|
|
Line 49: |
Line 49: |
| { apply to the Commission for such an exemption and shall specify the reasons | | { apply to the Commission for such an exemption and shall specify the reasons |
| ; for the relief requested. | | ; for the relief requested. |
| By letter dated February 4,1997, as supplemented March 19, 1997, Duke Power Company requested an exemption for its two nuclear plants from the | | By {{letter dated|date=February 4, 1997|text=letter dated February 4,1997}}, as supplemented March 19, 1997, Duke Power Company requested an exemption for its two nuclear plants from the |
| { requirements of 10 CFR 70.24. The staff has reviewed the submittal in regard to Catawba, and documented its detailed review in a Safety Evaluation. The t | | { requirements of 10 CFR 70.24. The staff has reviewed the submittal in regard to Catawba, and documented its detailed review in a Safety Evaluation. The t |
|
| |
|
|
---|
Category:GRANTS OF EXEMPTION FROM & EXTENSION TO NRC REQUIREME
MONTHYEARML20149K8221997-07-29029 July 1997 Exemption from Requirements of 10CFR70.24, Criticality Accident Requirements. Exemption Granted 1997-07-29
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20197J2871998-12-11011 December 1998 Initial Decision (Application for Senior Reactor Operator License).* Appeal of R Herring of NRC Denial of Application for SRO License Denied.With Certificate of Svc.Served on 981211 ML20151W5721998-09-11011 September 1998 NRC Staff Presentation in Support of Denial of Senior Reactor Operator License for Dl Herring.* Staff Decision to Fail Dl Herring on Category a of SRO Exam,Clearly Justified. Staff Denial of Herring SRO License Should Be Sustained ML20151W5941998-09-11011 September 1998 Affidavit of Cd Payne.* Affidavit Re NRC Staff Proposed Denial of Rl Herring Application for Senior Reactor Operator License for Use at Catawba Nuclear Station,Units 1 & 2 ML20151Y0601998-09-11011 September 1998 Affidavit of DC Payne.* Supports Denial of Application of Rl Herring for SRO License ML20151W6131998-09-0808 September 1998 Affidavit of Mn Leach in Support of NRC Staff Response to Rl Herring Written Presentation.* ML20151W6311998-09-0808 September 1998 Affidavit of ET Beadle.* Affidavit Relates to Denial of Senior Reactor Operator License Application for Rl Herring. with Certificate of Svc ML20237B6931998-08-13013 August 1998 Rl Herring (Denial of Operator License for Plant).* Rl Herring Submitted Written Presentation Arguments,Data, Info Matl & Other Supporting Evidence,Per Presiding Officer 980630 Order & 10CFR2.1233.W/one Oversize Drawing ML20237A3831998-08-12012 August 1998 NRC Staff Request for Extension of Time to File Response to Rl Herring Written Presentation.* Staff Respectfully Requests Motion for Extension of Time of 2 Wks to Respond to Herring Presentation Be Granted.W/Certificate of Svc ML20237B5571998-08-12012 August 1998 NRC Staff Request for Extension of Time to File Response to Rl Herring Written Presentation.* Granted by C Bechhoefer on 980818.W/Certificate of Svc.Served on 980818 ML20236T8511998-07-21021 July 1998 Specification of Claims.* Rl Herring Claims That Answer Given on Exam Was Correct When TSs Are Considered & When Design Basis Document Considered in Conjunction W/Duke Power Nuclear Sys Div.W/Certificate of Svc.Served on 980727 ML20236F5391998-06-30030 June 1998 Memorandum & Order (Hearing File & Spec of Claim).* Orders That Brief Spec of Claims Should Be Filed by Herring,Telling Why He Believes Staff Erred in Grading Exam.Staff Must Furnish Hearing File.W/Certificate of Svc.Served on 980630 ML20236F5631998-06-30030 June 1998 Notice of Hearing.* Presiding Officer Has Granted Request of Rl Herring for Hearing on NRC Denial of Application for Operator License for Plant.W/Certificate of Svc.Served on 980630 ML20149K8221997-07-29029 July 1997 Exemption from Requirements of 10CFR70.24, Criticality Accident Requirements. Exemption Granted TXX-9522, Comment Opposing Proposed GL on Testing of safety-related Logic Circuits.Believes That Complete Technical Review of All Surveillance Procedures Would Be Expensive & Unnecessary Expenditure of Licensee Resources1995-08-26026 August 1995 Comment Opposing Proposed GL on Testing of safety-related Logic Circuits.Believes That Complete Technical Review of All Surveillance Procedures Would Be Expensive & Unnecessary Expenditure of Licensee Resources ML20065P4491994-04-21021 April 1994 Comment Opposing Proposed Rule 10CFR50.55 Recommendation to Incorporate Proposed Rule to Adopt ASME Code Subsections IWE & Iwl ML20044G7371993-05-25025 May 1993 Comment on Proposed Rules 10CFR170 & 171, FY91 & 92 Proposed Rule Implementing Us Court of Appeals Decision & Rev of Fee Schedules;100% Fee Recovery,FY93. Opposes Rule ML20101R5931992-07-0606 July 1992 Comment on Proposed Rule 10CFR50 Re Loss of All Alternating Current Power & Draft Reg Guide 1.9,task DG-1021.Opposes Rule ML20091Q8661992-01-31031 January 1992 Comment Opposing Draft NUREG-1022,Rev 1, Event Reporting Sys,10CFR50.72 & 50.73,Clarification of NRC Sys & Guidelines for Reporting ML20087F7471992-01-15015 January 1992 Comment Opposing Rev 1 of NUREG-1022, Event Reporting Sys ML20246J6571989-08-31031 August 1989 Order Imposing Civil Monetary Penalty on Licensee in Amount of $75,000 for Violations Noted in Insp on 881127-890204. Payment of Civil Penalty Requested within 30 Days of Order Date.Evaluations & Conclusions Encl ML20247J8921989-08-31031 August 1989 Order Imposing Civil Monetary Penalty in Amount of $75,000, Based on Violations Noted in Insp on 881127-890204,including Operation in Modes 1-4 W/One Independent Containment Air Return & Hydrogen Skimmer Sys Inoperable for 42 Days ML20205N1471988-10-20020 October 1988 Comment on Petition for Rulemaking PRM-50-50 Re Provision That Authorizes Nuclear Power Plant Operators to Deviate from Tech Specs During Emergency.Request by C Young Should Be Denied ML20234D2821987-09-15015 September 1987 Joint Intervenors Emergency Motion to Continue Hearing for 2 Wks & for Immediate Prehearing Conference.* Urges That Hearing Re Offsite Emergency Planning at Plant,Scheduled for 870928,be Continued Until 871013.Certificate of Svc Encl ML20198C5771986-05-14014 May 1986 Transcript of 860514 Discussion/Possible Vote on Full Power OL for Catawba 2 in Washington,Dc.Pp 1-86.Viewgraphs Encl ML20203N4561986-02-20020 February 1986 Unexecuted Amend 6 to Indemnity Agreement B-100,replacing Item 3 of Attachment to Agreement W/Listed Info ML20151P2231985-12-31031 December 1985 Order Extending Time Until 860110 for Commissioners to Review ALAB-825.Served on 851231 ML20136H7231985-11-21021 November 1985 Decision ALAB-825,affirming Remaining Part of ASLB OL Authorization,Permitting Applicant to Receive & Store Spent Fuel Generated at Duke Power Co Oconee & McGuire Nuclear Power Facilities.Served on 851121 ML20138B3611985-10-11011 October 1985 Order Extending Time Until 851025 for Commission to Act to Review ALAB-813.Served on 851011 ML20137W4311985-10-0202 October 1985 Order Extending Time Until 851011 for Commission to Act to Review ALAB-813.Served on 851003 ML20134N5761985-09-0404 September 1985 Order Extending Time Until 851004 for Commission to Act to Review ALAB-813.Served on 850904 ML20126M2091985-07-30030 July 1985 Order Amending First Paragraph of Footnote 126 Re Need for Power & Financial Qualifications in ALAB-813 . Served on 850731 ML20126K7701985-07-26026 July 1985 Order Extending Time Until 850730 for Commission to Act to Review Director'S Decision DD-85-9.Served on 850729 ML20129C2351985-07-26026 July 1985 Decision ALAB-813 Affirming Aslab Authorization of Issuance of Full Power Ol,Except Insofar as Receipt & Storage Onsite of Spent Fuel Generated at Other Facilities.Served on 850729 ML20129K1651985-07-19019 July 1985 Order Extending Time Until 850726 for Commission to Act to Review Director'S Decision DD-85-9.Served on 850719 ML20129H9361985-07-10010 July 1985 Unexecuted Amend 5 to Indemnity Agreement B-100,changing Items 1 & 3 of Attachment ML20128K2171985-07-0808 July 1985 Order Extending Time Until 850719 for Commission to Act to Review Director'S Decision DD-85-9.Served on 850709 ML20127P0991985-06-28028 June 1985 Transcript of 850628 Supplemental Oral Argument in Bethesda, Md.Pg 99-169 ML20133C5201985-06-26026 June 1985 Undated Testimony of PM Reep Re Welding Inspector Concerns. Rept of Verbal Harassment Encl ML20127K7171985-06-24024 June 1985 Order Extending Time Until 850709 for Commission to Act to Review Director'S Decision DD-85-9 ML20126K6391985-06-17017 June 1985 Order Advising That Counsel Be Familiar W/Content of Commission Request for Public Comment on Decision to Exercise Discretionary Price-Anderson Act Authority to Extend Govt Indemnity to Spent.... Served on 850618 ML20126B8101985-06-13013 June 1985 Order Scheduling Supplemental Oral Argument on Pending Appeals on 850628 in Bethesda,Md Re Public Notice of Hearing Concerning Use of Facility for Receipt & Storage of Spent Fuel from Oconee & Mcguire.Served on 850613 ML20126E4601985-06-13013 June 1985 Notice of Supplemental Oral Argument on Pending Appeals on 850628 in Bethesda,Md.Served on 850613 ML20125B4251985-06-0707 June 1985 Responds to Aslab 850603 Order Requesting Response to NRC 850529 Filing Re Whether Notice of Proposal to Use Catawba to Store Oconee & McGuire Spent Fuel Discretionary or Required.Certificate of Svc Encl ML20126A7631985-06-0404 June 1985 Director'S Decision DD-85-9 Granting & Denying in Part Palmetto Alliance Request for Mod,Suspension or Revocation of CPs for Facilities Due to Harassment & Intimidation of QC Inspectors ML20129A6381985-06-0303 June 1985 Order Allowing Applicant to File & Serve Response to NRC 850529 Assertion Re Storage of Spent Fuel Generated at Another Facility Constituting Use of Commercial Utilization Facility No Later than 850607.Served on 850604 ML20128P0001985-05-29029 May 1985 NRC Views on Whether Notice of Proposal to Use Facility to Store Oconee & McGuire Spent Fuel Required or Discretionary. Certificate of Svc Encl ML20128P1031985-05-29029 May 1985 Memorandum Responding to Palmetto Alliance/Carolina Environ Study Group & Staff 850517 Memoranda Asserting That Fr Notice Not Reasonably Calculated to Inform of Requests Re Spent Fuel.Certificate of Svc Encl ML20127K0231985-05-20020 May 1985 Order Extending Time Until 850529 for Aslab to Act to File & Svc Reply Memoranda.Served on 850521 ML20127G2281985-05-17017 May 1985 Memorandum Responding to 850425 Aslab Order Addressing Four Questions Re Receipt & Storage of Spent Fuel.Certificate of Svc Encl ML20127H0041985-05-17017 May 1985 Response to Aslab Questions on Adequacy of Notice of Proposed Use of Facility to Store Spent Fuel from Oconee & McGuire Facilities.Aslab Has No Jurisdiction Over Proposal. Certificate of Svc Encl 1998-09-08
[Table view] |
Text
. - - _ .-
1 l
7590-01-P l
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
)
DUKE POWER COMPANY, ET AL. ) Docket Nos. 50-413 and 50-414
) I (Catawba Nuclear Station, )
Units 1 and 2) )
EXEMPTION J
I.
The Duke Power Company, et al. (the licensee) is the holder of Facility Operating License Nos. NPF-35 and NPF-52, for the Catawba Nuclear Station, Units 1 and 2. The licenses provide, among other things, that the licensee is subject to all rules, regulations, and orders of the Commission now or hereafter in effect.
l These facilities consist of two pressurized water reactors located at the licensee's site in York County, South Carolina.
II.
Title 10 of the Code of Federal Reaulations (10 CFR) at subsection (a) of 10 CFR 70.24, " Criticality Accident Requirements," requires that each licensee authorized to possess special nuclear material shall maintain in each area where such material is handled, used, or stored, a criticality accident monitoring system "using gamma- or neutron-sensitive radiation detectors which will energize clearly audible alarm signals if accidental criticality occurs."
Subsections (a)(1) and (a)(2) of 10 CFR 70.24 specify the detection,
'. 9707300172 970729 PDR ADOCK 05000413 P PDR
i sensitivity, and coverage capabilities of the monitors required by 10 CFR 70.24(a). Subsection (a)(3) of 10 CFR 70.24 requires that the licensee shall 4
maintain emergency procedures for each area in which this licensed special nuclear material is handled, used, or stored and provides (1) that'the ,
j procedures ensure that all personnel withdraw to an area of safety upon the sounding of a criticality monitor alarm, (2) that the procedures must include f drills to familiarize personnel with the evacuation plan, and (3) that the procedures designate responsible individuals for determining the cause of the i alarm and placement of radiation survey instruments in accessible locations !
j for use in such an emergency. Subsection (b)(1) requires licensees to have a i s 1
- means to quickly identify personnel who have received a dose of 10 rads or l 1
more. Subsection (b)(2) requires licensees to maintain personnel l
- decontamination facilities, to maintain arrangements for a physician and other l l
medical personnel qualified to handle radiation emergencies, and to maintain arrangements for the transportation of contaminated individuals to treatment i
facilities outside the site boundary. Subsection (c) exempts Part 50 !
l licensees (such as Catawba) from the requirements of paragraph (b).
! Subsection (d) states that any licensee who believes that there is good cause l why he should be granted an exemption from all or part of 10 CFR 70.24 may
{ apply to the Commission for such an exemption and shall specify the reasons
- for the relief requested.
By letter dated February 4,1997, as supplemented March 19, 1997, Duke Power Company requested an exemption for its two nuclear plants from the
{ requirements of 10 CFR 70.24. The staff has reviewed the submittal in regard to Catawba, and documented its detailed review in a Safety Evaluation. The t
i l
i staff found that Catawba's existing procedures and design features make an l
inadvertent criticality in special nuclear materials handling or storage at Catawba unlikely. The licensee has thus met the intent of 10 CFR 70.24(a)(1),
(2) and (3) by the low probability of an inadvertent criticality in areas l i
l where fresh fuel could be present, by the licensee's adherence to General '
Design Criterion 63 regarding radiation monitoring, and by provisions for personnel training and evacuation.
4 III.
Section 70.14 of 10 CFR, " Specific exemptions," states that The Commission may, upon application by any interested person or upon its own initiative, grant such exemptions from the requirements of the regulations in this part as it determines are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.
Section 70.24(d) of 10 CFR states that l
Any licensee who believes that good cause exists why he should be granted an exemption in whole or in part from the requirements of this section may apply to the Commission for such exemption.
Accordingly, the Commission has determined that good cause is present as defined in 10 CFR 70.24(d). The Commission has further determined that, pursuant to 10 CFR 70.14, the exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest. Therefore, the Commission hereby grants Duke Power Company an exemption from.the requirements of 10 CFR 70.24(a)(1), (2), and (3) for Catawba, Units 1 and 2, on the bases as stated in Section II above.
Pursuant to 10 CFR 51.32, the Commission has determined that granting of this exemption will have no significant effect on the quality of the human I
environment (62 FR 40553).
This exemption is effective upon issuance. )
FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY:
Samuel J. Collins, Director Office of Nuclear Reactor Regulation Dated at Rockville Maryland, this 29th day of buly 1997.
O e9,6
% 6' /f$f '
a a 26hl 0FFICE POII 2/PM Poll {k/\A PORMb 3 3 C 5 DRPE/D kk /
NAME Piam , L8 err er
[ B8oger RZ rman DATE )/f[ / 7 1/N/97 7 /0/97 7 /Mf97 / 7 0FFlC NWV y/1Che a'8 'f]l**
NAME Ws]CW b
]DATE @ M /97 l y/j7gy D008ENT RAME: G:\CATAWA\ CAT 97861.EX OFFICIAL RECORD COPY 1
--_-_-_____-_-__--c___.-_
(
Pursuant to 10 CFR 51.32, the Commission has determined that granting of this exemption will have no significant effect on the quality of the human environment (62 FR40553 ).
This exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION c ector Office of Nuclear Reactor Regulation Dated at Rockville, Maryland
.this 29th day of July 15l97.
1 i
i w_-_ - _ _ - --_.---- _ - - - - - _ _ -