ML18005A565
| ML18005A565 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/25/1988 |
| From: | Richey R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLS-88-194, NUDOCS 8809010291 | |
| Download: ML18005A565 (4) | |
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ACCELZMYZD DISTRIBUTION DEMONSTRATION SYSTEM v
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8809010291 DOC.DATE: 88/08/25 NOTARIZED: NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION RICHEY,R.B.
Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Submits addi info re 880201 Steam Generator Tube Rapture analysis.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR $ ENCL Q SIZE:
TITLE: OR Submittal:
General Distribution NOTES:Application f'r permit renewal filed.
DOCKET 05000400 05000400 D
RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY,B INTERNAL: ACRS NRR/DE ST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/PMAS/ILRB12 OGC/HDS1 RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD2-1 PD ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DOEA/TSB 11 NUDOCS-ABSTRACT G
01 NRC PDR COPIES LTTR E 5
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LTTR 28 ENCL
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CALL Carolina Power 8 Ught Company P. O. Box 1551
~ Raleigh. N. C. 27602 AUG25 agee R. B. RICHEY, Manager Llcenslng 6 Nuclear Fuel Department SERIAL: NLS-88-190 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-000/LICENSE NO. NPF-63 STEAM GENERATOR TUBE RUPTURE Gentlemen:
Based on recent conversations with the NRC Staff, Carolina Power k Light Company (CPRL) hereby submits additional information to supplement the Steam Generator Tube Rupture (SGTR) analysis transmitted via NLS-88-010 dated February I, 1988.
In the response to Item (I) in Attachment I to the February I, 1988 submittal, CPRL addressed the results of several simulator runs to demonstrate realistic operator action times.
Subsequent to these simulator runs, the active licensed plant operators received additional plant-specific training in the response to a SGTR event.
The training included the critical operator actions required to mitigate the event under design basis conditions and the allowable time to complete these actions to remain within the bounds of the analysis.
To further address operator action times, CPRL will include a Design Basis SGTR scenario (for overfill) in the next scheduled operator simulator requalification training for active operators.
This training is currently scheduled to begin in February 1989 and be completed in May 1989.
Each group of operators will be timed on the critical operator actions to confirm that they remain within the analysis assumptions.
CPRL willdocument the results of the operator action times from the simulator runs via submittal to the NRC within 30 days of their completion.
In the event that the action times assumed in the analysis are found to be nonconservative, the design basis SGTR analysis will be reevaluated using conservative operator action times.
The results of the reevaluation willbe submitted for NRC review and approval prior to startup from the Cycle 3 refueling outage.
Please refer any questions regarding this submittal to Mr. 3ames D. Kloosterman at (919) 836-8055.
Yours ver tru 3DK/dtw (5titi93DK) cc:
Mr. W. H. Bradford Mr. B. C. Buckley Dr. 3. Nelson Grace R. B. Richey o~<
SS09010291 SSOS25 PDR ADOCK 05000400 P
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