ML20140A539

Provides Addl Info Re License Amend Request Concerning upper-head Injection Sys.Bash Large Break LOCA Analyses Replaced w/NRC-approved Bart Analyses.Info from Listed Submittals Still Valid Unless Noted

ML20140A539
Person / Time
Site:	McGuire, Mcguire
Issue date:	03/17/1986
From:	Tucker H DUKE POWER CO.
To:	Harold Denton, Youngblood B Office of Nuclear Reactor Regulation
Shared Package
ML19276D358	List: ML20140A526 ML20140A539 ML20140A547 NRC-86-3112, Forwards Results of Bart Evaluation Model Large Break LOCA 10CFR50.46 Analysis,Demonstrating Acceptability of upper-head Injection Removal in Support of License Amend. Info Re Sys Behavior W/ & W/O upper-head Injection Encl
References
TAC-57211, TAC-57212, NUDOCS 8603200308
Download: ML20140A539 (4)

Text

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- - - (rtM) 373 4eas March 17, 1986 Mr. Barold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attention B.J. Youngblood, Director

)i PWR Project Directorate f4

Subject:

McGuire Nuclear Station Docket Mos. 50-369, -370 Dear Mr. Youngbloodt As a follow-up to the conversations of March 6 and 7,1986 between l representatives of the NRO, Duke, and Westinghouse, the following l addii:ional information or clarifications are being provided related to the l requested licensing amendment associated with the McGuire Nuclear 8tation Upper Head Injection (UBI) Systete. In general, the information provided in {

previous transmittals remains valid. The only revision to the previous l transmittals is the replacemant of the large break LOCA analyses, which had been performed using the BASH methodology, with analyses performed using l the NRC approved BART methodology. Due to the number of transmittale exchanged related to the UHI isolation request, the following list is provided to clarify where information related to various' aspects of the program may be found. This list is also intended to verify that the information provided in previous transmittale remains valid except where specifically noted. i Item 1 - Large Break LOCA Analysis The original large break LOCA analysis p ovided to support the isolation of the UHI System (October 2, 1986 transmittal, Appendix A) used the Westinghouse BASH methodology which has not yet been approved by the NRC.

Since chenges to the BASH computer code have been required in order to gain REC approval, the BASH methodology cannot be used to support the isolation of UHL in the upcoming McGuire Unit 2 outage. The large break LOCA analysis has been performed using the Westinghouse BART methodology which has been reviewed and approved by the NRC. The spectrum of large break discharge coef ficients (0.4, 0.6, and 0.8 for minimum SI and 0.6 for maximum SI) have been analysed using the BART methodology and the results provided by Wescinghouse (copy of transmittal letter attached) have shown acceptable results for McGuire assuming UBI isolated, minor changes to Cold Leg Accumulator peraeeters, and a peaking factor (F-Q) of 2.26.

8603200308 060319 PDR ADOCK 05000369 P PDR

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Harold R. Denton March 17, 1986 +.

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Ites 2 - Small Break LOCA Analysis The small break LOCA analysis performed to support the isolation of URL was performed using the NOTRUMP computer code which has been reviewed and approved by the NRC. Detailed information regarding the small break analysis-le provided in the October 2, 1986 transmittal, Appendix A. The information provided in the above transmittal remains applicable.

Item 3 - Non-LOCA Transiente The only FSAR non-LOCA transient which involved the espected actuation of the UEI System is the steamline break transient. The evaluation of the steamline break transients was performed with NRC approved asthodologies and reflected the planned configuration of McGuire with UHI isolated, minor modifications to the cold leg accumulator parameters, and as in the '

aristing FSAR analyses the removal of the Boron Injection Tank has been reflected in the safety analyses. The details of the steamline break analysis is provided la Appendix B of the October 2, 1986 transmittal. l l

Containment reponse was eva.luated in regard to peak temperatures and '

pressures and the discussions provided in the Safety Analysis for URI  ;

Elimination report provided in the October 2,1986 transmittal remain applicable. I Item 4 - Comparison / Explanation of UBI and UHI Isolated Analyses The explanation of the results of the UHI isolated analysis relative 1 to previous analyses with the UHI System assumed operable are provided by the Wastinghouse letter attached.

Item 5 Discussion of Impact of UBI Internals l The major plant differences between McGuire and non-URI Westinghouse plants after the URI isolation is implemented is the URI internals package. The benefits of the reactor vessel internals arrangement at McGuire are discussed in Westinghouse letter attached. ,

Item 6 - Description of Procedures for UHI Isolation The planned isolation of the UHI System and the impact on' plant Technical Specifications and procedures was discussed in the transmittals of December 17, 1985 and January 14, 1986 Plant Technical Specifications will reflect the isolation of the URI system by requiring the UNI isolation valves to be  ;

closed and confirmed to be closed at periodic surveillance intervals.

Modifications to Cold Leg Accumulator pressure and level specifications reflect the essumptions used in the BART and other safety analyses. A summary list of the plant procedures which require changes due to the

] isolation of UHI is provided below1

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Barold R. Denton March 17, 1986 -

Page 3 A) valve position and required actions during a on startu surveillence of UBI' and Cold Leg Accumulator parameters, specific actionsalarms.

related related to maintenance of the UHI System, and response to UH B) of UHI operability, verification of UHI isolation on af t actuation, UBI isolation during a controlled shutdown, and modifications to Cold Leg Accumuistor parameters.

f C) procedures will be. changed to reflect the inopera the changes to Cold Leg Accumuistor parameters.

In addition to the above information, Duke submitted via the Decemb er 23, 1983 transmittal the assessment of the radiological impact e of UHI del ti on.

This assearment is related to the actual removal of the, capping UHI piping of the UBI disconnect and remove upperthehead penetrations, UHI System. and other taska required to ph McGuire involve removal of UHI in the Current plans for the operation of 1987-1988 time period and isointice of UHI removal.-

physical by valve configuration chengts after upcoming outagesthe and until operable dona not involve significant modification to plant sys significant radiation exposure. changes to those plant procedures associated a onalwith occup ti isolation operable do not differ significantly from operationTherefore, the radiolog status, t

with the system in an Duke believes that the information provided above or provided b transmittals and referenced above justify the operation of thy previous e McGuire Nuclear Station with the UBI System isolated during normal operati on. All analyses have been performed using methodologies the NRC and have shown acceptable results se compared to reviewed and a criteri or more restrictive than those defined by the NRC. a equal to effort to respond to the questions and requests of the NRC and in a timelyDu{

thorough manner in order that the licensing amendment s will reque be t l approved in support of the upcoming McGuire Unit 2 outage, If any questions arise regarding the above information , previous i transmittals, the material provided in the attached letter or ccher aspects i

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Earold R. Denton March 17, 1986 Page 4 .

of the UBI isolation project, pleast contact Duke throu;;h normal licensing channels.

Very truly yours,

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Hal B. Tucker aLc/jsa Attachment xc Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Comatission Region II 101 Marietta St., W , Sulta 2900 Atlanta, Georgia 30323 W.T. Orders NIC Resident Inspector McGuire Nuclear Station Darl Hood, Project Manager Division of' Licensing Office of Nuclear Regulatory Commission Washington, D.C. 20555 l

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