IR 05000250/1979003
| ML17338A662 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/08/1979 |
| From: | Martin R, Vogtlowell R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17338A660 | List: |
| References | |
| 50-250-79-03, 50-250-79-3, 50-251-79-03, 50-251-79-3, NUDOCS 7904260459 | |
| Download: ML17338A662 (5) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report Nos.:
50-250/79-03 and 50-251/79-03 Licensee:
Florida Power and Light Company P, 0.
Box 529100 Miami, Florida 33152 Facility Name:
Turkey Point 3 and
Iicense Nos:
DPR-31 and DPR-41 Inspect'ion at Turkey Point te Inspector:
R. J. Vogt-Lo ell, Reactor Inspector
)
Approved by:
R.
D. Martin, Section Chief, R NS Branch Bt6/ //
Date Signed Date ig d
SUMMARY Inspection on February 6-9, 1979 Areas Ins ected This routine, unannounced inspection involved 32 inspector-hours onsite in the areas of refueling activities for Unit 3 and preparation for refueling of Unit 4.
Results Of the two areas inspected, no apparent items of noncompliance or deviations were identifie DETAILS Persons Contacted Licensee Em lo ees
-"H. E. Yaeger, Plant Manager
>J.
K. Hays, Plant Superintendent Nuclear B.
C. Kilpatrick, Assistant Maintenance Superintendent
- Nuclear T. Nox, Supervisor - Primary Maintenance J. J. Sullivan, Refueling Coordinator D. Haas, Technical Supervisor V. Kaminskas, Reactor Engineering Supervisor RE Mende, Reactor Engineer C. Becker, Reactor Engineer Other licensee employees contacted included operators and office personnel.
-Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on February 9, 1979, with those persons indicated in paragraph 1 above.
The inspector noti-fied the licensee that he would be returning the next day, February 10, 1979, to witness potions of actual fuel handling on the refueling deck.
However, as of February 11, 1979, -fuel handling had not commenced due to equipment malfunction in the fuel transfer canal.
Licensee Action on Previous Ins ection Findin s Not inspected.
4.
Unresolved Items
.5 Unresolved items were not identified during this inspection.
Unit 3 Refuelin Activities a
~
Refueling Reference Documents The following reference documents relating to the Cycle V to Cycle VI refueling outage were reviewed by the inspector:
"Cycle Length Analysis - PTP3-V" - issued by the Nuclear Analysis Department (NAD) of FPSL on December 6, 1978.
This document provided the latest estimates of the cycle length based on operating data and design calculations through 12/5/7 "Core Follow Data -
PTP 3" - transmitted via NAD-2064.
The data for PTP 3 for November 1978 included: boron letdown curve, hourly power history, daily burnup tabulation, moderator temperature, hourly xenon and samarium history, EOC calculation of curve fit of daily boron measurements.
"PTP 3 - Cycle V Bi-Monthly Report No.
2" - issued by NAD and covering reactor operation from August 1 - September 30, 1978.
"Reactor Engineering - Unit 3 - Boron Follow Book" - indicates that EOC V occurred on 1-1-79 when the unit was taken off the line at 0124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br />.
A summary of the last few days of operation is presented in tabular form as follows:
Date Time Boron Burnup Bank T. Avg.
(PPM)
MWD/MTU EFPH g Power Position (4F)
12/28 12/29 12/30 12/31 1/1 0822 0852 1015 0815 0338 31.4 25.8 22.1 20.6 55.7 8618.8 8649.4 8680 8708.6 8709 6745.5 6769.4 6793.4 6815.8 6816.1 100 100 100 100 228 573 225 573 224 573 228 573
"Reload Safety Evaluation -
TPP - Unit 3, Cycle 6" - issued by Westinghouse - Nuclear Fuel Division, in October 1978.
The following design parameters for Cycle VI were presented:
2200 MWt Core Power 2250 psia system pressure 546.2 F Core Inlet Temperature 263,130 GPM Total Thermal Design Flow 5.58 kw/ft Average Linear Fuel Power Density
"The Nuclear Design and Core Management of the TPP Unit No.
3, Cycle 6 -
WCAP 9433" Issued by Westinghouse in November 1978 and containing the results of nuclear design calculations for Cycle
of TP Unit 3.
Included is information on fuel loading, power and burnup distributions, reactivity coefficients, control rod worthsp kinetics, isotopic inventory, and other data pertinent to operation of the nuclear reactor.
b.
Refueling Procedures The following plant procedures were reviewed by the inspector:
AP 0149.1 Special Nuclear Material Accountability OP 16000.1 Limitations and Precautions for Handling Fuel'Assemblies OP 16009.2 Site Removal of New Fuel Assemblies from Shipping Containers
OP 1407.21 Refueling Activities Check-Off Iist OP 16008.1 Accident Involving New Fuel OP 16008.2 Accident Involving Spent Fuel OP 16002.6 Preparations and Precautions for Refueling Fuel Shuffle OP 16002.5 Refueling Core Shuffle OP 16004.2 Refueling System Interlocks Verification MP 16701.1 Gautry Crane Inspection and Preventative Maintenance In addition, the inspector reviewed the microfilmed copies of the
"New Fuel Receiving Records",
"Container Contents
- Fuel Assembly Inspection Records" and "Westinghouse Nuclear Fuel Division Quality Release Forms" for the 40 new fuel assembly that will be placed in the core for Cycle VI operation.
c.
Refueling Deck Observation The inspector toured the refueling deck area for the purpose of observing the refueling activities in progress.
The plant per-sonnel were involved, at the time, with uncoupling of the control rods for the subsequent removal of the upper intervals.
Within the area of the Unit 3 refueling activities inspected no items of noncompliance or deviations were identified.
Unit 4 Pre aration for Refuelin The inspector discussed the upcoming Unit 4 refueling outage with cognizant plant personnel and reviewed a listing of the procedures pertinent to the refueling activity. scheduled for the refueling outage.
No items of noncompliance or deviations were identified within the areas inspecte v
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