ML20058E337
| ML20058E337 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/26/1990 |
| From: | Hairston W ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19310C816 | List: |
| References | |
| NUDOCS 9011070135 | |
| Download: ML20058E337 (3) | |
Text
Alibims Po er Comptny 40 invemess Centu Parkway.
Post Ottica Dox 1295 Darmingham, Alabama 35201 Telephone 205 868-5501
-y W. G. Hairston, Ill Senior Vice President -
we r One,.nons AlabamaPower October 26~, 1990 the sovtten eActre syvem Docket No. 50-348 U. S. Nuclear-Regulatory Commission ATTN:
Document Control Desk Washington, D. C. 20555 Gentlemen Joseph H. Farley Nuclear Plant - Unit 1 RTD Bypass Elimination and Steam Generator Tube Plugging Amendment i'
To reduce future occupational radiation exposure and maintenance requirements, Alabama Power Company plans to eliminate.the Resistance i
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Temperature Detector (RTD) Bypass System at Farley Nuclear Plant Unit 1 by.
' removing'the. associated. system valves, piping, snubbers and selected supports. The; existing.RTD Bypass System vill be replaced with thermovell mounted,; fast response dual element RTDs installed directly into the reactor coolant l piping., It :is also' anticipated that the number of Unit -1 4
steam generator tubes: requiring corrective action may be in excess of the l-10% technical. specification limit. Therefore, evaluations and analyses have been performed;to allow an-average of 15% steam generator tube j
plugging vith a peak: limit.of-20% in any-one steam. generator, and an j
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approximate'l.5% reduction in the~ Reactor Coolant System-(RCS) thermal design flow. lTo support implementation of-the RTD Bypass Elimination modification 1and-the. increased steam generator tube plugging limit, Alabama N:
Power Company. proposes.that the'Farley Nuclear Plant Unit 1 Technical-Specifications; be' amended by revising certain reactor core safety limits, 1
reactor trip 1 instrumentation setpoints, and DNB parameters.
1' For.the increased' steam; generator tube plugging limit, all LOCA and
.non-LOCA analyses werel reviewed.. The large break LOCA,. major rupture of a-4 main feedvater pipe, uncontrolled bank withdrawal from suberitical, partial L
. loss'of forcedsreactorJcoolant: flow,-single reactor coolant pump locked
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3 rotor', and steam generator tube rupture accidents vere reanalyzed. The.
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potentia 11 effects ofi.the RTD Bypass Elimination modification vere included in the reviews.'and analyses' required for.the increased tube plugging limit j
by' performing'Farley' specific'RCS temperature and flow uncertainty i
evaluations. 'To eliminate the potential for control and-protection system interaction, tvo median (signaliselectors vill be incorporated into the Reactor: Control System for. the' RCS -average temperature and dif ferential temperature control functions.
It should'be noted that the analysis for the large break LOCA;may'be affected by resolution of a potential issue.
j concerning the Westinghouse ECCS evaluation model power distribution assumption.
This submittal: vill be updated, if required, upon resolution NOTE.' n src
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U. S. Nuclsar R gulatory Commission RTD Bypass Elimination Amendment Page 2 I
of the issue. Additionally, the results of the steam generator tube rupture analysis have changed not only due to the reduced thermal design l
flov and increased plugging limit, but also due to using current inputs for the Farley licensing basis methodology.
The proposed changes to the Technical Specifications are provided in The technical justification for the RTD Bypass Elimination modification and the associated technical specification changes is provided in Attachment 2 as VCAP 12613, Revision 1 (Vestinghouse proprietary class
- 2) and VCAP 12614, Revision 1 (Vestinghouse proprietary class 3).
The technical justification for implementation of the median signal selector with RTD Bypass Elimination is provided in Attachment 3 as VCAP 12675 (Vestinghouse proprietary class 2) and UCAP 12676 (Vestinghouse proprietary class 3).
The technical justification for the increased steam generator tube plugging with a reduced thermal design flow and the associated technical specification changes is provided in Attachment 4 as VCAP 12694 (Vestinghouse proprietary class 3).
i Also enclosed with Attachments 2 and 3 are Westinghouse authorization letters (CAV-90-078 and CAV-90-067, respectively) and accompanying affidavits, Proprietary Information Notices, and Copyright Notices.
VCAP 12613, Revision 1 and VCAP 12675 contain information proprietary to Westinghouse Electric Corporation which is supported by the affidavits j
signed by Vestinghouse, the owner of the information.
Each affidavit sets forth the basis on which the.information may be withheld from public-disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b) (4) of Section 2.790 of the-Commission's regulations. Accordingly, it is respectfully requested that the information which is proprietary to Vestinghouse be withheld fram public disclosure in accordance with 10 CFR Section 2.790 of.the Commission's regulations.
Correspondence with respect to the copyright or l
proprietary aspects of the items listed above or the supporting Vestinghouse affidavits should reference letters'CAV-90-078 or CAV-90-067 and should be addressed to R. A. Viesemann, Manager of Regulatory and i
Legislative-Affairs, Westinghouse Electric Corporation, P. O. Box 355, u
Pittsburgh, Pennsylvania, 15230-0355, t
.Farley Nuclear Plant Unit 1 is presently scheduled to shut dovr. for a refueling outage in March 1991.
In order to complete the required preparations and finalize the schedule for implementation of the RTD Bypass
>b Elimination modification, Alabama Power Company requests that.the NRC a
review and approve these proposed changes by February 15, 1991.
In addition, it should be noted that Alabama Power Company previously submitted a similar technical specification change request for an increased steam generator tube plugging limit by letter dated July 31, 1990-in support of the Unit 2 October 1990 refueling outage.
Future plans also include the implementation of the RTD Bypass Elimination modification-in Unit 2 during the subsequent refueling in March 1992.
Alabama Power Company has determined that the proposed changes do not involve a significant hazards consideration.
In accordance with 10 CFR 50.92 a significant hazards consideration evaluation is provided as Attachment 5.
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U. S. Nuci mr R0gulatory Commission RTD Bypass Elimination Amendment Page 3 Alabama Power Company's Plant Operations Review Committee has reviewed the proposed changes and the Nuclear Operation Review Board vill review the changes at a future meeting. A copy of these proposed changes is being sent to Dr. C. E. Fox, the Alabama State Designee, in accordance with 10 CFR 50.91 j
(b)(1).
If you have any questions, please advise.
Respectfully submitted, j
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t V. G. Ilairston, III VGH,III/HGE:mgd 23,28 Attachments SVORN TO AND SUBSCRIBED BEFORE ME j
cci Hr. S. D. Ebneter Ti!IS J/oY DAY _OF [ M g,1990 l
Mr. S. T. Iloffman Hr. G. F. Mc::vell Jd[It R u d m //b t f
Dr. C. E. Fox Notary Pq)lic
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