IR 05000250/1979013
| ML17338A872 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/22/1979 |
| From: | Martin R, Vogtlowell R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17338A871 | List: |
| References | |
| 50-250-79-13, 50-251-79-13, NUDOCS 7907240184 | |
| Download: ML17338A872 (9) | |
Text
<P.S RECI P0 Cy
+a**+
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos.
50-250/79-13 and 50-251/79-13 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, Florida 33101 Facility:
Turkey Point 3 and
Docket Nos.
50-250 and 50-251 License Nos.
DPR-'31 and DPR-41 k
Inspection at Turkey Point Site near Homestead, Florida Inspector:
R. J. Vogt-Lowell Approved by:
R. D. Marti
, Section hief, RONS Branch 5'~ g $~
7'ate Signed Q~ZZ 7 Date Signed SUl9fARY Inspection on May 8-11, 1979 Areas Ins ected This routine, unannounced inspection involved 28 inspector-hours onsite in the areas of startup testing results for Unit 3 and refueling activities for Unit 4.
Results Of the two areas inspected, no apparent items of noncompliance or deviations were identified.
'T9072 g I
DETAILS 1.
Persons Contacted Licensee E
lo ees
+H. E. Yaeger, Plant Manager
+J.
K. Hays, Plant Superintendent
- Nuclear
- J. E. Moore, Operations Superintendent
+D.
W. Jones, QC Supervisor
+R. J.
Spooner, QA Supervisor
+V. A. Kaminskas, Reactor Supervisor
+R.
G. Mende, Reactor Engineer C. J. Becker, Reactor Engineer L. Huenniger, Refueling Outage Coordinator Other licensee employees contacted included operators and office personnel.
+Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on May 11, 1979, with those persons indicated in Paragraph 1 above.
The licensee made the following commitments during the meeting:
a.
Revise Appendix B to O.P.
0204.3
'InitialCriticality After Refueling" to require calibration of the reactivity computer for negative values of reactivity in addition to the presently required positive reactivity calibration.
Such revision would be in effect prior to the use of the reactivity computer for startup testing of Unit 4 which is presently in a refueling outage.
(251/79-13-01)
b.
Issue a Special Instruction requiring completion of the "Turkey Point Units 3 and 4 Limiting Conditions for Refueling Operations" (table
of this report) prior to re-insertion of the last nine fuel assemblies in the Unit 4 core.
(251/79-13-02)
3.
Licensee Action on Previous Ins ection Findin s Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
~
~
5.
Startu Testin Results - Unit 3, The inspector reviewed the following completed operating procedures performed following the cycle V to cycle VI refueling outage:
-2" O.P.
0204.3 "Initial Criticality After Refueling" Appendix A - Nuclear Heating Determination Appendix B - Reactivity Computer Checkout O.P.
12702.1
"Normal Alignment of Reactivity Computer" O.P.
0204.5 "Nuclear Design Check Tests" Appendix A - Boron Endpoint Measurements Appendix B - Isothermal Moderator Temperature Coefficient Appendix C - Low Power M/D Flux Map Appendix D - Rod Worth Also, portions of the preliminary Startup Report prepared by the licensee in addition to the Reload Safety Evaluation for the cycle were examined by the inspector.
After discussions with the reactor engineering personnel, the inspector noted that the data acquisition, data reduction, and test package documen-tation practices could be improved.
Traceability of data and results was oftentimes cumbersome.
The Reactor Supervisor attributed, in part, the conditions observed by the inspector, to the experience level of the reactor engineers who were basically relatively new to the job.
The inspector suggested that the test engineers be encouraged to take data as accurately as possible and that they be reminded that the test results packages are QA documents subject to the provisions of the Operations QA Manual.
The Reactor Supervisor was receptive to the inspector's comments.
Within the areas inspected, no items of noncompliance or deviations were identified.
6.
Refuelin Activities - Unit 4 The Cycle V to Cycle VI refueling outage for Unit 4 commenced with the unit shutting down on April 4, 1979.
The Reactor Engineering Boron Follow book indicated the following pre-shutdown readings taken at 0802 on 4/4/79:
Boron Concentration:
1.53 ppm Burnup
4231 MWD/MTV Power
100$
Official control room copies of the following procedures (in their applicable stages of completion) were reviewed by the inspector:
O.P.
1407.21 Refueling Activities Checkoff List O.P.
16001.2 Technical Specifications Surveillance Requirements for Core Refueling
O.P.
16002.5 Refueling Core Shuffle O.P.
16002.6 Preparation and Precautions for Shuffle O.P.
16004.2 Refueling System Interlocks Verification O.P.
16104.1 Fuel Transfer System - Periodic Test O.P.
16304.1 Spent Fuel Pit Bridge Crane - Periodic Test within the areas inspected, no items of noncompliance or deviations were identifie DATE
~NKE.Y PNH.T IJNJJ.W
~ A 1 ItlE -
2t> IIOUR CLOCK SHIFT HI0:
OAY t PEAKt OPTPATOR HIO OAY APEAK EQUI PHEttT Contair.rient Equipment Oonr Contalnn nt Persorircl E, Emer.Airlock Doors Autamtic Containrcnt Isolation Valves i ~
Closed Yulvcs per Cnntainm.nt Penetration that Prnvodcs a Oiro ct Path to Atnnspherc Containment Vms and Purge System Isolation (CVPS)
Process Radiation
."janitors t:i.1t Initiate CVPS Isolation:
R-'-ll. R-*- i2 7.
Aprea sadiation I'oni tora Operating as Follows for Unit being Refueled tini t
Unit
~)
R-7 R-8 R-19 R-22
- I tlI ti I it tt i 1 RENDU I prEHEtiT FOR RfF irt Ittt'losed I/2 Clnscd Al I Operable or Closed One Operable Qper1ble Operable, both remote and local I III T I AL I HI T I AL I It I T I AL TIHC ALLOHEO BEFORE STOPPINO REFUELING at RATln'
hl'lcd i a t e Imiv.dia tc I mme d i P1 te Ihricdietc Ialcdi ate Irrhe d I a te Ianiedi ate T E CHti I CAL SPEC IFICAT'OIIS REFEPFNCE 3. 10. I 3. 10.1 3.10.1 3.10.1 3. 10.2 3.10.2 3. 10.3 REHARKS If not operable, at least one valve per penetration closed Tcsicd and verified Irricdiat 1I.
prior to reFurl ing npcrstinns Tested and verified in-wdintei prior to refueling operations Hon i tor con t inuous I y radi a t ion levels in Contsina.ent and Spent Fuel Pit areas.
If an ares ihonitor is not
~
operable, a portable monitor with alarm, nay be used.
it s>i I
8.
HIS Channels H31 and N32 Operating 2/2 Iarhedi ate 3. 10.4 7/2 when changing core geometry I/2 wlocn fuel is in reactor Rtlt'uryS in OperatiOn - lthCn TaVg
~
160 F
0.
Snro Concentration in Vessel I.
CoPRriunications Headsets/Other Reliable Cerrounicat ion System tlanipulatoi'rane to Control Center
~
~
Spent Fuel Assephbty ttoveaient - Over Reactor or SFP Sport Furl oonvcr<nt FrnT-Rr'r'r r lo SIP I/2 Hl n i aT Tati
+
1950 ppm Ava i 1 able I/157 Thuldnwn
>
109 hrS VERIFY OAILY Conc:
Iaiiiediate Iaraediate Itniiediate immediate lanedi ate 3-10.5 3. 10.6 3. 10. 7 3.10.8 3.10.9 Yeri fy daily iAP eh vessel he~d removed and Fuel is in vessel For direct ca~unications be-tween the Control Ccntrr C re-fuel inrj cavi ty manipulator crane Only one s-cnt fuel asscihbly wi II be handled at one tii e Over thC reaCtnr Or P.he St P Spent Fuel P i t Vent i 11t Ion Sys I ~ m Opc r.1h I c Air Samp lee nSamole Determines Tire 5.
The spent fuel cask shall not be moved over spent fiPel Iawcrie Rltc 3.10.8