ML20095B914
| ML20095B914 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 08/14/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8408220303 | |
| Download: ML20095B914 (3) | |
Text
m DUKE POWER GOMPANY P.O. Iso x 3 3180 CHAHLOTTE. N.O. 28242
' HAL H.TLCKER Teteruoxz (704) 07a-4sai g=,. y,
August 14, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear'Mr. Denton:
On June 25, 1984, Duke Power Company submitted a number of revised FSAR Chapter 14 test abstracts.
Further review of Chapter 14 has identified one additional change. Table 14.2.12-1 (Page 46), Heat Tracing Systems Test. This preoperational test (TP/1/B/1350/06) was identified in attachment 2 of Duke's July 2, 1984 letter to J. P. O'Reilly, NRC/ Region II, as not being complete prior to f'rel loading. With fuel loaded it was recognized that the boron concentration in the Chemical and Volume Control System (NV) could be reduced if the testing of the Trace Heating System (EHT) was performed in accordance with the Test Method described in Table 14.2.12-1 (Page 46). Also, the decreased temperatures needed to test the backup circuits could not be obtained due to summer time temperatures.
Therefore the Test Method and Acceptancu Criteria have been revised to verify proper operation of the EHT System under the current conditions.
The attached changes to Table 14.2.12-1 (Page 46) will be included in Revision 12 to the FSAR. License Condition C(6) of Facility Operating License NPF-24 requires prior approval by the NRC of any major modifications to the post-fuel-loading initial test program. Since the EHT System is not a safety-related system it is concluded that License Condition C(6) is not applicable and prior approval is not required.
Very truly yours, v
Hal B. Tucker ROS/mjf Attachment g
8408220303 840814 4i PDR ADOCM OS000413 0.D P
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~Mr. Harold R. Denton, Director-
--August 14, 1984 Page 2 cc:.Mr. James P. O'Reilly, Regional Administrator l-U. S. Nuclear Regulatory Commission Region =II:
-101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-
.NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.
Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412
' Palmetto Alliance 12135 Devine Street Columbic, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207
+-
4' Table 14.2.12-1 (Page 46)
HEAT TRACING SYSTEMS TEST Abstract Purpose 6
-To demonstrate the ability of the heat tracing system to maintain proper temperature control in the various piping systems (liquid and solid wastes, chemical volume control and boron rccycle).
Prerequisties Heat tracing system installation and component checks completed. Associated systems completed to the extent necessary to allow conduct of this test.
-Test Method Energize heat traciag system.
Monitor temperatures mainta'.ned by each heat tracing circuit with the system in a static condition.
Induce negative teraperature transients.
Verify primary and backup controllers energize and de-energize at setpoint
-temperatures.
Acceptance Criteria
. Primary and backup circuits maintain temperature range of 150*to 200*F for.
12% boric acid.
Primary and backup circuits maintain temperature range of 70*to 175*F for 4% boric: acid.
I Primary temperature controllers energize at 175 5'F'from decreasing-temperatures and de-energize at 175*5'F from increasing-temperatures for 12% boric acid.
f Primary temperature cEntrollers energize at 85 5+F from decreasing temperatures and de-energize. at 85 5 +F from increasing temperatures for 4% boric acid.
BackupLtemperature controllers energize at 160*5'F from decreasing temperatures I
and de-energiaa at-160*5 *F from increasing temperatures for 12% boric acid.
. Backup temperature controllers energize at 70*5*F from decreasing temperatures and de-energir.e at 70*5*F from increasing temperatures for 4% boric acid.
6 p
Rev. 12 l
.