ML20066L017
| ML20066L017 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 01/31/1991 |
| From: | Hairston W ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19310E557 | List: |
| References | |
| NUDOCS 9102060206 | |
| Download: ML20066L017 (5) | |
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Alalx1111a Power r, e,.- n,w %.m Docket No. 50-348 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C.
20555 Gentlemen:
Joseph M. Tarley Nuclear Plant - Unit 1 RTD Dypass Elimination and Steam Generator Tube Plugging Amendment Dy letter dated October 26, 1990, Alabama Power Company proposed a technical specification amendment to support RTD Dypass Elimination and increased steam generator tube plugging.
Submitted as part of the licensing amendment package were WCAP 12613, Revision 1, (proprietary) and WCAP 12614, Revision 1, (non-proprietary).
In the process of providing responses to NRC questions pertaining to the referenced WCArs, it was discovered that the seismic allowance (SA) term associated with the delta-flux penalty for overtemperaturo t>T setpoint was inadvertently omitted from the overtemperature oT uwertainty calculation.
Because the inclusion of an SA uncertainty impacts the overtemperature AT allowable value, the proposed technical specification change and suoporting WCAPs mustberevisedasdiscussedinatelephoneconferencecallonJanuary23, 1991 between Westinghouse, Alabama Power Company, and the NRC.
Technical specification page 2-10 (Attachment 1) has been changed to reflect the new overtemperature oT allowable value.
(Previously proposed revisions to page 2-10 are also included.) WCAP 12613, Revision 2 and WCAP 12614, Revision 2 (Attachment 2) have been revised to reflect the delta flux penalty SA term, the changed overtemperature AT uncertainty calculation, and the new overtemperature AT setpoint allowable value.
Also enclosed with Attachment 2 is Westinghouse authorization letter CAW-91-118 and accompanying affidavit, Proprietary Information Notice, and Copyright Notice. WCAP 12613, Revision 2 contains information proprietary to Westinghouse Electric Corporation which is supported by the affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with cpecificity the censiderations listed in paragraph (b) (4) of Section 2.790 of the Coolssion's regulations. Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CrR Section 2.790 of the bI 91020 _60206 910 _101 o ' >N a 7
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U. S. _ Nuclear Regulatory Comission ATnis Document Control Desk Comission's regulations. Correspondence with respect to the copyright or proprietary aspects of the item listed above or the supporting Westinghouse affidavit should reference letter CAW-91-ll8 and should be addressed to R. P. DiPlazza, Manager of Operating Plant Licensing Services, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania, 15230-0355.
Alabama Power Company has reviewed the significant hazards evaluation provided with the license amendment submitted on October 26, 1990. The conclusions of the significant hazards evaluation remain valid and no changes are considered necessary. With the submittal of this changed page the NRC is therefore requested to approve the Unit 1 RTD Bypass Elimination and 15% tube plugging amendment by February 15, 1991.
Alabama Power Company's Plant Operations Review Comittee has reviewed the proposed change and the Nuclear Operation Review Board will review the change at a future meeting. A copy of this proposed change is being sent to Dr. C. E. Fox, the Alabama State Designee, in accordance with 10 CTR 50.91 (b)(1).
If there are any questions, please advise.
Respec'tfully submitted,.
AIABAMA POWER COMPANY j
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. Hairston, III l
' WGH/REMiGEs sf j 33.06 Attachments SWORN TO AND SUBSCRIBED BEFORE ME cc i - Mr. S. D. Ebneter Mr. S. T. Hoffman THIS3/*IaYOF M...inuaul 1991
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4 ATTACIMIwr i Unit 1 Technical Specifications Changed Page 2-10
I TABLE 2.2-1 (Continued) s; REACTOR TRIP SYSTEM INSTRUMD1TATION TRIP SETPOINTS t-c NOTATION (Continued) 5
.4 t; - Time constant utilized in the rate lag controller for T,,,,
T - 10 secs; 3
+ t;s = The function generated by the lead-lag controller for GI dynamic compensation; 1 + t;s T, & T; = Time constants utilized in the lead-lag controller for ar, T; T; = 0 seconds;
=
1
= Lag compensator on measured T,,,;
1 + T, s T; = Time constant utilized in the measured T,,, lag compensator, T,
= 0 see; 5
s = Laplace transform operator, see f2(M) = 0 for all E.
Note 3: The channel's maximum trip point shall not exceed its computed trip point by more than 2.6 percent.
l Note 4: Pressure value to be determined during initial startup testing. Pressure value of f 55 psia to be used prior to determination of revised value.
4 Note 5: Pressure value to be determined during initial startup testing.
Note 6: The channel's maximum trip point shall not exceed its computed trip point by more than 2.9 percent.
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MTAOMENr 2 l
WCAP-12613, "RTD Dypass Elimination Licensing Report for J. M. Farley Revision 2 Nuclear Plant Units 1 and 2" (Westinghouse Proprietary Class 2)
WCAP-12614, "RTD Dypass Elimination Licensing Report for J. M. Farley Revision 2 1A.iclear Plant Units 1 and 2" (Westinghouse Proprietary Class 3)
CAW-91-118
" Application for Withholding Proprietary Information from Public Dicelosure" (Westinghouse letter with enclosures dated January 23, 1991) l l
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