|
---|
Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217D1071999-09-16016 September 1999 Provides Proposed Schedule for Review of Trojan License Termination Plan (Ltp),As Committed in 990903 Memo.Project Manager Should Schedule LTP Meeting Near Trojan Site for Late Nov or Early Dec,Based on Region IV Availability ML20216E4091999-09-0303 September 1999 Informs That Staff Has Performed Acceptance Review of Trojan Nuclear Plant License Termination Plan Submitted by Ltr Dtd 990805.NMSS Determined That Licensee Has Provided Sufficient Info for NRC to Proceed with Detailed Review ML20205R4091999-04-16016 April 1999 Informs That LTP for Trojan Nuclear Plant Did Not Provide Sufficient Info to Perform Detailed Review & Waste Mgt Recommends Returning LTP to Licensee So That LTP Can Be Resubmitted as Complete Application ML20195B6401998-11-10010 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Preliminary Plans for Plant Final Site Surveys ML20155G6571998-11-0303 November 1998 Notification of 981119-990331 Meeting with Util in Rockville,Md to Clarify Remaining Technical Issues Associated with Util Application for License to Operate ISFSI at Tpp ML20236S5361998-07-22022 July 1998 Notification of 980812 Meeting W/Portland General Electric in Arlington,Texas to Discuss Status of Decommissioning Activities at Trojan NPP ML20236R6511998-07-15015 July 1998 Notification of 980730 Meeting W/Listed Participants in Kelso,Wa Re Proposed Request from Portland General Electric Co for Approval to Allow one-time Shipment of Plant Decommissioned Reactor Vessel.Meeting Agenda Encl ML20236R6931998-07-15015 July 1998 Notification of 980730 Meeting W/Util to Discuss Request for Addl Info Re Ongoing Review of Portland General Electric Co Request for Approval to Allow one-time Shipment of Trojan Decommissioned Reactor Vessel.Meeting Agenda Encl ML20248L4691998-03-17017 March 1998 Notifies of in-house Research Project Re Digital I&C in NPP & Forwards Technical Training Div (TTD) ML20216E7421998-03-0606 March 1998 Notification of 980318 Meeting W/Portland General Electric in Rockville,Maryland to Discuss Proposed Shallow Land Disposal of Trojan Reactor Vessel ML20199D4951998-01-26026 January 1998 Notification of Licensee Meeting W/Util on 980209 in Arlington,Tx to Discuss Changes to Protected Area for Plant to Facilitate Ongoing Decommissioning of Site ML20199G1561998-01-22022 January 1998 Staff Requirements Memo Re SECY-97-244, Waste Classification of Plant Reactor Vessel ML20199G1121998-01-20020 January 1998 Submits Addl Views on Proposal to Dispose of Trojan Reactor Vessel,Per SECY-97-244 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20216F2611997-08-26026 August 1997 Staff Requirements Memo Re SECY-97-164, Shipment of Decommissioned Reactor Vessel,Containing Irradiated Internals,From Trojan Nuclear Plant to Hanford Nuclear Reservation,Richland,Wa ML20141G2911997-05-15015 May 1997 Forwards Page A-25 of Rev 5 to PGE-1060, Tnp Permanently Defueled Emergency Plan ML20137W9801997-04-16016 April 1997 Notification of Significant Licensee Meeting W/Util on 970508 in Rockville,Md to Discuss Plans for Decommissioning of Plant ML20137H2231997-03-31031 March 1997 Forwards Info in Support of Pnl Modeling for Fgeis Final Rule on Radiological Criteria for License Termination ML20135B1941997-01-30030 January 1997 Responds to Re Util Position Re Potential for Ash Fall at Trojan Site ML20138J2731997-01-21021 January 1997 Submits Comments on 970113-16 QA Insp of Sierra Nuclear Corp in Scott Valley,Ca ML20134B6001997-01-13013 January 1997 Provides Meeting Minutes from NRC Insp 97-201 Exit Meeting Re Insp of Trojan'S QA Program for Isfsi,From 970107-09 ML20133N2821997-01-0808 January 1997 Requests Comments on Poge Position Re Potential for Ashfall at Trojan Site ML20135B8581996-12-0303 December 1996 Requests Guidance on Use of 10CFR71.41(c) Per Licensee Request for Authorization to Transport Reactor Vessel as Type B Package ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20237F1891996-01-22022 January 1996 Notification of 960131 Meeting W/Util in Rockville,Md to Discuss Planned Removal of Plant Pressure Vessel ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20057B6071993-09-16016 September 1993 Notification of 930928 Meeting W/Util in Rockville,Md to Discuss Status of Decommission Activities & Physical Security ML20057A6651993-08-27027 August 1993 Forwards Notice of Consideration of Issuance of Amend to License NPF-1 & Proposed NSHC Determination & Opportunity for Hearing ML20056E5331993-08-16016 August 1993 Notification of 930901 Mtg W/Util & State of or in Rainier, or to Discuss Proposed Studies of Plant Sys at Plant ML20056E4451993-08-0606 August 1993 Notifies of 930812 Meeting W/Util in Rockville,Md for Presentation on Plant Decommissioned TS ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20128G0061993-02-0101 February 1993 Notifies of Cancelled 930210 Meeting W/Technical Analysis Corp to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127L9741993-01-22022 January 1993 Notification of 930204 Meeting W/Util in Rockville,Md to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127J7691993-01-15015 January 1993 Discusses Interim Plugging Criteria for Util & Provides Discription of Core Damage Frequency Derivation & Present RES Plans for Addl Work on Steam Generator Tube NDE That RES Intends to Do This Year ML20127E7821993-01-11011 January 1993 Notification of Significant Licensee Meeting W/Util on 930120 to Discuss Shutdown Plans & Decommissioning Strategies for Facility ML20127A5381993-01-0707 January 1993 Discusses QC Concerns W/Mine Safety Appliances Co Full Face Negative Pressure Respirators (Ultra View & Ultra Twin) W/Potential 10CFR21 Implications ML20127F4461993-01-0707 January 1993 Revised Notification of Significant Meeting W/Util on 930202 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Department at Plant ML20127A5701993-01-0505 January 1993 Provides Position on Interim Plugging Criteria for Plant ML20126G9861992-12-22022 December 1992 Notification of Significant Licensee Meeting W/Util on 930113 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Dept at Plant ML20126E6501992-12-18018 December 1992 Notification of or Energy Facility Siting Council Special Meeting & Hearing on 930105 & 06 in Portland,Or to Discuss Tnp SG Tube Cracking Issue,Interim SG Tube Plugging Criteria & Issues from Current Forced Outage.Agenda Encl ML20126F4271992-12-18018 December 1992 Notification of 921230 Meeting W/Util in Rockville,Md to to Discuss Steam Generator Insp Program & Results as Consequence of primary-to-secondary Steam Generator Leak Event on 921109 ML20126F4821992-12-18018 December 1992 Notification of Cancellation of 921230 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109 primary-to-secondary SG Tube Leak Event & Recent Issues Raised Re Interim Plugging Criteria ML20126E7641992-12-16016 December 1992 Notification of 921223 Meeting W/Util in Rockville,Md to Discuss Steam Generator Insp Program & Results as Consequence of 921109 primary-to-secondary Steam Generator Tube Leak Event ML20126F4651992-12-16016 December 1992 Cancelled Notification of 921223 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109,primary-to-secondary SG Tube Leak Event ML20125C7641992-12-0909 December 1992 Discusses Technical Aspects of Rationale Used to Support Steam Generator Tube Interim Plugging Criteria for Plant & Independent Conclusions on Viability of Independent Plugging Criteria for One Fuel Cycle ML20126F4711992-12-0707 December 1992 Forwards Draft Rept of RES Position on Steam Generator Tube Integrity ML20126E5221992-11-30030 November 1992 Informs Staff Revised Prioritization Will Be Forwarded for Further Comments in Response to 921124 Memo Re GI 163, Multiple Steam Geneator Tube Leakage ML20125A6311992-11-25025 November 1992 Notification of 921201 Meeting W/Util to Discuss Assessment of Recent SG Tube Leak ML20128C3491992-06-16016 June 1992 Discusses Proposal of New Generic Issue, Multiple SG Tube Leakage, as Resolution to DPO Received Addressing Operation of SGs W/Microscopic Tube Wall Cracks.Dpo Encl ML20128C3141992-03-27027 March 1992 Submits Analysis, Safety Issue Re Continuous Operation W/ Degraded SG Tubes, Indicating Core Melt Probability Frequency of 10 -4/Ry W/Containment Bypass 1999-09-03
[Table view] Category:STAFF REQUIREMENTS MEMORANDUMS
MONTHYEARML20199G1561998-01-22022 January 1998 Staff Requirements Memo Re SECY-97-244, Waste Classification of Plant Reactor Vessel ML20216F2611997-08-26026 August 1997 Staff Requirements Memo Re SECY-97-164, Shipment of Decommissioned Reactor Vessel,Containing Irradiated Internals,From Trojan Nuclear Plant to Hanford Nuclear Reservation,Richland,Wa 1998-01-22
[Table view] |
Text
{{#Wiki_filter:- _ _ _ - _ - _ _ _ _ _ - _
....................oooo
/ %g UNITED STATES RELEASED TOTHE PDR o 8 g NUCLEAR REGULATORY COMMISSlQN $
WASHINGTON, D.C. 20555-0001 o
-{*d a . /
- 6. m
*******a n,,,, January 22, 1998 OFFICE OF THE SECRETARY MEMORANDUM TO: L. Joseph Callan Ex utive Director for Operations FROM: C. , tary
SUBJECT:
STAFF REQUIREMENTS - SECY-97-244 - WASTE CLASSIFICATION OF THE TROJAN REACTOR VESSEL The Commission has approved the staff's proposed response to the State of Washington requesting additional information and analysis for the Trojan reactor vessel subject to incorporation of the changes indicated in the attachment.
(EDO) (SECY Suspense: 1/30/98)
Attachment:
As stated -
cc: Chairman Jackson Commissioner Dieus Commissioner Diaz Commissioner McGaffigan OGC CIO '
CFO 1 D OCA p# ~, '
OlG Office Dirc: tors, Regions, ACRS, ACNW, ASLBP (via E-Mail)
PDR 9 0,1 d e 3(EXh SECY NOTE: THIS SP,M, SECY-97-244, AND THE COMMISSION VOTING RECORD CONTAINING THE VOTE SHEETS OF ALL COMMISSIONERS WILL BE MADE PUBLICLY AVAILABLE AFTER THE LETTER IS SIGNED AND DISPATCHED.
9802040229 980122 PDR 10CFR 1
! ni ni PT9.7 PDR i[)1l g,
;l ,fff, {,
; QL k'lb
j-i
. Mr. John Lf Erickson, Director Division of Radiation Protection-Department of Health Airdustrial Center Building #5 P.O. Box 47827
- Olympia, WA 98504-7827
Dear Mr. Erickson:
On March 31,1997, Portland General Electric Company (PGE) requested the.U.S. Nuear Regulatory Commission to issue a Type B Certificate of Compliance under our transportation regulations to allow a one-time shipment of the Trojan Nuclear Plant's reactor vessel with its intemals for disposal at the U.S. Ecology site in Hanford, Washington. Prior to beginning a full
- review of this transportation package application, it is our intent to address the waste classification of the waste shipment ad r .:': w : Of h att:: j f;r d:;-;-x:L Underthe 10 CFR 20 waste manifesting requirements, a waste generator must classify wastes in accordance p with 10 CFR 61.55, it is our goal to ensure that the waste shipment is properly classified. ?
On June 18,1997, PGE submitted responses to several of our questions relating to the classification of the waste shipment (Attachment 1). PGE ackncdedges that some of the intemals are Greater-Than-Class C (GTCC), but is proposing to classify the wastes by ,
l averaging the reactor intemals with the pressure vessel. The core baffle plates, the core former I. . plates, and the lower core plate substantially exceed the recommended ratios for classifying activated metals given in Section 3.3 of the Branch Technical Position (BTP) on Concentration Averaging and Encapsulation dated January 17,1995. However, PGE indicated that the one-piece shipment of the RV with the intemals would allow contact handling of the shipment, would -
result in 30 to 44 fewer waste cans requiring storage until a GTCC waste disposal site is developed, would reduce ,ontamination control problems, would reduce occupational exposures from 134 to 154 person-rem to 67 person-rem (out of 591 person-rem estimated for the entire Trojan decommissioning), and would reduce waste shipments from 44 to 1.
- PGE also provided a pathway analysis performed by U.S. Ecology, which was previously submitted to the State of Washington. This pathway analysis addresses groundwater impacts ,
and doses from direct exposure. Other intruder pathways such as construction and resident-farmer scenados are not addressed, nor is there a justification for assuming that the package will remain iritect over the hazard lifetime of the nuclides that are critical to the waste classification: C-14, Ni-59, Ni-63, and Nb-94.
The NRC staff will consider attemative approaches to waste nucide averaging if it can be
'shown that the wastes will meet the performance objectives in.10 CFR Part 61 (see 10 CFR 61.58 and Section 3.9 of the Ornch T;;hnl;;l Psh:m BTP_ on Concentration Averaging and Encapsulation). The evaluation should include a comprehensive and defensible pathway analysis that includes all relevant pathways. The draft St=ch Tshn =l Pan:a BTP on a Performance Assessment Methodology for Low-Level Radioactive Waste Disposal Facilities could be used as guidance for this analysis. The draft BTP has been made available for public
{
t
3- comment and review and does not represent a final agency position.
We request that your staff ask U.S. Ecology, in coordination with PGE, to perform a comprehensive and defensible pathways analytis to demonstrate the suitability of the proposed wastes for disposal at the Hanford disposal site. Specifically, the analysis should be based on
- intruder-construction and intruder resident-farmer scenarios carried out foi ; 10,000 y;;r perled the timeframe proposed in the BTP.
If the waste package is assumed to be intact for a period greater than 500 years, justification needs to be provided. The draft *0r:n;S T;;hn;;;l re;n en BTP on a Performance Assessment Methodology for Low-Level Radioactive Waste Disposal Facilities
- ehcould be used as guidance. Sw.:tions 3.2.2,3.2.3,3.34. and 3.3.5 of this Or;n:h T;;hnl;;; I;;M:;n BTP provide guidance on the time frames for the performance assessment, use of engineered barriers, and evalJation of Wdste forms for the p6Tformance assessment.
After your revi3w of this information, if you conclude that the reactor vessel with intemals is suitable for disposal under the State of Washington's regulations, we will consider allowing the shipment to be classified under the attemative averaging provisions of the Or;nch T;;hn;;;;
Peedoen BTP on Concentration Averaging and Encapsulation. We are also willing to provide any technical assistance you may desire for the review of the submitted pathway analyses.
Sincerely, l
Richard L. Bangart, Director Office of State Programs 1
..}}