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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20148M6511997-06-18018 June 1997
Comment Opposing Proposed Suppl to Bulletin 96-001 That Would Request Licensees to Take Action to Ensure Continued Operability of Control Rods
L-95-045, Comment on Proposed Rules 10CFR2,50 & 51 Re Decommissioning of Nuclear Power Reactors1995-10-19019 October 1995
Comment on Proposed Rules 10CFR2,50 & 51 Re Decommissioning of Nuclear Power Reactors
ML20080M1121995-02-27027 February 1995
Comment Re Proposed Suppl 5 to GL 88-20 IPEEE for Severe Accident Vulnerabilities. Proposed GL Suppl Should Indicate That Licensees Can Use Llnl Hazard Results of NUREG-1488 Re Revised Hazard Estimates Instead of NUREG/CR-5250
ML20073M0751994-09-23023 September 1994
Comment on Proposed Rules 10CFR30,40,70 & 72 Re Clarification of Decommissioning Funding Requirements. Permitting Access to Funds Only on Semiannual Basis Seems Unnecessarily Restrictive
ML20069L5291994-06-13013 June 1994
Comment Supporting Proposed Rulemaking 50-60 Re Petition for Rulemaking & Changes to 10CFR50.54
ML20029D8251994-04-29029 April 1994
Comment Supporting Elimination of Proposed 5-yr Implementation Schedule & Believes That Current Programs Adequate to Maintain Containment Integrity
ML20044G1971993-05-24024 May 1993
Comment Supporting Draft Insp Procedure Re Commercial Grade Procurement & Dedication
ML20044E5721993-05-19019 May 1993
Comment Supporting Proposed Generic Ltr for Relocation of TS Tables on Instrument Response Time Limits
ML20044D3271993-05-0707 May 1993
Comment Opposing Proposed GL Availability & Adequacy of Design Bases Info
ML20125B6141992-12-0303 December 1992
Exemption from Requirements of 10CFR50,app a Re GDC-2 & 10CFR50.49 Re Environ Qualification of Electric Equipment Important to Safety for Nuclear Power Plants
ML20095J6881992-04-23023 April 1992
Comment Opposing Draft Reg Guide DG-1022, Emergency Planning & Preparedness for Nuclear Power Plants
ML20077R5161991-08-14014 August 1991
Comment Supporting Petition for Rulemaking PRM-20-20 Re Reduced Total Effective Dose Equivalent to Individual Members of Public from 0.5 Rem (5 Msv) to 0.1 Rem (1 Msv)
ML20235N8531989-02-14014 February 1989
Comment Supporting Chapter 1 Re Policy Statement on Exemptions Below Regulatory Concern.Policy Development for Criteria for Release of Radioactive Matl Needed for Development of Consistent Waste Mgt Practices
ML20235P3311989-02-0808 February 1989
Comment Opposing Proposed Rules 10CFR50 & 55 Re Educ & Experience Requirements for Senior Reactor Operators & Supervisors at Nuclear Power Plants
ML20236P5851987-11-0909 November 1987
Transcript of 871109 Briefing in Washington,Dc Re Facility Steam Generator Tube Rupture Event.Pp 1-56.Supporting Documentation Encl
ML20138N5311985-11-0101 November 1985
Memorandum & Order Affirming ASLB 850903 Initial Decision Authorizing Director of NRR to Issue License Amend for North Anna to Permit Receipt & Storage of 500 Spent Fuel Assemblies from Surry Power Station.Served on 851101
ML20133K7171985-10-18018 October 1985
Notice of Withdrawal of Appearance in Proceeding.Certificate of Svc Encl
ML20133K6801985-10-18018 October 1985
Forwards Notice of Withdrawal of Appearance in Proceeding. Requests Svc List Be Revised to Include Client Under Listed Address.W/O Encl
ML20133F4241985-10-0909 October 1985
Order Stating That ASLB 850903 Initial Decision Authorizing NRR to Amend OL to Permit Receipt & Storage of Spent Fuel Should Not Be Deemed Final,Pending Further Order. Served on 851009
ML20138A9521985-10-0909 October 1985
Notice of Withdrawal of Appearance in Proceeding.Certificate of Svc Encl
ML20134N6981985-09-0303 September 1985
Initial Decision LBP-85-34 Authorizing NRR to Issue Amends to Licenses NPF-4 & NPF-7 to Permit Receipt & Storage of 500 Spent Fuel Assemblies from Surry.Initial Decision Effective Immediately.Served on 850904
ML20134N4381985-09-0303 September 1985
Order Granting Licensee 850621 Request to Correct Transcript.Proposed Transcript Corrections & Certificate of Svc Encl.Served on 850904
ML20129K1251985-07-18018 July 1985
Brief in Support of NRC 850718 Proposed Findings of Fact & Conclusions of Law in Form of Initial Decision Authorizing Issuance of Amend to Licenses NPF-4 & NPF-7 to Permit Receipt & Storage of 500 Spent Fuel Assemblies
ML20129K1281985-07-18018 July 1985
Proposed Findings of Fact & Conclusions of Law in Form of Initial Decision Authorizing NRR to Issue Amend to Licenses NPF-4 & NPF-7 to Permit Receipt & Storage of 500 Spent Fuel Assemblies
ML20129F8231985-07-12012 July 1985
Reply Opposing Concerned Citizens of Louisa County post- Hearing Brief.Licensee Proposed Findings of Sabotage & Human Error Not Addressed.Challenge of NRC EIS Conclusion Unnecessary.Certificate of Svc Encl
ML20209F0021985-07-0808 July 1985
Post-hearing Brief Re Issues Raised at ASLB 850521 & 22 Evidentiary Hearings.Nrc Required by NEPA to Evaluate Alternative of Constructing & Operating Dry Cask Storage Facility,But Failed to Perform Even Cursory Review
ML20209F2041985-07-0808 July 1985
Proposed Findings of Fact & Conclusions of Law Re Application for Amend to Ol,Authorizing Licensee to Ship 500 Spent Nuclear Fuel Assemblies from Surry Power Station to North Anna Station.Certificate of Svc Encl
ML20128H0791985-07-0808 July 1985
Order Granting Concerned Citizens of Louisa County 850627 Motion for 7-day Extension Until 850708 to File Proposed Findings of Fact & Conclusions of Law.Served on 850708
ML20128G9471985-06-27027 June 1985
Motion for Extension of 850701 Deadline to File Proposed Findings of Fact & Conclusions of Law.Addl Wk Required Due to Addl Legal Duties.Certificate of Svc Encl
ML20127F0511985-06-21021 June 1985
Proposed Findings of Fact & Conclusions of Law Re Util 820713 Application to Amend Ol,Authorizing Receipt & Storage of Up to 500 Spent Nuclear Fuel Assemblies.Unsigned,Undated Order & Certificate of Svc Encl
ML20127F0451985-06-21021 June 1985
Post-hearing Brief Requesting Board Find in Util Favor Re Proposed OL Amend Authorizing Receipt & Storage of Up to 500 Spent Nuclear Fuel Assemblies.No Basis from Sabotage or Human Error Considerations for Denying Proposed Amend
ML20128A7731985-05-22022 May 1985
Transcript of 850522 Hearing in Charlottesville,Va.Pp 313-364.Supporting Documentation Encl
ML20125C4081985-05-21021 May 1985
Applicant Exhibit A-H-11,consisting of Undated,Untitled Photograph H
ML20125C3601985-05-21021 May 1985
Applicant Exhibit A-B-5,consisting of Undated,Untitled Photograph B
ML20125C4221985-05-21021 May 1985
Applicant Exhibit A-J-13,consisting of Undated,Untitled Photograph J
ML20125C3471985-05-21021 May 1985
Applicant Exhibit A-3,consisting of SAND82-2365, Assessment of Safety of Spent Fuel Transportation in Urban Environs, Dtd June 1983
ML20125C4301985-05-21021 May 1985
Applicant Exhibit A-K-14,consisting of Undated,Untitled Photograph K
ML20125C3941985-05-21021 May 1985
Applicant Exhibit A-F-9,consisting of Undated,Untitled Photograph F
ML20125C4361985-05-21021 May 1985
Applicant Exhibit A-L-15,consisting of Undated,Untitled Photograph L
ML20125C3101985-05-21021 May 1985
Staff Exhibit S-1,consisting of Undated Environ Assessment & Finding of Proposed No Significant Impact Re 820713 & 0820 Applications for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,allowing Receipt & Increased Storage of Spent Fuel
ML20125C3411985-05-21021 May 1985
Applicant Exhibit A-2,consisting of 830915 Procedure 1-OP-4.19, Receipt & Storage of Spent Fuel TN-8L Shipping Cask Unloading & Handling Procedures
ML20125C3291985-05-21021 May 1985
Staff Exhibit S-3,consisting of Forwarding NMSS Apr 1985 Environ Assessment Re 821008 Application for Authority to Construct & Operate Dry Cask ISFSI at Surry Power Station
ML20125C4001985-05-21021 May 1985
Applicant Exhibit A-G-10,consisting of Undated,Untitled Photograph G
ML20125C3381985-05-21021 May 1985
Applicant Exhibit A-1,consisting of 831104 Procedure OP-4.3, Shipping of Spent Fuel TN-8L Shipping Cask Loading & Handling Procedures, for Surry Power Station
ML20125C3711985-05-21021 May 1985
Applicant Exhibit A-C-6,consisting of Undated,Untitled Photograph C
ML20125C3791985-05-21021 May 1985
Applicant Exhibit A-D-7,consisting of Undated,Untitled Photograph D
ML20125C3821985-05-21021 May 1985
Applicant Exhibit A-E-8,consisting of Undated,Untitled Photograph E
ML20125C3501985-05-21021 May 1985
Applicant Exhibit A-A-4,consisting of Undated,Untitled Photograph a
ML20125C3191985-05-21021 May 1985
Staff Exhibit S-2,consisting of Undated Safety Evaluation Re Increasing Spent Fuel Storage Capacity.Proposed Mods to Spent Fuel Pool & Transshipment/Storage of Spent Fuel Acceptable
ML20125C4131985-05-21021 May 1985
Applicant Exhibit A-I-12,consisting of Undated,Untitled Photograph I
1997-06-18
[Table view]
Category:PUBLIC COMMENTS ON PROPOSED RULES & PETITIONS FOR
MONTHYEARML20148M6511997-06-18018 June 1997
Comment Opposing Proposed Suppl to Bulletin 96-001 That Would Request Licensees to Take Action to Ensure Continued Operability of Control Rods
L-95-045, Comment on Proposed Rules 10CFR2,50 & 51 Re Decommissioning of Nuclear Power Reactors1995-10-19019 October 1995
Comment on Proposed Rules 10CFR2,50 & 51 Re Decommissioning of Nuclear Power Reactors
ML20080M1121995-02-27027 February 1995
Comment Re Proposed Suppl 5 to GL 88-20 IPEEE for Severe Accident Vulnerabilities. Proposed GL Suppl Should Indicate That Licensees Can Use Llnl Hazard Results of NUREG-1488 Re Revised Hazard Estimates Instead of NUREG/CR-5250
ML20073M0751994-09-23023 September 1994
Comment on Proposed Rules 10CFR30,40,70 & 72 Re Clarification of Decommissioning Funding Requirements. Permitting Access to Funds Only on Semiannual Basis Seems Unnecessarily Restrictive
ML20069L5291994-06-13013 June 1994
Comment Supporting Proposed Rulemaking 50-60 Re Petition for Rulemaking & Changes to 10CFR50.54
ML20029D8251994-04-29029 April 1994
Comment Supporting Elimination of Proposed 5-yr Implementation Schedule & Believes That Current Programs Adequate to Maintain Containment Integrity
ML20044G1971993-05-24024 May 1993
Comment Supporting Draft Insp Procedure Re Commercial Grade Procurement & Dedication
ML20044E5721993-05-19019 May 1993
Comment Supporting Proposed Generic Ltr for Relocation of TS Tables on Instrument Response Time Limits
ML20044D3271993-05-0707 May 1993
Comment Opposing Proposed GL Availability & Adequacy of Design Bases Info
ML20095J6881992-04-23023 April 1992
Comment Opposing Draft Reg Guide DG-1022, Emergency Planning & Preparedness for Nuclear Power Plants
ML20077R5161991-08-14014 August 1991
Comment Supporting Petition for Rulemaking PRM-20-20 Re Reduced Total Effective Dose Equivalent to Individual Members of Public from 0.5 Rem (5 Msv) to 0.1 Rem (1 Msv)
ML20235N8531989-02-14014 February 1989
Comment Supporting Chapter 1 Re Policy Statement on Exemptions Below Regulatory Concern.Policy Development for Criteria for Release of Radioactive Matl Needed for Development of Consistent Waste Mgt Practices
ML20235P3311989-02-0808 February 1989
Comment Opposing Proposed Rules 10CFR50 & 55 Re Educ & Experience Requirements for Senior Reactor Operators & Supervisors at Nuclear Power Plants
1997-06-18
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'94 MAY -6 P 2 :4I VIRGINIA POWER OFFiCEOFSE(RM'"k-00CKEilM ^
April 29, 1994 BRirhUll Secretary of the Commission Serial No.94-051 l U.S. Nuclear Regulatory Commission NL&P/GSS R0 Attn: Docketing and Service Branch Washington, D.C. 20555 Gentlemen:
COMMENTS ON PROPOSED RULE CODES AND STANDARDS l SUBSECTIONS IWE AND IWL l in the January 7,1994 Federal Register, the NRC requested comments on the proposed rule to amend its regulations to incorporate the 1992 Edition of the ASME Code with the 1992 Addenda of Subsections IWE, " Requirements for Class MC and Metallic Liners for Class CC Components of Light-Water Cooleo Power Plants" and IWL, Requirements for Class CC Concrete Components of Light-Water Cooled Power Plants." The purpose of the proposed rule is to specify inspection requirements to ensure that containments maintain minimum accepted design wall thicknesses and prestressing forces.
We strongly support the elimination of the proposed five year implementation schedule and feel that the current programs are adequate to maintain containment integrity. Additionally, we endorse the comments sent separately to the NRC by the Nuclear Energy Institute and offer thn attached comments associated with the implementation of Subsections IWE arid IWL. Please note that there are several areas identified where the implementatiori of the code will be impractical. The resolution of these areas should be part of the rulemaking.
We appreciate the opportunity to make comments on the proposed rule, if you l have any questions, please contact us. j l
Very truly yours, ;
f Ymj 1 l
M. L. Bowling, Manager l Nuclear Licensing and Programs j 9405100158 940429 PDR PR 50 59FR979 PDR flb i J
cc: Mr. Ron Simard Manager, industry Coordinator Nuclear Energy Institute 1776 Eye Street Suite 300 Washington, D. C. 20006-3706
9 CODES AND STANDARDS FOR NUCLEAR POWER PLANTS SUBSECTIONS IWE AND IWL PROPOSED RULE The following comments are associated with the implementation of Subsections IWE and IWL. As indicated, the differences between the code requirements and the existing programs would make implementation complicated. It is recommended that thece areas be taken into consideration and resolved prior to the issuance of the proposed rule.
- 1. Subsection IWL is initiated with the structural integrity test in lieu of the commercial operation date. This means IWL would have a different interval than the rest of the code. Additionally, the rulemaking does not address when the utility is to update the IWL code.
- 2. Section IWL-2310(b) requires VT-3C visual examinations to be conducted. The purpose is to determine the general structural condition of the concrete surfaces of containment by identifying areas of concrete deterioration and distress. The acceptance criteria includes the ability to locate a discrepancy of a lower case character height of approximately 1/10". Th'is criteria is considered impractical for all the containment concrete. It is recommended that the general visual examinations described in IWE be considered.
- 3. Section IWL-2310 requires the qualification for concrete examination personnel (VT-1C and VT-30) in accordance with IWA-2300. However, there are no industry Level lil's for VT-1C and VT-3C.
- 4. The rulemaking indicates that licensees are not to submit plans. It is recommended that the rulemaking provide guidance for the processing of relief requests and when they should be implemented.
- 5. The rulemaking indicates that the requirements of IWE and IWL are necessary to provide detailed visual examinations. These requirements are currently provided by Appendix J. If the requirements of Subsections IWE and IWL are imposed, then the visual examination requirements in Appendix J should be deleted.
- 6. Category E-D, note 1 in the 1993 Addenda of IWE adds a statement to coincide the inspection of seals and gaskets with component disassembly. It is recommended that the rulemaking teference this addenda.
- 7. iWE-5240 and IWE-5210 seems to mandate VT-2 examination requirements for Appendix J tests. It is recommended that this area be evaluated to determine if this was the intent of the code to require the qualification of Appendix J personnel.
