3F0896-08, Forwards Revised Data Points Incorporating ERDS on 960708, Per 10CFR50,App E,Section VI.3.a

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Forwards Revised Data Points Incorporating ERDS on 960708, Per 10CFR50,App E,Section VI.3.a
ML20116H558
Person / Time
Site: Crystal River Duke energy icon.png
Issue date: 08/06/1996
From: Beard P
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0896-08, 3F896-8, NUDOCS 9608120134
Download: ML20116H558 (2)


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Florida Power CORPORATION l CCl August 6, 1996 3F0896-08 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Emergency Response Data System

Dear Sir:

Florida Power Corporation (FPC) is in the process of replacing the main steam line radiation monitors for Crystal River Unit 3 (CR-3). The new monitors provide a more sophisticated measurement of primary-to-secondary system leakage which includes an automated conversion to gallons per day. This allows direct assessment of primary-to-secondary leakage any time the reactor is at power. The attached revised data points were incorporated into the Emergency Response Data System (ERDS) on July 8, 1996. This information is provided in accordance with 10 CFR 50, Appendix E, Section VI.3.a which states that data point changes must be submitted to the NRC within 30 days after the changes are complete. J l

Sincerely, )

.4 g l M Beard, Jr.

Senior Vice President Nuclear Operations Attachment PMB:AEF xc: Regional Administrator, Region II Senior Resident Inspector NRC Project Manager i9onna9608120134 960806 PDR ADOCK 05000302 3 g1 PDR F- 0 CRYSTAL RIVER ENERGY COMPLEX: 15760 W Power une St . Crystal River, Florida 3442&6708 e (352) 7954486 1 \\

A Florida Progress Company

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U. S. Nuclear Regulatory Commission l 3FQ796-17

{

Atta'chment 1 of 2 1 I

l PWR Data Point Library Reference File Date: July 3,1996 I'

Reactor Unit: CR3 Crystal River-3 Data Feeder: N/A NRC ERDS Parameter: MAIN SL B1 Point ID: W319 Plant Specific Point

Description:

RM-G26 - BI Pri/Sec Leakage l Generic /Cond

Description:

Stm Gen BI Steam Line Rad 12 vel Analog / Digital: A Engineering Units / Digital State: GPD (Gallons per Day)

Engineering Units Conversion: N/A Minimum Instrument Range: 0.1 Maximum Instrument Range: 100 s Zero Point

Reference:

N/A l Reference Point Notes: N/A PROC or SENS: S  !

Number of Sensors: 1 Ilow Proceswd: N/A l

l Sensor Locations: Intermediate Buildmg Alarm / Trip Setpoints: 50 GPD liigh/100 GPD liigh liigh NI Detector Power Supply Cut 4N Power Level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: None Temperature Compensetbn l

for DP Transmitters: N/A l

Level Reference Leg: N/A l Unique System

Description:

Monitors the B-1 main steam line for N 16 and calculates primary to secondary leakage.

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. n U. S. Nuclear Regulatory Commission 3Fa796-17 Attachment 2 of 2 PWR Data Point Library Reference File Date: July 3.1996 Reactor Unit: CR3 - Crystal River-3 Data Feeder N/A NRC ERDS Parameter MAIN SL A2 Point ID: W320 Plant Specific Point

Description:

RM427 - A2 Pri/Sec Leakage Generic /Cond

Description:

Stm Gen A2 Steam Line Rad Level Analog / Digital: A Engineering Units / Digital State: GPD (Gallons per Day)

Engineering Units Conversion: N/A Minimum Instrument Range: 0.1 Maalmum Instrument Range: 100 Zero Point

Reference:

N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 Ilow Processed: N/A Sensor Locations: Intermediate Building Alarm / Trip Setpoints: 50 GPD liigh /100 GPD liigh liigh NI Detector Power Supply Cut off Power level: N/A NI Detector Power Supply Turn.en Power level: N/A Instrument Failure Mode: None Temperature Compensatien for DP Transmitters: N/A Level Reference Leg: N/A Unique System

Description:

Monitors the A-2 main steam line for N 16 and calculates primary to secondary leakage.

43

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