ML18009A624

Forwards Addl Info Re Operator Action Times Assumed in Steam Generator Tube Rupture Analyses for Plant,Per 900712 Telcon

ML18009A624
Person / Time
Site:	Harris
Issue date:	08/03/1990
From:	Loflin L CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLS-90-147, NUDOCS 9008090101
Download: ML18009A624 (4)

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'CELERATED DI RIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9008090101 DOC.DATE: 90/08/03 NOTARIZED: NO DOCKET g FACIL:50-400 Shearon Harris Nuclear Power 'Plant, Unit, 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION LOFLIN,L.I. Carolina Power 6 Light Co.

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

SUBJECT:

Forwards addi info re operator action times assumed in steam generator tube rupture ana3,yses for, plant,per 900712 telcon.

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S A

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Carolina Power 8 Light Company gg8 0 3590 SERIAL'LS-90-147 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 STEAM GENERATOR TUBE RUPTURE REANALYSES Gentlemen:

Carolina Power & Light Company (CP&L) hereby submits additional information concerning operator action times assumed in the Steam Generator Tube Rupture (SGTR) analyses for the Shearon Harris Nuclear Power Plant. This information, contained in Attachment 1, was requested by NRC during a telephone conversation on July 12, 1990.

By letter dated December 15, 1989, CP&L submitted the revised SGTR analysis along with a commitment to upgrade the Pressurizer Power-Operated Relief Valve (PORV) manual actuation components, controls, and power supplies to safety-grade for use in the SGTR event only. The plant modification to upgrade two of the Pressurizer PORVs to safet:y-grade for use in the SGTR event will be completed during the next refueling outage (Fuel Cycle 4).

If you have any questions on this submittal or require additional information on this subject:, please contact Mr. J. H. Eads at (919) 546-4165.

Yours very truly, Leonard I. flin Manage Nuclear Licens ng Section Attachment JHE/j he (porv) cc: Mr. R. A. Becker Mr. S. D. Ebneter Mr. J. E. Tedrow 9008090101 900803 PDR ADOCK 05000400 P PDC oof 411 Fayettevilte Street o P. 0, Box 1551 o Raleigh, N. C. 27602 tfl

Attachment 1 SGTR 0 erator Action Times 1989 August 1989 Simulator 2'ebruary-April Simulator Data 15 crews Data~ Time Used Action mean mean + mean In Re-Anal sis

l. Identify and isolate 10 min. 13 mill. 9 min. 13 min.

ruptured S/G (both 55 sec. 35 sec. 4 sec. 35 sec.

steam & FW/AFP lines)

2. Operator action to 4 min. 8 min. 2 min. 8 min.

initiate cooldown 55 sec. 1 sec. 16 sec. 1 sec.

(open S/G PORV)

3. Operator action to 1 min. 2 min. 1 min. 2 min.

initiate RCS 26 sec. 14 sec. 37 sec. 16 sec.

depressurization (from stabilized RCS temperature to open prz. PORV)

4. Time to terminate SI N/A4 N/A 2 min. 3 min.'

(from close prz. 34 sec. sec.

PORV to closing BIT outlet valves)

~

Five simulator runs using 2 non-licensed crews and 3 licensed crews.

~ Mean time of 10 min. 55 sec. based only on 11 simulator runs due to simulation problem modelling time to reactor trip during the first four runs; this only affected the timing of the Operator Action Number 1.

~ Mean time of 4 min. 55 sec. based only on 14 simulator runs due to an operator error on one crew which resulted in an abnormally short operator action time.

4 The simulator runs conducted in February - April 1989, modelled all 3 pressurizer PORVs as ino erable, therefore, timing of Operator Action Number 4 was not possible.

~

Due to the limited sample size, the bounding time was established by conservatively using the longest measured time.

(SGTR)

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