ML20117F523

From kanterella
Jump to navigation Jump to search
Forwards Response to Questions in Response to RAI Re Link to NRC Emergency Response Data Sys
ML20117F523
Person / Time
Site: Catawba  Duke energy icon.png
Issue date: 08/21/1996
From: Mccollum W
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9609040106
Download: ML20117F523 (3)


Text

- . ~ . - , _ ~ . . , . . - , . . - . ~ . . . - . - - . - - . . _ - . . . - . - . . - - . . - . - . ~. . -,

e 11 I Duke Mgr Company ~ Www R. Meow M, Jw i Catawba Nuclear Generation Department . \1ce President

, , . 4500QvcordRoad (8W)DI-90 Offin ,

. M, SC29745 - (8W)Dl41% M ,

i DUKEPOWER August 21, 1996 i

U.-S. Nuclear Regulatory Commission i

. ATTN.: Document Control Desk l Washington, D.C. 20555 l i

l

Subject:

Catawba Nuclear Station Dockets 50-413 and 50-414 Operator Aid Computer (OAC) Replacement Link to NRC Emergency Response Data System (ERDS)

Request for Additional Information l

l In a letter dated June 3, 1996 letter, Duke. informed the NRC of l plans to replace the OAC at Catawba Nuclear Station, Unit 1 and of the impact of this OAC replacement on the Unit 1 link to the NRC ERDS. A revised data point library was submitted as an

. attachment to that letter. ,

By letter - dated July 15, 1996, from Frank J. Congel of your staff, five areas were identified where ' additional information l was required in order to provide physical significance to the ERDS data for use by NRC technical teams. Catawba's response to those questions is attached.

If there are any questions concerning this . response, please

! contact Kay Nicholson'at (803) 831-3237.

l Sincerely, g  ? ,'

W. R. McCollum, J

\ KEN:ERDS-OAC.RAI xc: S. D. Ebneter, Regional Administrator P. S. Tam, ONRR f R. J. Freudenberger, SRI [()h[p I F. J. Congel

.J. R. Jolicoeur

^t 9609040106 960821 PDR ADOCK 05000413 Ut F PM w on we.

( .

Duka Power Company

~

  • Catawba Nuclear Station

, . Docket Nos. 50-413, 50-414

1. For Point ID Number C1P0300 (Pressurizer Level) 1% = 5.22 inches with < 13% (PZR), < 75% RX = Level at the top of the pressurizer heaters l f
2. For Point ID Numbers C1P0180 and C1P0181 (RV Level)  :

1 l

2 5.04 inches = 1% level change l

3. For Point ID Numbers C1A0674, C1A0680, C1A0686, C1A0692 (S/G W/R Level) 69.4%* = level at top of S/G U-Tubes 3 j

- Value at cold calibration conditions l

4. For the following Point ID Numbers  !

a) C1E0131 (EMF 36H Unit Vent Gas Monitor)  ;

b) C1E0263 (EMF 49L Waste liquid Discharge) c) C1E0259 (EMF 49H Waste Liquid Discharge) d) C1E0115 (EMF 34H Steam Generator Water Sample High)

Provide any conversion factors that could be used to convert to a release rate in Ci/hr or equivalent; if these are variable conversions, a representative range of the conversion factors. i 1

a) C1E0131 (EMF 36H Unit Vent Gas Monitor)"

(Values are (pCi/cc)/ cpm)

Decay Normal Gap Core Melt Time Reactor Spectrum Spectrum (hours) Coolant 0.01 4.19E-04 3.32E-04 3.32E-04 1 3.44E-04 2.91E-04 2.91E-04 2 3.10E-04 2.56E-04 2.56E-04 4 2.69E-04 2.43E-04 2.43E-04 8 2.33E-04 2.29E-04 2.29E-04 24 2.07E-04 2.09E-04 2.09E-04 l 48 2.02E-04 2.03E-04 2.03E-04 100 2.00E-04 2.01E-04 2.01E-04 250 2.00E-04 2.00E-04 2.00E-04 500 2.00E-04 2.00E-04 2.00E-04 i

720 2.00E-04 2.00E-04 2.00E-04 l

Duk3 Power Company Catawba Nuclear Station

. . Docket Nos. 50-413, 50-414 b) C1E0263 (EMF 49L Waste liquid Discharge)3 = 2.9E-9 (pCi/ cpm-ml) c) C1E0259 (EMF 49H Waste Liquid Discharge)5 = 2.9E-4 i (pCi/ cpm-ml) ,

d) C120115 (EMF 34H Steam Generator Water Sample High)5 i

= 2.9E-4 (pCi/ cpm-ml) i

5. For point ID number C1P0250D2 (Wind Direction)

Is this point measured in the to or from direction?

This point is measured in the FROM direction.

Upper Wind Direction 15 Min Run Avg (DL* ) 6

- Data Link

REFERENCES:

1. CN 1680-122-01, Reactor Coolant System (NC) Elevation View vs. Instrument Percent Scale for NC Level Instrumentation, 1 Rev 6A l i
2. OP/1/A/6700/01, Unit One Data Book, Figure 2.6.1, RVLIS Indications 1
3. DPC-1552.08-00-0169, Wide Range S/G Level Control Setpoints,  ;

Approved 02/29/96

4. Calculation MCC-1227.00-00-0015 1
5. OP/1/A/6700/01, Unit One Data Book, Table 4.1, Process Radiation Monitors Correlation Factor Table
6. IP/0/B/3343/13, Meterological Monitoring System (EED) l Calibration and Maintenance Procedure l

l I

\

\

l 1

l I