ML20204E961

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Advises That Plant Visit Portion of Emergency Feedwater Reliability Evaluation Will Begin on 870331,per NRC .Agenda Listed.Details Will Be Arranged Onsite.W/O List of Participating NRC & Contractor Personnel
ML20204E961
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 03/20/1987
From: Silver H
Office of Nuclear Reactor Regulation
To: Wilgus W
FLORIDA POWER CORP.
References
NUDOCS 8703260113
Download: ML20204E961 (2)


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Docket No. 50-302_

March 20,1987

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,Mr.. Walter S; Wilgus-Vics President, Nuclear Operations

~ Florida Power Corporation.

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ATTN:

Manager, Nuclear Licensing

-,' A Fuel Management i

P40. Box 14042;'M.A.C. H-3

,St. Petersburg, Florida, 33733

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Dear Mr. Wilgus:

As stated.in ourLletter dated February 18, 1987, the plant visit portion'of

.our Crystal River' Unit 3 Emergency Feedwater (EFW) Reliability Evaluation will z

begin March 31, 1987; ~The' participating NRC'and contractor personnel-and their principal. areas of interest are listed in the enclosure.

The:NRR Project Manager, Harley Silver, will also participate.

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The agenda for the visit is expected to follow the general outline'below.

Details will be arranged onsite.

' Tuesday, March 31 (as discussed with your staff) 08'00-09:00 Training for unescorted access'(EOF)

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209:00-09:30 EFIC preview (EOF)

-10:00-12:00 Presentation by FPC (plant site) 01:00-04:30

'Walkthrough

-Wednesday, April'l ~

-08:00-04:30' Discussions with.FPC personnel in four parallel groups Maintenance, Surveillance, and Testing:(maintenance e

. supervisors and technicians) 18C design and maintenance (plant and engineering personnel)

L E0Ps (operators, shift supervisor, engineering)

Reliability Analysis and transient experience (engineering, l

PRA)-

l Thursday, April 2

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'08:00-12:30 Discussions with FPC personnel in four parallel groups

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' Training (training supervisors) 180 (as above)

E0Ps (as above)

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Feliability Analysis and transient experience (as above) i-01:30-03:30 NRC caucus

. 03:30-04:30 Exit meeting L

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8703260113 870320 hDR ADOCK 05000302 PDR l.

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< As discussed with your staff, the team would like to observe and discuss the following if they can be performed conveniently during this visit (also, refer to Enclosure 2, Item 17 of our letter dated February 18,1987).

Simulation / talk-through of recovery of MFW and EFW systems Simulation / talk-through of alternate decay heat removal system (s)

Turbine-driven EFW pump trip reset and restart 30-day EFW train surveillance Your cooperation is appreciated.

Sincerely,

/S/

Parley Silver, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B

Enclosures:

As stated cc w/o enclosure:

See next page NPC ALPDPs PBD-6 FMiraglia ACRS-10 OGC-MNBB 9604 EJordan Ringram BGrimes HSilver RWeller Gray File NThompson 7

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