ML20212E875

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Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl
ML20212E875
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 09/20/1999
From: Beasley J
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-99-02, LCV-1385, NUDOCS 9909270178
Download: ML20212E875 (3)


Text

r.

J. B$rnie Be sley. Jr., P.E.

SouthIrn Nuclzer

%ce Pres. dent Op: rating Comp:ny. Inc.

Vogtle Project 40 inverness Center Pa kway PO Box 1295 Birmingham, Alabama 35201 Te! 2059923110 Fax 205 992 0433 SOUTHERN COMPANY Energy to Serve Your World" September 20, 1999-Docket Nos.: 50-424 LCV-1385 50-425 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Ladies and Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT RESPONSE TO GENERIC LETTER 99-02 LABORATORY TESTING OF NUCLEAR-GRADE' ACTIVATED CHARCOAL On June 3,1999, the Nuclear Regulatory Commission (NRC) issued GL 99-02,

" Laboratory Testing of Nuclear-Grade Activated Charcoal," to address concerns regarding the adequacy oflaboratory testing techniques utilized to determine the efficiency of charcoal used in radiological filtration systems. Specifically, licensees were requested to describe their Technical Specification (TS) requirements for testing charcoal samples for each Emergency Safety Feature (ESP) ventilation system.

Vogtle Electric Generating Plant (VEGP) TS's incorporate a requirement to perform charcoal sample testing in accordance with ASTM D3803-1989. Attached is a description of the methods used to comply with this standard along with the most recent test results.

Please contact this office if you have any questions.

Sincerely, b

/

~. easl y, Jr JBB/BHW/gje

Attachment:

Response to NRC GL 99-02 9909270178 990920 l

PDR ADOCK 05000424 P

PDR

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l U. S. Nuclear Regulatory Commission

' LCV-1385 Page' 2 -

cc: Southern Nuclear Operating Companv -

Mr. J. T. Gasser Mr. M. Sheibani SNC Document Management U. S. Nuclear Regulatory Commision Mr. L. A. Reyes, Regional Adra.bdstrator Mr. Ramin R. Assa, Vogtle Project Manager, NRR Mr. J. Zeiler, Senior Resident inspector, Vogtle i

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T' Attachment c

Response to NRC GL 99-02 i

VEGP TS's incorporate a requirement to perform charcoal s..nple testing in accordance l

with ASTM D3803-1989. The applicable surveillance requirements for the Control Room l

Emergency Filtration System (CREFS) and the Piping Penetration Area Filtration and l

Exhaust System (PPAFES) reference the Ventilation Filter Testing Program (VFTP) which includes the following acceptance criteria:

ESF Ventilation System Penetration RH Temperature CREFS s 0.2 %

70 %

30 C PPAFES s 10 %

95 %

30 C The Fuel Handling Building Post Accident (FHB-PA) exhaust system is described in the Technical Requirements Manual (TRM). It is also tested per ASTM D3803-1989 at 95%

RH and 30 C and has an allowable penetration of 10%. The most recent test results for each train of these systems indicate acceptable carbon adsorber constion.

Test Carbon Penetration Bed Bed Sample Test Results Acceptance System Depth Depth Date Penetration Criteria CREFS 1 A 4 in.

4 in.

2/8/99 0.012 %

s 0.2 %

CREFS 1B 4 in.

4 in.

3/9/99 0.001 %

s 0.2 %

CREFS 2A 4 in.

4 in.

2/8/99 0.009 %

s 0.2 %

CREFS 2B 4 in.

4 in.

3/9/99 0.022 %

s 0.2 %

PPAFES 1 A 4 in.

2 in.

12/16/98 0.552 %

s10%

i PPAFES 1B 4 in.

2 in.

1/19/99 5.930 %

s 10 %

PPAFES 2A 4 in.

2 in.

7/1/99 0.678 %

6 10 %

PPAFES 2B 4 in.

2 in.

6/10/99 0.524 %

s 10 %

FHB-PA Train A 4 in.

2 in.

2/18/99 0.317 %

5 10 %

FHB-PA Train B 4 in.

2 in.

8/19/98 0.301 %

s 10 %

Note: The PPAFES and FHB-PA are 4-in, deep beds but use 2-in. bed depth for laboratory testing.

{

The total residence' time per 4-in. bed is 0.5 sec. with a face velocity of 40-ft./ min.

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