ML18012A393

Application for Amend to License NPF-63,proposing to Implement Change to Bases for TSs 3/4.6.1.4 & 3/4.6.1.6 Revising Calculated Peak Pressure for MSLB Event

ML18012A393
Person / Time
Site:	Harris
Issue date:	10/08/1996
From:	Robinson W CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18012A394	List: ML18012A393 ML18012A398
References
HNP-96-064, HNP-96-64, NUDOCS 9610160021
Download: ML18012A393 (3)

Text

CATEGORY 1 REGULATORY'INFORMATION DISTRIBUTIONYSTEM (RIDE)

ACCESSION NBR:9610160021 'DOC.DATE: 96/10/08 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Proposes implementing change to Bases for TSs 3/4.6.1.4 6 3/4.6.1.6 to change calculated peak pressure for MSLB event.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution T

NOTES:Application for permit renewal filed. 05000400 E

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 0 LE,N 1 1 INTERNAL: ACRS 1 1 FILE CENTER 1 1 NRR/DE/EMCB 1 1 R DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1. 1 D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris Nuclear Plant OCT 8 1996 SERIAL: HNP-96-064 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 TECHNICALSPECIFICATION BASES CHANGE - CONTAINMENTANALYSIS Gentlemen:

In accordance with 10 CFR 50.36(a), the Harris Nuclear Plant is proposing to implement a change to the Bases for Technical Specifications (TS) 3/4.6.1.4 and 3/4.6.1.6.

In response to NRC Information Notice 87-65, "Plant Operation Beyond Analyzed Conditions,"

an analysis was performed to evaluate the temperature distribution inside containment. That analysis concluded that the containment temperature is normally stratified, and under worst case conditions, would result in an average temperature of 135'F ifthoroughly mixed. Containment temperature and pressure for the limiting MSLB and LOCA scenarios were recalculated using 135'F as the pre-accident temperature. 120'F had been used as the pre-accident temperature in previous analyses.

The revised analyses show that the peak temperature and pressure values remain within the accident acceptance criteria. The peak containment pressure following the most limiting LOCA scenario is essentially unchanged and remains below the peak accident pressure, Pa, as stated in TS 3.6.1.2 and the corresponding Bases. Therefore, offsite dose projections are not affected and there willbe no increase in the consequences of this scenario.

However, the change in calculated peak pressure for the MSLB event willrequire revision of the Bases for Internal Pressure (TS 3.6.1.4) and Containment Structural Integrity (TS 3.6.1.6).

Specifically, the peak pressure expected from a postulated MSLB event is now 41.2 psig, which is an increase above the current Bases peak values of 40.9 psig (TS 3.6.1.4) and 41 psig (TS 3.6.1.6) However, the revised peak pressure of 41.2 psig remains below the maximum

~

internal design pressure of 45 psig, as stated in TS 5.2.2, Design Pressure and Temperature.

96iOih002i 9hi008 POR ADOCK 05000400 p PDR 35OOSI State Road 1134 New Hill NC Tel 919 362-2502 Fax 919 362-2095

Document Control Desk HNP-96-064/ Page 2 The attached retyped Bases pages B 3/4 6-1 and B 3/4 6-2 are provided for your information.

Questions regarding this matter may be referred to Mr. T. D. Walt at (919) 362-2711.

Sincerely, Enclosure LSR/lsr c: Mr. J. B. Brady-NRC Resident Inspector Mr. S. D. Ebneter-NRC Regional Administrator Mr. N. B. Le-NRC Project Manager