ML17341B616
| ML17341B616 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/28/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.E.1.2, TASK-2.F.1, TASK-TM GL-82-05, GL-82-5, L-83-46, NUDOCS 8302010606 | |
| Download: ML17341B616 (5) | |
Text
n REGULATORY
.iFQRMATION DISTRIBUTION SYS.
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ACCESSION NBR:8302010606 OOC ~ DATE: 83/01/28 NOTARIZED:
NO DOCKET FACIL:50-250 Turkey Point Plant< Unit 3< Florida Power and Light C
050 50 50 251 Turkey Paint Pl ant
< Unit er F1Orida POWer and Light C ~00025 AUTH INANE AUTHUR AFFILIATION UHRIGr R ~ Eg Florida Power 8 Light Co ~
REC IP ~ WANE RECIP IEN f'FFILIATION VARGAFS ~ AD Operatsng Reactors Br anch 1
SUBJECT:
Submi ts update to NUREG-0737F Items II,8.3F "PosteaAcci dent Sampl ing SysF" CI ~ E,i.2F "Auxiliary Feedwater Sys Automatic Initiation 8, Flow IndicationP" 8 II ~ F,iF "Addi Accident Monitoring Instrumentation,"
DISTRIBUTION CODE:
A046S COPIES RECEIVED:LTR ENCL SIZE:
/
TITLE:
OR Submittal:
Tt~I Action Plan Rgmt NUREG-0737 8
NUREG-0660 NOTES:
RECIPIENT IO CODE/NAME NRR ORB 1 BC 01 INTERNAL: ELD/HDS4 IE/DEP EPDS NRR PANLSONFll.
NRH/DL D IR 14 NRR/DL/ADOR 15 NRH/DL/DRAB 18 NRR/DSI/ADRS 27 NRR/OS I/ASB NRR/DST DIR 30 RG 1%2 EXTERNAL: ACRS 34 INPOgJ ~ STARNES NRC PDR 02 NTIS COPIES L.TTR ENCL 7
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1 TOTAL NUMBER OF COPIES HEUUIREDe LTTR 46 ENCL 45
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FLORIDA POWER & LIGHTCOMPANY January 28, 1983 L-83-46 Office of Nuclear Reactor Regulation Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch IE1 Division of Licensing U.
S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Va rga:
Re: Turkey Point Units 3 5 4 Docket Nos.
50-250 8 50-251 Post-TMI Re ui rements The following paragraphs contain an update on'everal NUREG-0737 items that have been addressed in previous correspondence and in Generic Letter 82-05.
1.
Post-Accident Samplin System I I.B.3 Our letter of November 15, 1982 stated that the Post-Accident Sampling System (PASS) was undergoing startup testing.
Many problems with the design and installation of the system have been identified during this testing.
A significant amount of manpower is being applied to resolve these di fficulties.
We will provide you with an update of the status of the system on or before March 30, 1983.
2.
Auxiliary Feedwater System Automatic Initiation and Flow Indication II.E.1.2 a.
AFW Flow Indication In our letter of April 27,
- 1982, we informed you that modifications to the power supplies for the flow indication and flow control had been installed in Unit 3 and would be installed in Unit '4 during the next scheduled outage of sufficient duration.
The modifications are now complete for both Units 3 and 4.
b.
AFW System Steam Su pl Valves Another schedule change affects the change of two of three AFW steam supply valve actuators from AC to DC.
The modifications for Unit 4 will be done as schedul.ed during the steam generator repair outage.
The modification to the Unit 3 valve actuators also requires the unit to be shutdown.
It is scheduled that this modification.will be done during the next scheduled Unit 3 refueling outage.
83020i0606 830i28 PDR ADQCK 05000250 P
PDR PEOPLE... SERVING PEOPLE
Office of Nuclear React egulations Page 2
3.
Noble Gas Monitors/Iodine Particulate Samplin I I.F.1.1, II.F.1.2 a.
Plant Vent Effluent Monitors In our letter of January 7,
- 1982, we identified that the plant vent effluent monitors may require additional modifications to provide isokinetic sampling.
Our engineering department has developed a
Plant Change and Modification package containing the required design modifications.
We will inform you when an implementation date is available.
b.
Air Ejecto r Efflue nt Monito rs As the NRC staff is aware through previous correspondence, the air ejector effluent monitors have had severe operability problems since their installation due to moisture accumulation.
Our engineering department has developed a Plant Change and Modification package which contains a proposed design change that addresses the problem.
We will inform you when an implementation date is available.
4.
Contairinent Hi h
Ran e Radiation Monitors II.F.1.3 The required in situ calibration of the monitors in both Units 3 and 4 has been completed as required.
5.
Contairment Hydrogen Monitor's I I. F.1.6 The heat tracing for the contairment hydrogen monitors was installed prior to September 30, 1982.
The heat tracing is still undergoing preopera-tional testing.
We will inform you when the testing is canpleted and the entire system is turned over to operations.
R rt E. Uhrig Vice President Advanced Systems 8 Technology REU/PKG/js c:
J.
P. O'Reil ly, Region II Harold F.
Rei s, Esquire P NS-LI-83-037-1