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Category:GRANTS OF EXEMPTION FROM & EXTENSION TO NRC REQUIREME
MONTHYEARML20058D6481993-11-19019 November 1993 Exemption from Requirements of 10CFR140.11(a)(4) to Extent That Primary Financial Protection in Stated Amount Shall Be Maintained ML20057D1891993-09-27027 September 1993 Exemption from Training rule,10CFR50.120 Requirements to Establish,Implement & Maintain Training Program,Using Sys Approach to Training,For Categories of Personnel Listed in 10CFR50.120.Exemption Effective 931122 ML20246B1001989-06-28028 June 1989 Grants Exemption from 10CFR20,App A,Footnote d-2(c) Requirements to Allow Use of Radioiodine Protection Factor of 50 for MSA GMR-I Canisters at Plant ML20248E9091989-03-29029 March 1989 Exemption from 10CFR50,App J Requirements to Permit one-time Extension for Certain Local Leak Rate Tests to Cycle 8 Refueling Outage & Changes to Surveillance Period for Local Leak Rate Tests of DHR Suction Piping ML20155D5601988-10-0303 October 1988 Exemption from Property Insurance Rule (10CFR50.54(w)(5)(i)) Until Rulemaking Finalized But No Later than 890401 ML20207E6721988-08-0404 August 1988 Exemption from Requirements of 10CFR50.71,extending Date for Submittal of Amend 6 of Updated SAR ML20206F8801986-05-19019 May 1986 Exemption from Requirements of 10CFR50,App R,Subsection Iii.L Re Capability to Achieve Cold Shutdown in 72 H. Alternative Shutdown Capability Should Be Able to Achieve Cold Shutdown Conditions in 205 H ML20137B5311985-12-24024 December 1985 Exemption from Requirements of 10CFR50.44(c)(3)(iii) Re Installation of Reactor Vessel Head Vent & Other Sys Required to Maintain Adequate Core Cooling If Accumulation of Noncondensible Gases Causes Loss of Function of Sys 1993-09-27
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20149E4541994-05-13013 May 1994 Licensee First Set of Interrogatories & Request for Production of Documents to Eco.* W/Certificate of Svc. Related Correspondence ML20058P3701993-12-16016 December 1993 Memorandum & Order (Telcon 931209).* Smud Unopposed Motion Granted.W/Certificate of Svc.Served on 931217 ML20058P4161993-12-15015 December 1993 Licensee Petition for Review of Second Prehearing Conference Order & Motion for Directed Certification.* Advises That Commission Accept Review & Grant Directed Certification of Board Rulings.W/Certificate of Svc ML20058E0471993-11-30030 November 1993 Second Prehearing Conference Order (Proposed Contentions; Summary Disposition).* Environmental & Resources Conservation Organization Bases 1,5,11,13,2 & 14 Accepted for Litigation.W/Certificate of Svc.Served on 931201 ML20058E0361993-11-30030 November 1993 Transcript Corrections (Second Prehearing conference,930921- 22).* Board Adopts Listed Corrections.W/Certificate of Svc. Served on 931201 ML20058D6481993-11-19019 November 1993 Exemption from Requirements of 10CFR140.11(a)(4) to Extent That Primary Financial Protection in Stated Amount Shall Be Maintained ML20058E0151993-11-14014 November 1993 Comment Opposing Proposed Rule 10CFR50 Re Exemptions in Accident Insurance for Nuclear Power Plants Prematurely Shut Down ML20057G2181993-10-14014 October 1993 Proposed Transcript Corrections.* Submits Listed Transcript Corrections for 930921 & 22 Prehearing Conference. W/Certificate of Svc ML20058M8951993-10-0505 October 1993 Order (Proposed Transcript Corrections).* Util Submitted Proposed Transcript Corrections for 930921-22 Prehearing Conference.Other Parties May Submit Proposed Corrections by 931015.W/Certificate of Svc.Served on 931005 ML20058M8581993-10-0101 October 1993 Licensee Motion to Correct Transcript of Prehearing Conference.* Requests That Licensing Board Direct Correction of Prehearing Conference Trancript in Manner Described Above.Certification of Svc& Svc List Encl ML20057D0861993-09-27027 September 1993 NRC Staff Response in Support of Licensee Motion for Summary Disposition of Eco Original Loop Contention.* Summary Disposition Should Be Granted.Certificate of Svc Encl ML20057D1351993-09-27027 September 1993 Eco Concise Statement of Material Facts as to Which There Exists Genuine Issue to Be Heard.* Eco Original LOOP Contention Continues to Present Justifiable & Matl Issues Requiring Denial of Smud Motion.Certificate of Svc Encl ML20057D1021993-09-27027 September 1993 Eco Answer in Opposition to Smud Motion for Summary Disposition of Eco Original Loop Contention.* Urges Board Either to Deny Motion or to Defer Consideration of Smud Motion to Conclusion of Proceeding.W/Certificate of Svc ML20057D1891993-09-27027 September 1993 Exemption from Training rule,10CFR50.120 Requirements to Establish,Implement & Maintain Training Program,Using Sys Approach to Training,For Categories of Personnel Listed in 10CFR50.120.Exemption Effective 931122 ML20057D0451993-09-24024 September 1993 Notice of Hearing.* Notifies That Hearing Will Be Conducted in Matter of Proposed Decommissioning of Plant.W/Certificate of Svc.Served on 930924 ML20057D0441993-09-23023 September 1993 Notice of Appearance.* Notice Given That Undersigned Attorney Enters Appearance in Listed Matter & Listed Info Provided.W/Certificate of Svc ML20057C0851993-09-22022 September 1993 Transcript of 930922 Hearing in Bethesda,Md Re Facility.Pp 387-579 ML20057B9611993-09-21021 September 1993 Transcript of 930921 Hearing in Bethesda,Md.Pp 181-386 ML20057B0091993-09-10010 September 1993 Memorandum & Order CLI-93-19.* Informs That Further Questions of Board Re Effect of Commission Holding in Issues Concerning CLI-93-3 & CLI-93-12 Should Be Certified to NRC, Per 10CFR2.718(i).W/Certificate of Svc.Served on 930910 ML20057B0051993-09-0707 September 1993 Licensee Motion for Summary Disposition of Environ & Resources Conservation Organization Original Loop Contention.* Advises That Contention Presents No Genuine Issue of Matl Fact to Be Heard & Should Be Dismissed ML20057B0101993-09-0707 September 1993 Licensee Statement of Matl Facts as to Which There Is No Genuine Issue to Be Heard (Environ & Resources Conservation Organization Original Loop Contention).* Advises That Contention No Longer Matl Issue.W/Certificate of Svc ML20057A1721993-08-31031 August 1993 Notice of Prehearing Conference.* Notifies of 930921 Prehearing Conference in Bethesda,Md to Discuss Proposed Decommissioning of Plant.W/Certificate of Svc.Served on 930901 ML20128D4951993-01-28028 January 1993 Notice of Appointment of Adjudicatory Employee.* W/Certificate of Svc.Served on 930129 ML20127D5091992-09-11011 September 1992 Environ & Resources Conservation Organization Brief in Support of Appeal from LBP-92-23.* Certificate of Svc Encl ML20127D4711992-09-0808 September 1992 Notice of Appeal.* Gives Notice of Appeal from Order of Board (Served 910821),denying Environ & Resources Conservation Organization Petition for Intervention & Request for Hearings & Termination of Proceedings ML20141M5981992-08-20020 August 1992 Prehearing Conference Order (Terminating Proceeding).* Petition for Leave to Intervene & Request for Prior Hearing of Petitioner, ,denied & Proceeding Terminated. W/Certificate of Svc.Served on 920821 ML20141M5881992-08-17017 August 1992 NRC Staff Response in Support of Licensee Motions to Strike Improper Argument in Environmental & Resources Conservation Organization (Eco) Filings.* Further Argument by Eco Unauthorized.Certificate of Svc Encl ML20058G9051990-10-23023 October 1990 Comment on Fr Notice Page 41280 to 41282 Re Smud Possession Only License Amend.Believes Termination of Plant OL Prior to End of Authorized Operating Term Will Have Significant Impact on Environ Sources Needed to Generate Power ML20247K3691989-08-29029 August 1989 Transcript of 890829 Status Briefing W/Util in Rockville,Md Re Plant.Pp 1-104.Supporting Documentation Encl ML20246B1001989-06-28028 June 1989 Grants Exemption from 10CFR20,App A,Footnote d-2(c) Requirements to Allow Use of Radioiodine Protection Factor of 50 for MSA GMR-I Canisters at Plant ML20245G6761989-04-0707 April 1989 Transcript of 890407 Briefing on Plant in Rockville,Md.Pp 1-64.Related Matl Encl ML20247R4391989-04-0707 April 1989 Transcript of Commission 890407 Press Conference in Rockville,Md.Pp 1-14 ML20248E9091989-03-29029 March 1989 Exemption from 10CFR50,App J Requirements to Permit one-time Extension for Certain Local Leak Rate Tests to Cycle 8 Refueling Outage & Changes to Surveillance Period for Local Leak Rate Tests of DHR Suction Piping ML20247C9031989-03-21021 March 1989 Director'S Decision Under 10CFR2.206 Re Denial of Request to Shut Down Facility Based on Allegation That Util Disregarded Public Health & Safety Per 1980,1984 & 1988 Incidents ML20247C9501989-03-21021 March 1989 Notice of Issuance of Director'S Decisions Under 10CFR2.206 ML20235S4121989-02-24024 February 1989 Comment on Proposed Rules 10CFR50 & 55 Re Educ of Senior Reactor Operators.Alternative 2 Preferable.Util Suggests That Neiter Be Imposed.Both Alternative Could Cause Immediate & long-term Impact on Plant Safety ML20235T9061989-02-19019 February 1989 Comment on Proposed Rules 10CFR50 & 55 Re Educ & Experience Requirements of Senior Reactor Operators & Supervisors. Requirement for Educ from Source Other than Industry Will Probably Cut Into Time Allotted for Training Now Received ML20206M5991988-11-18018 November 1988 Comment Supporting Proposed Rule 10CFR26 Re NRC Fitness for Duty Program.Recommendations Listed ML20155D5601988-10-0303 October 1988 Exemption from Property Insurance Rule (10CFR50.54(w)(5)(i)) Until Rulemaking Finalized But No Later than 890401 ML20207E6721988-08-0404 August 1988 Exemption from Requirements of 10CFR50.71,extending Date for Submittal of Amend 6 of Updated SAR ML20148K0181988-03-22022 March 1988 Transcript of 880322 Public Meeting in Washington,Dc Re Discussion/Possible Vote on Facility Restart.Related Info Encl.Pp 1-113 ML20148J3811988-03-22022 March 1988 Director'S Decision Under 10CFR2.206 Re T Bradley,Mayor of Los Angeles,Ca,Petition Requesting NRC to Conduct Public Hearing & Permanently Close Plant.For Reasons Discussed, Petition Denied ML20236A7691987-10-16016 October 1987 Transcript of 871016 Briefing in Washington,Dc on Status of Plant.Pp 1-72.Supporting Documentation Encl ML20215D6741987-06-12012 June 1987 Suppl 4 to Petition for Immediate Action to Relieve Undue Risk Posed by Nuclear Power Plants Designed by B&W.Ucs Reply to Responses from NRC & B&W Owners Group.* Certificate of Svc Encl ML20210B8041987-04-27027 April 1987 Receipt of Petition for Director'S Decision Under 10CFR2.206.* Notice of Receipt of B Moller 870225 Petition to Show Cause Why Facility Should Not Be Restarted or Completely Shut Down ML20247F0451987-04-0707 April 1987 Transcript of 870407 Investigative Interview W/Rj Rodriguez in San Diego,Ca 1994-05-13
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7590-01 ,
UNITED STATES OF AMERICA >
NUCLEAR REGULATORY COMMISSION In the Matter of )
SACRAMENTO MUNICIPAL UTILITY )
DISTRICT ) Docket No. 50-312 (Rancho Seco Nuclear Generating )
Station) )
EXEMPTION
Sacramento Municipal Utility District (the licensee) is the holder of Facility Operating License No. DPR-54 which authorizes the operation of the Rancho Seco Nuclear Generating Station (the facility) at steady-state power levels not in excess of 2772 megawatts thermal. The license provides, among other things, that it is subject to all rules, regulations and Orders of the Nuclear Regulatory Connission (the Commission) now or hereafter in effect.
The facility is a pressurized water reactor (PWR) located at the i licensee's site in Sacramento County, California.
II.
] On December 2,1981, the Commission published a revised Section 10 CFR 50.44, " Standards for Combustible Gas Control System in Light-Water-Cooled j
Power Reactors" (46 FR 58484). Section10CFR50.44(c)(3)(iii)ofthe regulation requires:
"To provide improved operational capability to maintain adequate core cooling following an accident, by the end of the first scheduled outage beginning after July 1,1982, and of sufficient duration to permit required modifications, each light-water nuclear power reactor shall be provided with high point vents for the reactor coolant system, for the 8601150550 851224 DR ADOCM O 2
7590-01 1
reactor vessel head, and for other systems required to maintain adequate core cooling if the accumulation of noncondensible gases would cause the loss of function of these systems."
By letter dated July 2, 1982, the licensee requested an exemption from the requirement of 10 CFR 50.44(c)(3)(iii) to install a reactor vessel head vent. The basis for the request was a proposed alternate technique for venting noncondensible gases from the reactor vessel head. The alternate technique involved the use of high point vents at the top of the hot leg U-bends as a means to vent noncondensible gases from the reactor vessel.
- On July 25, 1983, the Commission issued an interim exemption to defer the implementation date for installation of a reactor vessel head vent until December 31, 1985. At that time, the Commission was unable to conclude that noncondensible gases could be safely vented by the hot leg high point vents '
4 alone. The primary reason for the Commission's conclusion was the lack of integral system test data which would demonstrate the feasibility of the proposed venting procedure. The interim exemption was granted in order to allow the licensee to perform the necessary integral system testing.
On April 12, 1985, the licensee provided the results of testing performed in the Once-Through Integral System (OTIS) test facility which was performed to demonstrate that a reactor vessel head vent is not necessary to (nsure adequate core cooling in the presence of significant quantities of noncondensible gases. Based upon these test results, the licensee requested a permanent exemption from the requirement to install a reactor vessel head vent.
7590-01 III.
The OTIS facility is an experimental test facility at Babcock & Wilcox's (B&W's) Alliance Research Center in Alliance, Ohio. The OTIS facility was designed to evaluate the thermal / hydraulic conditions in the reactor coolant system and steam generator of a raised-loop B&W reactor, during the natural circulation phases of a small-break Loss of Coolant Accident (LOCA). The OTIS facility is a portion of the Integral Systems Test Program sponsored by the Commission, EPRI, B&W Owners Group and B&W.
The Commission has reviewed the OTIS test results and the licensee's proposed procedures and found that: -
The hot leg vent can be used to remove noncondensible gases from the reactor vessel head during a plant cooldown and depressurization without interrupting natural circulation.
Even if noncondensible gases in the reactor vessel head expanded into the hot leg U-bend and interrupted natural circulation, feed-and-bleed cooling can be used to assure core cooling. In addition, opening of the het leg vent will also allow the restoration of natural circulation.
Venting procedures have been developed to limit gas expansion rates from the reactor vessel head in order to ensure that natural circulation is continuously maintained during a plant cooldown.
Procedures would specify initiation of feed-and-bleed cooling of the core, should natural circulation become interrupted, while' attempting to recover natural circulation by leaving the hot leg vents open. -
~
7590-01 The reactor vessel head gas bubble which would remain following plant cooldown to actuation of the decay heat removal system will not interfere with core cooling. The licensee has developed various means to remove this gas bubble in the long term.
The OTIS tests were performed in a manner which assures that the results bound the expected Rancho Seco plant performance.
Based on the above discussion, we conclude that an exemption to 10 CFR ~
50.44(c)(3)(iii) can be granted. Details of the review may be found in the Commission's related Safety Evaluation dated December 24, 1985, which is available for public inspection at the Commission's Public Document Room, 1717 H Streat, N.W., Washington, D.C., and at the Sacramento City-County Library, 828 I Street, Sacramento, California.
IV. '
Accordingly, the Commission has determined that, pursuant to 10 CFR Part 50.12, an 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 and hereby grants an exemption with' respect to the requirements of 10 CFR 50.44(c)(3)(iii), as follows:
The licensee is not required to install a reactor vessel head vent at the Rancho Seco Nuclear Generating Station.
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7590-01 i
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Pursuant to 10 CFR 51.32, for the reasons stated in the Environmental Assessment and Finding of No Significant Impact, published in the FEDERAL REGISTER on December 17, 1985, 50 FR 51492, the Commission has determined that the issuance of the exemption will have no significant impact on the environment.
This exemption is effective upon issuance.
FOR THE EAR REGULATORY COMMISSION Fran Schroeder, De uty Director i Division of PWR Licensing-B
- Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 24th day of December 1985.
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