L-84-250, Requests Withdrawal of Tech Specs for Reactor Vessel Level Monitoring Sys from Table 3.5.5 Re Accident Monitoring Instrumentation,Contained in 840615 Application to Amend Licenses DPR-31 & 41,per NUREG-0737.Revised Pages Encl
| ML17346A536 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/13/1984 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 L-84-250, NUDOCS 8409180136 | |
| Download: ML17346A536 (10) | |
Text
REGULATORY FORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR;8409180136 DOC ~ DATE: 84/09/13 NOTARIZED; NO DOCKET ¹ FACIL!50 250 Turkey Point Planti Unit* 3i Florida Power and Light C
05000250 50-251 Turkey Point Plant'i Unit 4i Florida Power and Light C
05000251 AUTH,NAME AUTHOR AFFILIATION WILLI'AMSiJe W ~
F 1 or i da >Power 8 Light 'Co, RECIP ~'NAME RECIPIENT AFFILIATION EISENHUTiD+G ~
Division of Licensing al t
SUBJECT:
Requests withdrawal of Tech Specs for reactor vessel level monitor.ing sys from Table 3' '
re accident monitoring instrumentat.ion~contained in 840615 application to amend Licenses DPR 31 L'"4liper NUREG 0737 'evised pages encl, ~
DISTRIBUTION iCODE:
A046D COPIES RECE'IVED!LTR ENCL 'IZE:
T'ITLE:
OR Submittal:
TMI Action Plan 'Rgmt NUREG-0737 8
NUREG~06b0 NOTES:
OL: 07/19/72 OL: 04/14/73
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FLORIDAPOWER 8[ LIGHTCOMPANY September 13, 1984 L-84-250 Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Ei senhut:
Re: Turkey Point Units 3 and 4
Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility Operating Licenses DPR-31 and 41 NUREG 0737 Technical, S eci fications Our letter, L-84-155, dated Dune 15, 1984 provided a request to amend the operating licenses for Turkey Point Units 3 and 4 to incorporate certain TNI modifications in the Technical Specifications.
The purpose of this letter is to withdraw a portion of our request.
Specifically we wish to withdr w the requested specification for the Reactor Vessel Level Monitoring System (RVLNS) from Table 3.5.5, Accident Monitoring Instrumentation.
This system has been purchased from Combustion Engineering and is very similar to the RVLMS for our St. Lucie units.
As a member of the Combustion Engineering Owners Group, FPL will be participating in the Owners Group effort to define appropriate operability requirements for the RVLMS.
Until the Owners Group effort is completed, it would be inappropriate for FPL to establish a technical specification on this systeII.
Revised pages to our amendment. request to incorporate this deletion are provided as attachments to this letter.
840918013b 840~13 PDR ADOCK, 05000250
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~, Office of Nucl'ear Reactor Regulation Attention:
Hr. Darrell G. Eisenhut P.age 2
Should you or your staff, have any questions on this information, please contact us.
'Very truly, yours, J.
W. Willies, Jr.
Group Vice President Nuclear Energy JWW/PLP/js
,Attachment cc: J.
P. O'Reilly, Regi'on II Harold F. Reis, Esquire Lyle Jerrett, 'Ph.D., 'Director'.
Office of Radiation Control Dept. Health 8 Rehabilitati.ve Services 1323 Winewood BouTevard Tall ahassee, FL
'32301" P NS-LI-84-326
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TABLE3.5-5 ACCIDENT MONITORINGINSTRUMENTATION INSTRUMENTATION TOTAL NO.
OF CHANNELS MINIMUMCHANNELS OPERABLE APPLICABLE ACTIONS 1.
Pressurizer Water Level 2.
3.
5.
6.
7.
8.
9.
10.
11.
12.
13.
Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor PORV Position Indicator (Primary Detector)
PORV Block Valve Position Indicator Safety Valve Position Indicator (Primary Detector)
Containment Pressure (Wide Range)
Containment Pressure (Narrow Range)
Containment Water Level (Wide Range)
Containment Water Level (Narrow Range)
Containment High Range Area Radiation Containment Hydrogen Monitors High Range - Noble Gas Effluent Monitors a.
Plant Vent Exhaust b.
Unit 3 - Spent Fuel Pit Exhaust c.
Condenser Air Ejectors d.
Main Steam Lines 10.
Incore Thermocouples (Core Exit Thermocouples) 2 per generator 2
1/valve 1/valve 1/valve 2
0/core quadrant 1 per generator 1
1/valve 1/valve 1/valve 1
2/core quadrant 1,2 1,2 1,2 1,2 3
1,2 3
6,7 1,2
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TABLE0.1-1 SHEET 0 Channel Descri'ion Check Calibrate Test Remarks 35.
Containment High Range Area Radiation 36.
Containment Hydrogen Monitors 37.
High Range Noble Gas Effluent Monitors a.
Plant Vent Exhaust
- b. Unit 3 Spent Fuel Pit Exhaust R(Note 1)
Q(i)
~
R (1) Channel calibration using sample gas containing:
a.
One volume percent hydrogen, balance nitrogen.
c.
Condenser AirEjectors d.
Main Steam Lines 38.
Incore Thermocouples (Core Exit Thermocouples)
Mtt N.A,(See Note 2)
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