ML18009A301
| ML18009A301 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/15/1989 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18009A302 | List: |
| References | |
| NLS-89-320, NUDOCS 8912190109 | |
| Download: ML18009A301 (8) | |
Text
I REGULATORY~FORMATION DISTRIBUTIONM (RIDE)
)ACCESSION NBR:8912190109 DOC.DATE: 89/12/15 NOTARIZED: YES DOCKET CIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 UTH.NAME AUTHOR AFFILIATION TTER,A.B.
Carolina Power a Light Co.
RECIP.NAME RECIPIENT AFFILIATION
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t Document Control Branch (Document Control Desilt'~+
SUBJECT:
Forwards proprietary WCAP-12403 6 nonproprietary WCAP-12404, "LOFTTR2 Analysis for Steam Generator Tube Rupture W/Revised Operator Action Times for Shearon Harris Nuclear Power Plant."
WCAP-12403 withheld (ref 10CFR2.790(b)(4)).
t DISTRIBUTION CODE:
AP01D COPIES RECEIVED:LTR I
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SIZ TITLE: Proprietary Review Distribution Operate.ng Reactor gei/gd NOTES:Application for permit renewal filed.
05000400 B
01 E TERNAL: LPDR RECIPIENT ID CODE/NAME PD2-1 LA BECKER,D INTERNAL: ACRS REC FILE COPIES LTTR ENCL 1
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 17 ENCL 14
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Cy sf CHAL Carolina Power & Light Company P.O. Box 1551
~ Rateigh, N.C. 27602 OEC 1 5 589 A. B CUTTER Vice President Nuclear Services Department United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SERIAL:
NLS-89-320 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 STEAN GENERATOR TUBE RUPTURE REANALYSES Gentlemen:
Carolina Power
& Light Company (CP&L) hereby submits the revised Steam Generator Tube Rupture (SGTR)'nalysis for the Shearon Harris Nuclear Power Plant (SHNPP).
This reanalysis is submitted in response to the NRC SGTR Safety Evaluation Report (SER) dated September 30, 1988.
The revised SGTR analysis is contained in Westinghouse report WCAP-12403, "LOFTTR2 Analysis for a Steam Generator Tube Rupture With Revised Operator Action Times for Shearon Harris Nuclear Power Plant" (Proprietary) and is included as Attachment 1.
The non-proprietary version, WCAP-12404, is included as Attachment 2.
The SHNPP SGTR analysis was reanalyzed to reflect revised operat:or action times based on simulator demonstration runs.
These times are listed in.
This updated SGTR analysis utilizes the same methodology as the previous SGTR analyses.
However, in addition to revised operator action times, credit has been taken for the operation of the pressurizer power operated relief valves (PORVs) to perform the reactor coolant system depressurization in this updated analysis.
A meeting with NRC staff to discuss this revised SGTR analysis was held on October 12, 1989.
As requested in 'that meeting, a discussion of the existing PORV capability for the SGTR event is included as Attachment 4.
This discussion documents that although the existing PORVs are not safety-grade, they are extremely reliable plant components, which are required to be operable by existing plant Technical Specifications and are capable of performing the depressurization function for this event.
However, in order to provide additional assurance of overall reliability, CP&L hereby commits to upgrade the pressurizer PORV manual actuation components,
- controls, and power supplies to safety-grade for use in the SGTR event only.
This will include Class lE manual control circuits and power supplies, safety grade pneumatic power source and supply, and qualified (environmental and seismic) components whose functions are required for the SGTR event (ie. check valves and solenoid operated valves in the pneumatic supply, etc.).
This upgrade is scheduled to be completed prior to restart from the next refueling outage (Fuel Cycle 4).
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Document Control Desk NLS-89-320 / Page 2
As WCAP-12403 contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit (Attachment 5) 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 specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.
Accordingly, it i,s respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR2.790 of the Commission's regulations.
Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Westinghouse Affidavit should reference CAW-89-116 and should be addressed to R. A. Wiesemann, Manager of Regulatory
& Legislative Affairs, Westinghouse Electric Corpora'tion, P.O.
Box 355, Pittsburgh, Pennsylvania 15230-0355.
Please refer any questions regarding this submittal to Mr. John Eads at (919) 546-4165.
Yours very tr A. B. Cutter JHE/jhe(sgtr) cc:
Mr. R. A. Becker Mr. J.
E. Tedrow Mr. S.
D. Ebneter
0
December 29, 1989 NVZE TO:
James C. McKnight IRM/DCB FROM:
Richard A. Becker, Project Manager NRR/DHP/PD II-1
SUBJECT:
CONFIRMATION OF APPROVAL TO REPRODUCE CP&L SGTR ANALYSIS, SUBMITTED DECEMBER 15, 1989 CONTAINING PROPRIETARY AND COPYWRITED MATERIAL This note confirms our telephone discussion on this date transmitting verbal permission t'o reproduce the CP&L submittal on Steam Generator tube rupture
- analysis, dated December 15, 1989.
This submittal contains Westinghouse proprietary and copywrited material.
The reproduction of this submittal is for records storage and distribution.
The proprietary information will be withheld from public distribution.
ichard A. Becker, Project"Manager NRR/DRP/PD II-1
0