ML18005A922
| ML18005A922 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/19/1989 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-89-149, NUDOCS 8905300294 | |
| Download: ML18005A922 (5) | |
Text
ACCELERATED DIBUTION DEMONS~ON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8905300294 DOC.DATE: 89/05/19 NOTARIZED: NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina
-AUTH.NAME AUTHOR AFFILIATION
~ LOFLIN,L.I.
Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Documen't Control Branch (Document Control Desk)
SUEGECT:
Submits addi info re operator action times for steam generator tube rupture accident analysis,per 880825 ltr.
DISTRXBUTION CODE:
A001D COPXES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES:Application for permit renewal filed.
DOCKET 05000400 05000400 S
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~a CNK Carolina Power 8 Light Company MAYS 9889 SERIAL':
NLS-89-149 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 ANALYSIS Gentlemen:
Carolina Power
& Light Company (CP&L) hereby submits additional information concerning operator action times for the Steam Generator Tube Rupture (SGTR) accident analysis for the Shearon Harris Nuclear Power Plant (SHNPP).
By letter dated August 25,
- 1988, CP&L committed to document the results of SGTR operator action times based on simulator runs conducted during the next scheduled licensed operator simulator requalification training session.
Simulator runs from fifteen (15) separate crews of active licensed plant operators were timed in order to validate operator action times assumed in the analyses.
These demonstration runs were conducted on a simulator model which duplicated accident analysis assumption as closely as possible.
Table 1 contains a
comparison of key accident assumptions with assumptions modeled on the simulator during the demonstration runs.
Table 2 contains the summary of operator action times based on these demonstation runs.
The bounding operator action times shown on Table 2 are based on the mean times calculated from the 15 demonstration runs increased by two standard deviations to provide a 95 percent confidence level that these times will be bounding.
By letter dated September 30,
The -following requirement was included in the SER.
The staff concludes that the operator action times from the demonstration runs already performed are close enough to the times assumed in the analysis and that enough conservatism has been incorporated into the overall SGTR analysis to assure the successful mitigation of a SGTR accident if one should 'occur during Cycle 2.
However, in the event that those demonstration runs performed during Cycle 2 generate operator action times that are not bounded by those assumed in the SGTR accident analysis for Harris, the licensee shall submit supplemental SGTR analyses, including radiological consequences, using conservative operator action times based 8905300294 890519 PDR ADDCK 05000400 P
PDC 411 Fayettevilte Street o P. O. Box 1551 o Raleigh, N. C. 27602 ool
Document Control Dote
. NLS-89-149 / Page 2
on those generated during the demonstration runs (excluding main steam line integrity analyses already evaluated in this report.
Since the operator action times generated by the latest demonstration runs are not bounded by the existing SGTR analyses, CP&L will submit the required reanalyses for NRC review prior to startup from the Cycle 3
refueling outage.
NRC approval of the reanalyses is not required prior to startup.
The required SGTR reanalyses is presently scheduled to be submitted by October 1, 1989.
Please refer any questions regarding this submittal to Mr. John Eads at (919) 546-4165.
Yours very truly, Leonard I. L lin Manage Nuclear Licensing Section JHE/jhe cc:
Mr. R. A. Becker Mr.
W. H. Bradford Mr. S.
D. Ebneter
TABLE 1 SGTR SIMULATOR MODEL SGTR Analysis Assumptions SGTR Simulator Model 600 gpm Tube Rupture 100 percent
- power, EOL Reactor Trip at 45 seconds Loss of Offsite Power with Trip One Control Rod Stuck All Pressurizer PORVs Inoperable Auxiliary Spray Inoperable Failed Closed Intact S/G PORV 600 gpm Tube Rupture 100 percent
- power, EOL Reactor Trip at 45 seconds Loss of Offsite Power with Trip One Control Rod Stuck All Pressurizer PORVs Inoperable Auxiliary Spray Inoperable Failed Closed Intact S/G PORV
TABLE 2 STGR OPERATOR ACTION TIMES (minutes)
OPERATOR ACTION EXISTING ANALYSIS ASSUMPTION LONGEST MEAN MEASURED STANDARD TIME 'IME DEVIATION BOUNDING TIME 95')
Identify and isolate ruptured SG (MSIV 6 FW isolated) 10:00 10:55 12:39 1:20 13:35
- 3) Terminate SI following completion of cooldown 5:30 7:06 13:15 2:36 12:17