ML17346A542
| ML17346A542 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/05/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Williams J FLORIDA POWER & LIGHT CO. |
| References | |
| REF-GTECI-A-45, REF-GTECI-DC, TASK-A-45, TASK-OR NUDOCS 8409200207 | |
| Download: ML17346A542 (4) | |
Text
Docket Nos.
50-250 and 50-251 Mr. J.
W. Williams, Jr., Vice President Nuclear Energy Department Florida Power and:Light Company Post Office Box 14000 Juno Beach, Florida 33408"
Dear Mr. Will-iams:
,DI~BUTION c e DR L.PDR Gray File CParrish DMcDonald DEisenhut OELD EJordan JNGrace ACRS 10 September 5,
1984
SUBJECT:
SITE VISIT RELATING TO UNRESOLVED SAFETY ISSUE A-45, DECAY HEAT 'REMOVAL CAPABILITY, TURKEY POINT PLANT UNITS 3 AND 4 As discussed with members of your staff, we would like to arrange for a two day site visit on September ll and 12 at the Turkey Point Plant for NRC staff members and our contractor, Sandia National Laboratory.
A list of attendees is attached.
The purpose of this site visit is to obtain information related to the
.resolution of Unresolved Safety Issue (USI) A-45 on Shutdown Decay Heat Removal Requirements.
The primary objectives of the USI A-45 program are to evaluate the safety adequacy of decay heat removal (DHR) systems in existing light water reactor (LWR) power plants and to assess the value and impact (or cost-benefit) of alternati.ve measures for improving the overall reliability of.the DHR function.
The USI A-45 program is conducting probabilistic risk assessments and.deterministic evaluations of those DHR system and support systems required to achieve hot shutdown and cold shutdown conditions in both pressurized and boiling water reactors.
Integrated systems analysis techniques are being used to assess the vulnerability of DHR systems to various internal and external
- events, including transients, small-break loss of coolant accidents, and special emergency challenges, such as fires, floods, earthquakes, and sabotage.
State-of-the-art cost-benefit analysis techniques are being utilized to assess the net safety benefit of alternative measures to improve the overall DHR system reliability.
We propose to meet with members of your staff on the first day of our visit to provide an overview of the A-45 program, including the scope, preliminary findings and the analytical model used in our analyses of the DHR and supporting systems at your plant.
We also plan to describe the fault tree and event tree methodology being util-ized in the USI A-45 program, including our plans for analyzing special emergency events.
We want to verify specific plant system features, success criteria, operating procedures, and recovery actions.
The second day of our visit will consist of a plant walk-through with special emphasis on those accessible areas 8409200207 840905 PDR ADOCK 05000250 P
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Mr. J.
W. Will,iams, Jr.
September 5,
1984 containing equipment related to decay heat removal capability.
We envision much of our information needs as listed in the enclosure will be satisfied during the discussion and plant walk-through.
Our questions will. deal with realistic.operational and engineering responses to transients and small break LOCA accident scenarios, with additional questions on selected special emergency situations.
Your responses should be viewed as providing information only and not as needed to meet any current requirements.
It is quite likely that some of the scenarios proposed will exceed the current design basis of your plant.
Your responses will be annotated and typed, and a copy of the responses wil'1 be provided for your review prior to use as information or data for our study.
We would appreciate your consideration and cooperation in this matter.
If we can be of assistance or if you have any questions, please
- contact, Mr. Daniel G. McDonald, the NRC project manager for your facility.
Sincerely,
Enclosures:
As stated
/s/SVar ga Steven A. Varga, Chief Operating Reactors Branch ¹1 Division of Licensing cc w/enclosures:
See next page ORBD1:D 8
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