ML20059A014
| ML20059A014 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/14/1993 |
| From: | Rehn D DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19311B289 | List: |
| References | |
| NUDOCS 9312290142 | |
| Download: ML20059A014 (5) | |
Text
DukePowerCompany D. L Rim Catawba Kudear Generation Department tice hesident
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4800ConcordRoad (803)3313205 Office York,5C2976 (803)&T13C6 Tax DUKEPOWER Decenmer 14,1993 r
U. S. Nuclear Regulatory Conunission j
Attention: Document Control Desk Washington, D. C.
20555 i
Subject:
Catawba Nuclear Station Docket Nos. 50-413 and 50-414
-l Supplement To Technical Specification Amendment i
Renewal Of Steam Generator Tube Interim Plugging Criteria for Unit 1 Cycle 8 1
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On October 5,1993, Catawba Nuclear Station submitted a proposed Technical Specification Amendment requesting renewal of the voltage-based steam generator tube interim plugging.
criteria for Unit I for Cycle 8. This submittal was discussed with the NRC staff during teleconferences which were held on December 6, 8 and 9,1993. During these discussions, the NRC staff called into question the exclusion of certain data points fmm Table 4-1 and the burst correlation of Figure 4-1 of WCAP-13854. As a result of these discussions, the NRC staff has requested that data point R28C41 be placed into the data base at a calculated leak rate together with model boiler specimens 598-1 and 598-3 at their measured leak rates and be used in the leakage correlation. Inclusion of the R28C41 data point has resulted in an increase in the total projected primary-to-secondary leakage under steam line break conditions to 29.35 gpm at the end of Cycle 8, which exceeds the maximum leakage I
previously submitted. This revised leakage value was calculated in accordance with the methodology given in Draft NUREG-1477 and utilizes the msults of the recently completed j
Unit i End-Of-Cycle (EOC) 7 steam genemtor tube inspection, projected to EOC 8 conditions. Without inclusion of R28C41 in the data base, the projected leak rate applying Draft NUREG-1477 methodology at 98% confidence would be 19.9 gpm.- slightly higher l
than the 17.5 gpm leak rate previously submitted.
Since the new calculated leakage value exceeds the liinit previously submitted, Catawba is -
l proposing to increase-the primary-to-secondary leakage limit given in Surveillance-Requirement 4.4.5.4.a.13)l. to 30.0 gpm and decrease the Unit I limit on specific activity q
l of the reactor coolant given in Technical Specification 3.4.8.a. to 0.58 microCuries per j
l gmm dose equivalent I-131. This decrease in specific activity ensures that the dose
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consequences from the increased steam line break leakage will be less than the pertinent i
i 10 CFR 100 limits.
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U, S. Nuclear Regulatory Commission December 14,1993-Page 2 It is requested that these changes receive an expedited review and approval in order to meet the schedule for_ the Catawba Unit 1, Cycle 8 startup (entry into Mode 4). Startup is currently scheduled for December 22,1993.
The marked up Technical Specification pages are given on Attachment 1. Attachment 2 contains the Technical Justification for these changes, and Attachment 3 contains the No Significant Hazards Analysis and EnvironmentalImpact Statement.
Enclosed as Attachment 4 is a letter from Westinghouse which provides the results of the new main steam line break leakage calculations which are consistent with the methodology given in Draft NUREG-1477 and utilizes data point R28C41 and the results of the recently completed Unit i EOC 7 steam generator tube inspection.
In addition, enclosed as Attachment 5 (3 copies), is the revised Catawba offsite dose analysis engineering calculation and results which utilize the new value for steam line break steam generator tube leakage. The revised calculation also includes a small amount of new infonnation which is noted by side-bar. These small changes do not affect the methodology for iodine spiking or the behavior of the defective fuel. Attachment 5 contains proprietary models, equations, calculations and discussions which develop an alternative methodology for demonstmting that offsite dose analyses associated with a postulated main steam line break are within acceptable limits. This document contains infonnation which constitutes "tode secrets and commercial or financial infonnation obtained and developed by Duke Power Company which is privileged or confidential" and is therefore exempt' from disclosure pursuant to Section 552 (b)(4) of the Freedom ofInfonnation Act,5 U.S.C. 6 552, as amended, and applicable NRC regulations (10 CFR 2.790 (a)(4) and (b)).
Duke Power Company requests that the revised dose analysis calculation in Attachment 5 he withheld from public disclosure because it contains trade secrets and confidential commercial information, disclosure of which would result in substantial hann to Duke Power Company's competitive position and its ability to obtain technical infonnation necessary to maximize the effectiveness of its nuclear operations. Duke Power Company believes that nondisclosure of this proprietary infonnation would.not detract from the ability of the public to be fully apprised as to the basis for and affects of this dose analysis calculation.
Included in Attachment 5 is the sworn declaration of D. L. Rehn, Site Vice-President, Catawba Nuclear Station. Duke Power Company, which provides the basis for withholding from public disclosure the proprietary dose analysis calculation given in Attachment 5.
Should the NRC deem it necessary to allow inspection of these materials by NRC -
contmetor personnel who may be asked to review this request, Duke Power Company would be willing, in that limited instance, to supply a protective agreement under the tenns of which the document could be so inspected.
4 i
i Nuclear Regulatory Commission -
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December 14,1993 j
Page 3 Please note that when these changes are approved, the Technical Specifications for Catawba
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Unit I will be different from Unit 2 with regard to specific activity of the reactor coolant.
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The page numbers for each unit will be differentiated and the specifications will be printed l
on differently colored paper.
t Pursuant to 10 CFR 50.91 (b)(1), the appropriate South Carolina official is being provided
.f a copy of this amendment change reque'st.
l During the teleconference held on December 6,1993, Catawba infonned the NRC staff of four specific findings related to the Unit i EOC 7 steam generator tube inspection.
Catawba wishes to confinn these findings as follows:
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- 1) All Hot Leg Tube Support Plate.(TSP) indications whose dent voltages exceeded 4 volts were inspected with an MRPC probe, i
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- 2) No indications at the flow distribution baffle were identified.
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- 3) No unexpected inspection findings relative to the assumed characteristics of the flaws at the TSP elevations were identified.
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- 4) No detectable circumferential indications or detectable indications extending outside a
the thickness of the TSP were identified.
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Very truly yours, I
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D. L. Rehn Attachments i
RKS/
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Nuclear Regulatory Commission December 14,1993 Page 4 i
xc: Mr. S. D. Ebneter j
Regional Administrator, Region II U. S. Nuclear Regulatory Commission j
101 Marietta Street, NW, Suite 2900 Atlanta, GA 30323 Mr. Heyward Shealy, Chief q
Bureau of Radiological Health South Carolina Depanment of Health &
Environmental Control 2600 Bull Street Columbia, SC 29201 Mr. R. J. Freudenberger i
NRC Resident Inspector Catawba Nuclear Station i
Mr. Robert E. Manin, Project Manager i
ONRR Mr. William T. Russell, Associate Director Inspection & Technical Assessment ONRR I
American Nuclear Insurers c/o Dottie Shennan, ANI Library l
The Exchange, Suite 245 270 Fannington Avenue Fannington, CT 06032 M & M Nuclear Consultants i"
l166 Avenue of the Americas New York, NY 10036-2774 1
2 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 3033.9
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U. S. Nuclear Regulatory Conunission
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'D. L. Rehn, being duly sworn, states that he is Site Vice-President,' Catawba Nuclear -
e Station; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission this revision to the Catawba Nuclear Station - Technical Specifications, Appendix A to License Nos. NPF-35 and NPF-52; and that all statements and matters set forth therein are true and correct to the best of his knowledge.
D.(.Rehn' i
i Subscribed and sworn to before me this
/4" day of I)ec,1993.
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f My Commission Expires:
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