Letter Sequence Other |
|---|
|
|
MONTHYEARML20100H4581985-02-28028 February 1985
Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program
Project stage: Other
ML20100H4341985-04-0505 April 1985
Forwards WCAP-10786, Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Per App H to 10CFR50.Based on Rept,Rev to Tech Specs May Be Necessary.Nrc Will Be Advised If Rev Needed
Project stage: Other
ML20138K8101985-12-16016 December 1985
Application for Amends to Licenses NPF-9 & NPF-17,extending Authorization to Operate Facilities Until 210612 & 230303, Respectively.Fee Paid
Project stage: Request
ML20140A5571986-01-15015 January 1986
Forwards Projected Values of RT Pressurized Thermal Shock, Per 10CFR50,Section 50.61(b)(1).Ref Temp Determination Also Encl
Project stage: Other
ML20141C8571986-01-31031 January 1986
Nonproprietary Analysis of Capsule V from Duke Power Co, McGuire Unit 2,Reactor Vessel Radiation Surveillance Program
Project stage: Other
ML20141C8451986-04-0202 April 1986
Forwards Nonproprietary WCAP-11029, Analysis of Capsule V from Duke Power Co,Mcguire Unit 2,Reactor Vessel Radiation Surveillance Program. Revised Capsule Removal Schedule Recommended
Project stage: Other
ML20155J5671986-05-15015 May 1986
Application for Amends to Licenses NPF-9 & NPF-17,changing Tech Specs to Ensure Plant Operation Consistent W/Design & Statements in Unit 1 Cycle 4 Reload Safety Evaluation.Fee Paid
Project stage: Request
ML20195E2591986-05-23023 May 1986
Forwards Peaking Factor Limit Rept for Unit 1,Cycle 4 in Support of 841116 Application for Amends to Licenses NPF-9 & NPF-17.Conclusions in Reload Safety Evaluation Remain Valid
Project stage: Request
ML20210U3301986-05-29029 May 1986
Requests Addl Info Re Concerning Ref Temps for Pressurized Thermal Shock Reactor Vessel Beltline Matls Calculated for Svc Life of Plant.Response Requested within 45 Days
Project stage: Other
ML20211G1061986-06-0606 June 1986
Informs That Correct Date for Submittal of Proposed License Amends Re Cycle 4 Optimized Fuel Assembly Reload Is 860515, Not 841116 as Ref in Transmitting Peaking Factor Limit Rept
Project stage: Other
ML20202B3881986-06-30030 June 1986
Proposed Tech Specs Re Specific Criteria & Predicted Values of Safety Analyses & Evaluations Performed for Transients Sensitive to Positive Moderator Coefficient
Project stage: Other
ML20207B7171986-07-10010 July 1986
Responds to NRC 860529 Request for Addl Info Re Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock.Values for Best Estimate Weight Percent of Copper & Nickel Obtained from WCAP-10786 & WCAP-11029
Project stage: Request
ML20204H6551986-07-31031 July 1986
Rev 1 to Reload Safety Evaluation,Mcguire Nuclear Station, Unit 1 Cycle 4
Project stage: Other
ML20205C9341986-08-0404 August 1986
Notice of Consideration of Issuance of Amends to Licenses NPF-9 & NPF-17 & Proposed NSHC Determination & Opportunity for Hearing Re Supplemental Request Concerning Optimized Fuel Assemblies
Project stage: Other
ML20204H6241986-08-0404 August 1986
Revised Application for Amends to License NPF-9 & NPF-17, Changing Design Features Tech Spec Section to Generally Allow Use of Modified Fuel Assemblies in Core.Cycle Specific Reload SER Revised to Reflect Core Redesign
Project stage: Request
ML20204H6491986-08-0404 August 1986
Proposed Tech Specs,Reflecting Revised Design Features to Generally Allow Use of Modified Fuel Assemblies in Core
Project stage: Other
ML20206M2891986-08-12012 August 1986
Advises That Rev to Peaking Factor Limit Rept Unnecessary. End of Cycle 3 Refueling Outage Schedule Provided in 860804 Submittal Revised to Reflect Unit 1 860823 Cycle 4 Startup
Project stage: Other
ML20214M6621986-08-28028 August 1986
Notice of Violation from Insp on 860707-11
Project stage: Other
05000369/LER-1986-013-02, :on 860626,discovered Loose Fuel Pellets from Fuel Assembly D-03 on Reactor Core Baffle Plate Near Core Location P-3.Caused by Baffle Jetting.Assembly Removed from Core & Core Redesigned1986-08-28028 August 1986
- on 860626,discovered Loose Fuel Pellets from Fuel Assembly D-03 on Reactor Core Baffle Plate Near Core Location P-3.Caused by Baffle Jetting.Assembly Removed from Core & Core Redesigned
Project stage: Other
ML20210C0091986-09-0808 September 1986
Application for Amends to Licenses NPF-9 & NPF-17,changing Tech Specs to Incorporate Improvements Re Pressure Temp Operating Limits as Result of Exam of Capsules Withdrawn During First Refueling Outage.Fee Paid
Project stage: Request
ML20210C0331986-09-0808 September 1986
Proposed Changes to Tech Specs,Incorporating Improvements Re RCS Pressure Temp Operating Limits
Project stage: Request
ML20215K9621986-10-21021 October 1986
Forwards Evaluations Supporting 860115,0402,05 & 0710 Responses to 10CFR50.61 Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events,Based on 32 EFPYs
Project stage: Other
ML20235W0921987-10-13013 October 1987
Requests That Portions of Util 860908 Application for Amends to Licenses NPF-9 & NPF-17 to Change Tech Specs Re RCS Pressure/Temp Limits Be Revised Due to Change Not Having Endorsement of Westinghouse Owners Group
Project stage: Other
ML20236B6131987-10-20020 October 1987
Responds to Requesting Rev to 860908 Proposal to Update Existing RCS pressure-temp Limits.Present Operating Limits Valid Until 1989.Proposed Tech Spec Rev Withdrawn. Appropriate Proposal Will Be Submitted at Later Date
Project stage: Other
1986-05-29
[Table View] |
Text
e DUKE POWEli GOEPANY e.o.nox aa:Bo OHAMLOTTE. N.C. 28242 HAL H. TUCKER TELEPHONE vum reanspawr (704) OT+4531 April 5, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Ms. E. G. Adensam, Chief Licensing Branch No. 4
Subject:
McGuire Nuclear Station, Unit 1 Docket No. 50-369
Dear Mr. Denton:
l Pursuant to 10 CFR50, Appendix H, please find attached a report entitled
" Analysis of Capsule U from the Duke Power Company McGuire Unit 1 Reactor Vessel Radiation Surveillance Program", WCAP-10786.
Based on an initial and preliminary review of the results of this capsule evaluation, it appears that the present heatup and cooldown curves in Technical Specification will need to be revised.
Plant heatup and cooldown operating limits generated as part of this report differ I
from the original 10 year plant operating limits identified in the plant technical specifications. The new limits are based on a 10 EFPY neutron fluence of 3.89 x 1018 n/cmZ and RT of178'Fwhgreasthetechnicalspecificationlimitsarebased on a fluence of 2 h x 1018 n/cm and an RTNDT of 124 F.
This difference occurs because Regulatory Guide 1.99 Revision 1 was used to predict radiation damage for the new limit curves whereas Westinghouse prediction methods were used for developing the original limit. curves.
In addition, neutron fluence values for the limiting weld location have been updated using the latest state of the art dosimetry methods (energy groups, cross sections, etc.).
It should also be noted i
that in the original analysis the capsules located at 56 and 58.5* vere assumed to provide shielding for the critical longitudinal weld seam located a't 60*.
However, in the new analysis the capsules were not considered as providing shielding because they only shield approximately 30 inches'of 106 inch long weld seam located at 60'.
, Although new plant operating limits have now been developed for the plant, the y old operating limit curves have been determined to be appropriate for up to 4.86 EFPY. McGuire Unit 1 has operated for approximately 2 EFPY to date.
Duke is continuing to review the results contained in this report.
If determined to be necessary, a proposed Technical Specification revision will be submitted in a timely manner so as to allow NRC sufficient time to review and approve prior to the present Technical Specification curves becoming non-conservative.
8504090178 850405,
OI PDR ADOCK 0500036 0
Y PDR
\\g t
- ,6 s
Mr. Harold R. Denton, Director April 5, 1985 Page 1 If there are any questions regarding this, please advise.
Very truly yours, pl. cLL.g Hal B. Tucker RLG/mjf Attachment cc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission
. Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 W. T. Orders Senior Resident Inspector McGuire Nuclear Station Mr. Darl Hood, Project-Manager Division of Licensing Office of Nuclear Regulatory Commission Washington, D. C. 20555 o
a s
q g~t-
.bm'*
