ML17341A963
| ML17341A963 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/15/1982 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.F.1, TASK-TM L-82-93, NUDOCS 8203230290 | |
| Download: ML17341A963 (10) | |
Text
REGULATORY ORMATION DISTRIBUTION "SY
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ACCESSION NBR',8203230290 OOC DATE'?/03/15 NOTARIZED!
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T FAGIL:.50 250 Tur key Point <Plantr,UniIt 3r Florida 'Power and Light 'C 5000 50 251 Turkey Point <<Plantr,Uni,t ffr,Florida Power -and Light C
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'AUTH~ NAME AUTHOR AFFILIATION UHRI'Gr ROE ~
.Flot ida ~Power L Light <<Co ~
RKCIP ~ NAMK RECIPIENT AFFILIIATION EISENHUTrOBG ~
Di.vision of Licensing
SUBJECT:
Informsof currTent Progress.statps, in implementing NURKG 0737 requi:rementsE Items II~ 81 K II,F~ 1 ~
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FLORIDAPOWER 8 LIGHTCOMPANY March 15, 1982 L-82-93 Office of Nucl ear Reactor Regul ati on Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing U.
S.
Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Eisenhut:
Re:
Turkey Point Units 3
8 4 Docket No. 50-250 8 50-251 POST-TMI RE UIREMENTS The purpose of this letter is to inform you of the status of our pr ogress in implementing the requirement NUREG-0737 Items II.B.l and II.F.l.
The attachment to this letter contains the current status on these items.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/PKG/cab Attachments cc:
Mr. James P. O'Reilly, Region II Mr. Harold F.
Rei s, Esquire 3.v~
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ATTACHMENT Page 1
Re:
Turkey Point Units 3 5 4 Docket No. 50-250 5 50-251 Post TMI Re ui rements 1.
REACTOR COOLANT SYSTEM VENTS II.B.1 In our letter L-82-5 dated January 7, 1982, we stated that we intended to submit a set of operating procedures to you by March 1, 1982.
We have recently received a letter from Mr. Steven A. Varga dated February 24, 1982 which requested additional information concerning the Reactor Coolant System Vents.
Item 7 of the enclosure to that letter specifically requested that FPL submit "operating guidelines" for use of the system.
We are reviewing the content Mr. Varga's letter and are scheduling the submittal of our "operating guidelines" in accordance with the date requested in his letter.
2.
ADDITIONAL ACCIDENT - MONITORING INSTRUMENTATION II.F.l A.
Technical S ecifications In our January 7,
1982 letter, we addressed the scheduled submittals of our proposed technical specifications for the accident monitoring instrumentation to be installed by the requirements of NUREG-0737 Items II.F.1. 1 through II.F.1.6.
Some of the items had specific submittal dates for the proposed technical specifications and others were to be provided following the installation of the monitors.
Rather than submit the technical specifications, one or two at a time in a piecemeal fashion, it is our intent to submit them all at once following the complete installation and determination of OPERABILITY of all the monitors.
Proposed Technical Specifications for the monitors specified in items II.F.1.3 through II.F.1.6 have already been approved by the Plant Nuclear Safety Committee.
The Company Nuclear Review Board must yet review and approve them for submittal.
It is our opinion that a single Technical Specification submittal of all item II.F.l monitors will be more efficient and will eliminate repetitive reviews by both your staff and ours.
B.
NOBLE GAS MONITORS/IODINE, PARTICULATE SAMPLING II.F.l. 1 AND II.F.1.2 All five of the effluent monitors are completely installed and operable.
Each has been tested and calibrated.
It is our intent to have operating procedures written by April 30, 1982.
As previously stated in our letter (L-82-5) dated January 7, 1982, the plant vent effluent monitor may require additional modifications to provide isokinetic sampling.
Any needed modifications will be scheduled when the extent of the modifications, if any, are known.
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C.
CONTAINMENT HIGH RANGE RADIATION MONITOR II.F.1.3 In our January 7,
1982 letter we stated that the monitors had been installed in Unit 4.
The system was completed and startup testing initiated on December 18, 1982.
Equipment problems which occurred during startup testing prevented the Unit 4 system from being made completely operable until January 17, 1982.
It was also stated that the system would be installed in Unit 3 prior to the startup from the steam generator repair outage.
It was recently discovered that one of the two redundant SIGMA indicators to be mounted in the control room was defective.
The indicator was sent back to the vendor.
It is expected to be returned to the plant within six weeks.
It is our i ntent that one train of the system will be completely operable by the Unit 3 startup and the redundant train will be made operable as soon as the repaired or replaced indicator is returned and installed.
Due to misinterpretation of the calibration requirements of NUREG-
- 0737, Item II.F.1.3, the in situ calibration for at least one decade below 10 R/hr by means of a calibrated radiation source was not made.
The system was checked for source indication using a lower strength source.
In situ calibration by. electronic signal substitution was made for the higher ranges of the monitor.
A calibrated radiation source will be used to complete the calibration of the monitors in accordance with the requirements, of Item II.F.1.3.
Both channels of Unit 3 will have their calibration completed prior to startup from the current steam generator repair outage.
The calibration of one channel of the Unit 4 system will be completed prior to April 1, 1982.
The redundant Unit 4 monitor, which is not accessible during plant operation, will have its calibration completed during the next Unit 4 outage currently scheduled to begin on May 30, 1982.
D.
CONTAINMENT PRESSURE MONITOR II.F.1.4 In our January 7,
1982 letter, we stated our intent to install the wide range portion (0-180 psig) of the Unit 3 containment pressure monitor prior to the startup from the steam generator repair outage.
It was recently discovered that both redundant SIGMA indicators to be mounted in the control room were defective.
The indicators have been sent back to the vendor.
It is currently scheduled that the indicators will be returned to the plant within six weeks.
The repaired or replaced indicator will be installed following receipt from the vendor.
As previously stated, the installation of the vacuum portion of the system for both Units 3 and 4 will be completed as soon as possible following receipt from the vendor.
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E.
CONTAINMENT WATER LEVEL MONITOR I I.F. 1.5 As in the case of the containment pressure monitors discussed
- above, we will not be able to complete the installation of the Unit 3 Containment Water Level Mon'itor s by the startup from the current steam generator r epair outage because of defective SIGMA indicators in both trains.
The indicators will be installed following receipt from the vendor.
F.
CONTAINMENT HYDROGEN MONITORS I'I.F.1.6 As.stated in our letter of January 7, 1982, the Containment Hydrogen Monitors have been partially installed in both Turkey Point Units 3 and'.
Portions of the system are tied in with the Post - accident Sampling System (item 11.8.3) which has caused delays in construction.
The balance of the system to be installed is not outage related and will be done as soon as possible.
We will provide you with an update on April 30, 1982 on our progress for making the system completely operational.
The status of the installation of the heat tracing of the sample lines has not changed.
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