organization; two No dedicated secunty organization Target-threat combination does watchpersons per shift for required, other than random not support costs associated with a monitoring detection equipment patrols or other security personnel. dedicated security organization S. Documented liaison with None N/A designated response force or LLEA
- 7. Specified screening before None lN/A granting unescorted access l
- 8. Controlled ID & lock system None lN/A
- 9. Escorted individuals under None lN/A constant escort l
- 10. Redundant communications Not necessary. Target-threat combination does between security organization not support costs
& designated response force or LLEA
- 11. Searches of all hand-carried Not necessary With CCTV and detection system packages and vehicles directly enveloping the casks, and no credible threat, deterrence value of perimeter search is negligible
- 12. Written response procedures No safeguards response Target-threat combination for unauthorized penetration - procedures necessary, incongruent with Appendix C to
- including contingencies part 73 covered in App.C to part 73
- 13. All detection and surveillance None N/A systems must be tamper-indicating with line supervision - with comp measures when necessary
- 14. Security program review At discretion of licensee Security program not sufficient every 24 months scope or importance to mandate program review frequency
- 15. All documentation retained for At discretion of licensee l Paperwork reduction. Not 3 years l necessary