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MONTHYEARML20211K7841985-04-25025 April 1985 Forwards Affidavit for Withholding Proprietary McGuire Units 1 & 2 Tubesheet Region Plugging Criterion (Ref 10CFR2.790).Nonproprietary Version Encl.Proprietary Version Withheld Project stage: Other ML20127P5321985-05-0909 May 1985 Summary of 850502 Meeting W/Util & Westinghouse in Bethesda,Md Re Steam Generator Tube Plugging for Indications within Tubesheet Region.List of Attendees & Viewgraphs Encl Project stage: Meeting ML20195C3711985-10-0909 October 1985 Change 0 to B&W Spent Fuel Receipt,Storage & Shipping W/Nli Cask. Summary of TN-8L Cask Procedure Encl Project stage: Other ML20140F8021986-03-20020 March 1986 Application for Amend to Licenses NPF-9 & NPF-17,authorizing Use of TN-8 & TN-8L Casks for Receipt of Irradiated Fuel. Justification Encl.Fee Paid Project stage: Request ML20195C3861986-05-0909 May 1986 TN-8L Draft Unloading Procedure for McGuire Station Project stage: Draft Other ML20198H4311986-05-22022 May 1986 Notice of Consideration of Issuance of Amends to Licenses NPF-9 & NPF-17 Re Use of Transnuclear,Inc multi-element Spent Fuel Shipping Casks TN-8 or TN-8L to Receive Irradiated Fuel Project stage: Other ML20195C3521986-05-23023 May 1986 Responds to 860512 & 15 Requests for Addl Info Re 860320 Application for Amends to Licenses NPF-9 & NPF-17,permitting Use of multi-element Spent Fuel Casks.Summary of Procedure OP/O/A/6550/13 Encl.W/Two Oversize Drawings Project stage: Request ML20195E2821986-05-28028 May 1986 Proposed Tech Spec 3/4.6.2.3,deleting Drywell Air Lock Seal Pressure Instrumentation 31-day Channel Functional Test from Surveillance Requirement 4.6.2.3.d.1 Project stage: Other ML20211K7711986-06-24024 June 1986 Application for Amends to Licenses NPF-9 & NPF-17,modifying Steam Generator Tube Plugging Criteria to Allow Evaluations of Degraded Tubes to Be Performed within Tubesheet.Fee Paid Project stage: Request ML20211K7791986-06-24024 June 1986 Proposed Tech Specs,Changing Steam Generator Tube Plugging Criteria to Allow Evaluations of Degraded Tubes to Be Performed within Tubesheet Project stage: Other ML20206U0001986-07-0101 July 1986 Forwards Revised Marked Up Proposed Tech Specs,Re Criterion for Plugging Steam Generator Tubes,Reflecting Change in Wording of Proposal.Changes Not Functionally Different from Changes in 860624 Submittal Project stage: Other ML20203A5051986-07-10010 July 1986 Informs of Present Schedule for Ongoing Refueling Outage,Per Proposed Changes to Tech Specs Submitted in 860624 & 0701 Ltrs.Approval of Change Required Prior to Entry Into Mode 4, Presently Scheduled for 860822 Project stage: Request ML20202J7721986-07-10010 July 1986 Forwards Addl Info to Support 860320 Application for Amends to Licenses NPF-9 & NPF-17,authorizing Use of Multielement Spent Fuel Casks TN-8 & TN-81 for Receipt of Irradiated Oconee Fuel.Timely Approval Requested Project stage: Request ML20207B1531986-07-11011 July 1986 Notice of Consideration of Issuance of Amends to Licenses NPF-9 & NPF-17 & Opportunity for Prior Hearing Re Elimination of Requirements for Plugging Steam Generator If Defect 2 Inches Below Top of Tube Sheet Project stage: Other ML20207B1381986-07-11011 July 1986 Disagrees That Proposed Amends to Licenses NPF-9 & NPF-17, Eliminating Need to Plug Steam Generator Tubes,Would Not Involve Significant Hazards Consideration.Notice of Opportunity for Prior Hearing Re Amends Encl Project stage: Other ML20211P2621986-07-16016 July 1986 Notification of 860725 Meeting W/Util & Westinghouse in Bethesda,Md to Discuss Proposed Tech Spec Change Re Plugging of Steam Generator Tubes W/Defects in Tubesheet Region Project stage: Meeting ML20212B8841986-07-31031 July 1986 Nonproprietary Tubesheet Region Plugging Criterion for Duke Power Co McGuire Nuclear Station Units 1 & 2 Steam Generators Project stage: Other ML20212B8741986-08-0101 August 1986 Requests That WCAP-11224 Tubesheet Region Plugging Criterion for Duke Power Co McGuire Nuclear Station Units 1 & 2 Steam Generators Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl Project stage: Other ML20212D0061986-08-0505 August 1986 Suppls 860320 Application for Amends to Licenses NPF-9 & NPF-17,permitting Use of multi-element TN-8 & TN-8L Spent Fuel Casks for Receipt of Irradiated Fuel.Info Re Environ Impacts Per 10CFR51.52 Encl Project stage: Request ML20212B8661986-08-0505 August 1986 Proposed Tech Specs,Incorporating Revised Steam Generator Plugging Criteria Project stage: Other ML20205H8161986-08-11011 August 1986 Environ Assessment & Finding of No Significant Impact Re Application for Amends to Licenses NPF-9 & NPF-17 to Revise Tech Spec 3/4.4.5, Steam Generators Project stage: Other ML20206M2951986-08-13013 August 1986 Supplemental Application for Amends to Licenses NPF-9 & NPF-17,revising Tech Specs Re RCS Surveillance Requirements for Steam Generator Tube Plugging.Tubes Will Be Inspected During Each Inservice Insp Project stage: Supplement ML20206M3031986-08-13013 August 1986 Proposed Tech Specs Re RCS Surveillance Requirements for Steam Generator Tube Plugging Project stage: Other ML20206M2821986-08-18018 August 1986 Forwards Revised marked-up Pages to Proposed Tech Specs Re Criterion for Plugging Steam Generator Tubes Reflecting Change in Wording of Proposal.Changes Not Functionally Different from Changes in 860813 Submittal Project stage: Other ML20206N9861986-08-19019 August 1986 Safety Evaluation Supporting Amends 59 & 40 to Licenses NPF-9 & NPF-17,respectively,modifying Steam Generator Tube Plugging Requirements for Tube Defects Located in Tubesheet Region Project stage: Approval ML20206N9981986-08-19019 August 1986 Notice of Issuance of Amends 59 & 40 to Licenses NPF-9 & NPF-17,respectively Project stage: Approval ML20206N9811986-08-19019 August 1986 Amends 59 & 40 to Licenses NPF-9 & NPF-17,respectively, Modifying Steam Generator Tube Plugging Requirements for Tube Defects Located in Tubesheet Region Project stage: Other ML20212N0061986-08-22022 August 1986 Environ Assessment & Finding of No Significant Impact Supporting 860320 Application for Amends to Licenses NPF-9 & NPF-17,authorizing Use of Transnuclear,Inc Models TN-8 & TN-8L Shipping Casks for Receipt of Irradiated Fuel Project stage: Other ML20206P8861986-08-25025 August 1986 Approves Withholding WCAP-10949, Tubesheet Region Plugging Criterion for Full Depth Hardroll Expanded Tubes, Per Util 860723 Application & Recipient 860722 Affidavit (Ref 10CFR2.790) Project stage: Other ML20210S5421986-09-22022 September 1986 Submits Addl Info Re Radiochemistry Program for Primary to Secondary Leakage Detection & Quantification,Per 860812 Telcon Request Project stage: Other ML20203N6881986-10-15015 October 1986 Agrees to Withhold Proprietary Version of McGuire Units 1 & 2 Tubesheet Region Plugging Criterion, (Ref 10CFR2.790) Per 860801 Request Project stage: Other AECM-86-0351, Forwards Application for Amend to License NPF-29,correcting Reactor Pressure Vessel pressure-temp Graph,Figure 3.4.6.1-1,clarifying Drywell Airlock & Changing Portion of Surveillance Requirement 4.6.2.3.Fee Paid1986-11-11011 November 1986 Forwards Application for Amend to License NPF-29,correcting Reactor Pressure Vessel pressure-temp Graph,Figure 3.4.6.1-1,clarifying Drywell Airlock & Changing Portion of Surveillance Requirement 4.6.2.3.Fee Paid Project stage: Request ML20213G7591986-11-11011 November 1986 Application for Amend to License NPF-29,correcting Reactor Pressure Vessel pressure-temp Graph (Figure 3.4.6.1-1), Clarifying Drywell Airlock & Changing Portion of Surveillance Requirement 4.6.2.3 Re Airlock Seal Sys Project stage: Request ML20213G7631986-11-11011 November 1986 Proposed Changes to Tech Spec Figure 3.4.6.1-1 Re Min Reactor Pressure Vessel Metal Temp Vs Reactor Vessel Pressure & Spec 3.6.2.3 Re Drywell Airlocks Project stage: Request ML20212J3471987-01-20020 January 1987 Proposed Tech Spec 3/4 4.6 Re Reactor Pressure Vessel pressure-temp Curve,Deleting Ref to NEDO-21778-A Project stage: Other ML20212J3341987-01-20020 January 1987 Supplemental Application for Amend to License NPF-29, Revising Tech Spec 3/4 4.6 Re Reactor Pressure Vessel pressure-temp Curve to Delete Ref to NEDO-21778-A Project stage: Supplement ML20211D6221987-02-13013 February 1987 Proposed Tech Spec 4.6.2.3 Re Surveillance Requirements for Containment Sys Concerning Drywell Air Lock Project stage: Other AECM-87-0037, Revises 861111 Application for Amend to License NPF-29, Changing Tech Spec 4.6.2.3.d.1 Re Drywell Airlock Seal Pressure Instrumentation Channel Functional Test Submitted on 860528,per Discussion W/Nrc.Proposed Tech Spec Page Encl1987-02-13013 February 1987 Revises 861111 Application for Amend to License NPF-29, Changing Tech Spec 4.6.2.3.d.1 Re Drywell Airlock Seal Pressure Instrumentation Channel Functional Test Submitted on 860528,per Discussion W/Nrc.Proposed Tech Spec Page Encl Project stage: Request ML20205R7501987-03-31031 March 1987 Amend 32 to License NPF-29,changing Tech Specs & Associated Bases for Reactor Pressure Vessel Pressure & Temp Limits to Be Consistent W/Limits Provided by GE for NSSS Project stage: Other ML20205Q6041987-03-31031 March 1987 Amend 31 to License NPF-29,revising Tech Specs by Changing Wording to Indicate Only One Drywell Airlock & Rearranging Action Statement a to Clarify That All Actions in Statement Parts of Same Action Project stage: Approval ML20205Q6081987-03-31031 March 1987 Safety Evaluation Supporting Amend 31 to License NPF-29 Project stage: Approval ML20205R7731987-03-31031 March 1987 Safety Evaluation Supporting Amend 32 to License NPF-29 Project stage: Approval ML20206B6631987-04-0303 April 1987 Errata to Amend 32 to License NPF-32,correcting Tech Spec Page B 3/4 4-3 Project stage: Other 1986-07-16
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3 DUKE POWER GOMPANY P.O. BOX 33180 CHARLOTTE, N.C. 28242 HAL B. TUCKER TELEPHONE
{7Q4)G M S3[
PR E.
August 5, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Conunission 9'
Washington, D.C.
20555 i
ATTENTION:
B.J. Youngblood, Director PUR Project Directorate #4 II '
5
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370 TN-8, TN-8L Multielement Spent Fuel Casks License Amendments - Supplement
- j ut
- A i T i
Daar Mr. Denton.
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My letter of March 20,1986 (as supplemented by my letters dated May 23, and July 10, 1986) submitted proposed license amendments (pursuant to 10 CFR 50.90) to Facility Operating Licenses NPF-9 and NPF-17 for McGuire Nuclear Station Units 1 i
cnd.2, respectively. The proposed amendments seek to permit use of the multielement TN-8 (and TN-8L) spent fuel casks for receipt of irradiated Oconee j
fual in addition to the previously authorized NFS-4 (NAC-1) and NLI-1/2 single 3
fusl assembly casks. The " Notice of Consideration of Issuance of Amendment to Facility Operating License and proposed No Significant Hazards Consideration J
Datermination and Opportunity for Hearing" related to the submittal was published in the Federal Register on May 29, 1986.
Tha above rc.arenced July 10, 1986 letter submitted certain additional information requested by the NRC with respect to the environmental assessment being prepared for these amendments. However, as a result of subsequent discussions between Duke Power Company and members of your staff regarding the environmental impacts of the proposed change, further information was requested for the assessment. This raquasted information addressing 10CFR 51.52 is provided in Attachment 1.
Sinca this letter contains information supplementing that provided in my March 20, 1
1986 submittal which is currently under review and is bounded by the contents of that submittal, the previous amendments, justification and safety analyses, and
{
significant hazards considerations remain valid, and no additional amendment fees j
cra necessary.
8bb812b283 86b8ad VDB Abock c50o6%9 Mg a
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Mr. H:rold R. D;nten, Dirsctor August 5, 1986 Page 2 Duke Power Company requests that this matter receive immediate attention and the proposed amendments issued as soon as possible for the reasons outlined in previous correspondence / discussions. Training and dry run operations with the TN-8L cask were scheduled to begin at McGuire on August 4, 1986, with shipments to btgin the week of August 18, 1986. Should there be any questions or if further information is required, please advise.
Vsry truly yours, Hal B. Tucker i
PBN/22/j gm Attachment xc:
Dr. J. Nelson Grace Regional Administrator U.S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Dayne Brown, Chief Radiation Protection Branch Division of Facility Services Department of Human Resources P.O. Box 12200 Raleigh, N.C.
27605 Mr. Darl Hood, Project Manager Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 i
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Mr. W.T. Orders Senior Resident Inspector McGuire Nuclear Station i
I l
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ATTACHMENT 1 DUKE POWER COMPANY McGUIRE NUCLEAR STATION SUPPLEMENTAL INFORMATION FOR ENVIRONMENTAL ASSESSMENT TRANSPORTATION OF OCONEE SPENT FUEL '20 McGUIRE VIA TN-8/8L CASKS Riqu7st:
Address 10CFR 51.52 with regard to plans for shipping spent fuel from Oconee to McGuire with the TN-8/TN-8L shipping casks.
f k1 Re ptnse:
[
1 Th3 anvironmental impact results contained in Table S-4 of 10CFR 51.52 make j l csveral assumptions on fuel assembly characteristics, traffic and population 1 4 !
d:naities. As discussed below, each of these assumptions is applicable to the M
prcpesed shipments of spent fuel from Oconee to McGuire. Consequently, all of the
~g j) canditions in paragraph (a) of Section 51.52 are met.
m Table S-4 assumes LWR with limited thermal power of 3800 Mega-
~l Recctor type watts. Oconee and McGuire are both LWR Nuclear Stations with
- l unit thermal power ratings of 2568 and 3411 Messwatts respec-tively.
Fuel type Table S-4 asstanes Zr-4 clad UO2 at enrichments below 4%.
l Oconee fuel is UO2 with Zr-4 cladding. Maximum initial en-richment of fuel that would be shipped from Oconae is 3.20%.
Fusi history
- Table S-4 assumes fuel burnup levels below 33,000 MWD /MIU and I
a minimum cooling time of 90 days. Oconee's candidate fuel assemblies will have average burnup levels less than 33,000 MWD /MTU. Minimum cooling time is espected to be 5 years, but in no instance will it be less than the 270 day minimum speci-fied in McGuire's operating license.
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i Transpcre Mode - Table S-4 assumes that shipments of irradiated fuel utilize truck, rail or barge transport modes. All shipments from Oconee to McGuire will be by truck.
Hast loads Table S-4 asstunes a maximum of 250,000 Btu /hr heat load per cask during shipment. Due to the extended cooling time for the candidate fuel assemblies this limit will never be ex-ceeded.
For 5-year cooled fuel the heat content will be less than one KW or 3,400 Beu/hr; or 10,200 Btu /hr per TN-8/TN-8L cask.
Waight limits As mentioned in Table S-4, weight limitations will be govern-ed by State and Federal regulations which will be observed by Duka Power Company.
Fr qu ncy of Shipments with the TN-8/TN-8L cask will be scheduled at the Shipm:nts rate of one per week. The Table S-4 limits of 1 truck ship-ment per day and 3 rail shipments per month will not be ex-caeded.
Doses to Transportation DOT regulations limit exposure in occupied areas of the Workers transport vehicle to a maximum of 2 mr/hr.
Assuming 2 per-sons in the transport vehicle, 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per Oconee to McGuire
~
shipment, 52 stdpments per year, and 2 mr/hr, the yearly cu-mulative dose to transportation workers would not exceed.728 man-rem.
Historical data indicates that actual dose rates will be much less than 2 mr/hr.
Doses to Table S-4 assumes that for each shipment,10 onlookers are Onlookers exposed for 3 minutes at a distance of 3 feet from the cask.
For Oconee to McGuire shipments, there are no planned stops during the 3 travel time and, consequently, no onlookers are expected to be exposed to radiological doses.
Doses to Public Along Route
- The approved shipping route between Oconee and McGuire is 172 miles in length. Population density along this route is conservatively estimated at 719 persons per square mile.
(This is based upon 1980 census data.) If a one mile wide corridor is examined, the total population.is 123,668 which is less than the Table S-4 value of 600,000 by a factor of 4.8.
Cumulative yearly dose to this population will not exceed the 3 man-rem limit specified in Table S-4 since that figure was based on a dose rate 6 feet from the cask equal to the legal limit.
Accidents in Transport
- The risks specified in Table S-4 were based on 155,000 vehicle miles per year. The subject shipments will result in only 8,944 miles per year by which the accident rate would be lower by a factor of 17.
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