ML18010B011
| ML18010B011 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 02/10/1993 |
| From: | Mccarthy D CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-93-039, NLS-93-39, NUDOCS 9302170292 | |
| Download: ML18010B011 (5) | |
Text
ACCEI.ERA D DOCUMENT DIST UTION SYSTEM REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION 1RR:9302170292 DOC.DATE: 93/02/10 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH.NAME AUTHOR AFFILIATION MCCARTHY,D.C.
Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides formal response to NRC question asked during 930129 meeting re limiting condition for operation action requirements, DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:Application for permit renewal filed.
05000400 RECIPIENT ID CODE/NAME PD2-1 LA LE,N INTERNAL: ACRS NRR/DOEA/OTSB11 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS1 EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD2-1 PD NRR/DET/ESGB NRR/DST/SELB 7E NRR/DST/SRXB 8E R
G FILE 01 NSIC COPIES LTTR ENCL 1
1 1
1 1
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO EUMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
0 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 ENCL
0
(
SNK Carolina Power 8 Light Company jIFEB >0 ]S93 SERIAL:
NLS-93-039 10 CFR 50.90 United States Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEMENTAL INFORMATION LIMITING CONDITIONS FOR OPERATION (LCO) ACTION REQUIREMENTS Gentlemen:
On January 29, 1993, Carolina Power 6 Light Company (CPQL) met with the NRC in White Flint, Maryland, to discuss licensing issues related to the Shearon Harris Nuclear Po~er Plant (SHNPP).
One of the issues discussed with the NRC was CPGL's pending Request for License Amendment related to LCO Action Requirements.
The purpose of this letter is to provide a formal response to an NRC question asked during that meeting.
With respect to the Request for License Amendment, and specifically the portion dealing with Technical Specification 3.7.1.1, Safety Valves, the NRC asked whether the SHNPP Main Steam Safety Relief (MSSR) valves provide a safety function in Mode 4 (Hot Shutdown).
The SHNPP MSSR valves are spring-loaded with fixed setpoints staggered between 1170 psig and 1230 psig.
The design function of these valves is to protect the Main Steam piping and steam generator shell from overpressurization.
In Mode 4, with steam generator pressure at approximately 3.50 psig nr less, the MSSRs are closed and cannot be manually operated to remove heat load.
Neat removal via the MSSRs is assumed in several of the Final Safety Analysis Report (FSAR) Chapter 15 accident analyses; but in all cases, the MSSRs function to maintain the reactor in a stable condition in Mode 3 (Hot Standby).
For Chapter 15 analyses that require the unit to be cooled down and depressurized, such as the Steam Generator Tube Rupture (SGTR) analysis, the MSSRs serve no function and cannot be utilized to place or maintain the unit in Mode 4.
- Further, the MSSRs are containment isolation valves and are requ'ired to be closed in Mode 4, as required by Specification 3.6.3.
Therefore, the MSSRs provide no safety function in Mode 4 related to the removal of heat from the RCS.
93022702'P2 930210 PDR
- DOCK 05000400 P
PDR 411 Fayettevitte Street o P. O. Box 1551 o Raleigh. N. C. 27602 (19'l98ttP)
Document Control De NLS-93-039 / Page 2
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Please refer any questions regarding this submittal to Mr. R.
W. Prunty at (919) 546-7318.
Yours very truly, David C. McCarthy Manager Nuclear Licensing Section LSR/)bw cc:
Mr. Dayne H. Brown Mr. S.
D. Ebneter Mr. N. B. Le Mr. J.
E. Tedrow
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