Letter Sequence Other |
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Results
Other: ML20195E282, ML20203N688, ML20205H816, ML20206M282, ML20206M303, ML20206N981, ML20206P886, ML20206U000, ML20207B138, ML20207B153, ML20210S542, ML20211K779, ML20211K784, ML20212B866, ML20212B874, ML20212B884
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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
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
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
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
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
ML20212B8661986-08-0505 August 1986
Proposed Tech Specs,Incorporating Revised Steam Generator Plugging Criteria
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
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
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
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
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
1986-07-16
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s DUKE POWER GOMPANY P.O. DOX M3180 CIIAHLO1TE, N.C. 28242 IIAL 13. TUCKEH TELEPHONE vu a ememenent (704) 373-4531 w~trie r=a==vvvo=
September 22, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTENTION: Mr. B.J. Youngblood, Director PWR Directorate No. 4
Subject:
McGuire Nuclear Station Docket No. 50-369, 50-370
Dear Mr. Denton:
Discussions between our respective staffs in support of the F* criterion for steam generator tube plugging (reference McGuire license amendments 59 and 40 for Units 1 and 2, respectively) involved inquiries into our radiochemistry program at McGuire Nuclear Station for primary to secondary leakage detection and quanti-fication.
It was agreed in a telephone conference on August 12, 1986 between D.
Hood, D. Sellers, and T. Sullivan of your staff and R. Gill, J. Day, and R. Michael of my staff that the radiochemistry information provided in that call would be supplied in a follow-up letter, but would not be required prior to issuance of the amendment; the subject information is provided herein.
The normal surveillance frequency is once weekly.
If a significant change in the leak rate is observed, the surveillance is increased appropriately until the leak l
rate has stabilized, at which time weekly sampling is resumed.
It has been l
generally observed that leak rate changes in steps.
The normal calculation is based upon the ratio of Xenon-133 gn the off gas and in the primary coolant. Based upon 12 scfm offgas with 1 x 10- microcuries/ml Xe-133 and 0.1 microcuries/mi Xe-133 in the primary systca, the leak rate is calculated to be 1.3 gallons per day. If the quantity of offgas is less than 12 i
scfm (typical is 8-12 scfm), the detection limit is proportionately lower. A leak rate of 5-10 gpd is sufficient to pinpoint the affected steam generator.
If for some reason the Xenon calculation does not appear valid, a calculation based upon iodine may be employed.
0 8610080169 860922 1
PDR ADOCK 05000369 I
i P
D PDR
Mr. Harold R. Denton, Director September 22, 1986 Page 2 Steam line monitors which alarm'in the control room and the condenser evacuation system noble _ gas monitor which also alarms in the control room are available to detect any sudden change in leak rate between normal samplings if the leak is of a sufficient magnitude to be of concern.
It is in Duke's interest not only from a safety, but an economic standpoint as 1
well to operate with minimum leakage due to possible secondary side (turbine) contamination, thus we consider the possibility of primary to secondary leakage an important issue.
Very truly yours,
/- l/
g Hal B. Tucker JBD/83/jgm xc: Darl Hood (NRC/0NRR)
E.J. Sullivan (NRC/0NRR)
W.T. Orders (NRC/MS)
I I
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