ML20091K820
| ML20091K820 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/21/1995 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20091K824 | List: |
| References | |
| NUDOCS 9508280162 | |
| Download: ML20091K820 (3) | |
Text
1 Tennessee Valley Authority. Post Office Bon 2000. Soddy-Daisy Tenressee 37379 August 21,1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
)
Decket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SON)- ADDITIONAL INFORMATION FOR TECHNICAL SPECIFICATION (TS) CHANGE 94-15, "POSTACCIDENT SAMPLING (PAS)"
Reference:
TVA letter to NRC dated April 6,1995, "Sequoyah Nuclear Plant (SON) -
Technical Specification (TS) Change 94-15,'Postaccident Sampling (PAS)'"
By the referenced letter, TVA submitted TS Change 94-15 that proposed to delete License Condition 2.C.(23)F of License No. DPR-77 for Unit 1 and 2.C.(16)g of License No. DPR-79 for Unit 2. These license conditions are associated with operation of SON's PAS System.
Recent discussions between SON's Licensing staff and NRC indicated that clarification was needed within SON's Final Safety Analysis Report (FSAR) concerning the start of the response times for taking samples. Specifically, NRC indicated that the PAS System must have the capability of taking samples within the specified response time following the accident rather than following the onset of core stability. Accordingly, TVA is resubmitting Enclosure 5 to the above referenced letter in its entirety to reflect this clarification. Note that the justification for SON's response time in the revised PAS Program (provided in Enclosure 4 of TVA's referenced letter) remains unaffected by the change in capability described above. SON's PAS Program will be established to ensure the appropriate sampling response time capability exists and will be executed in accordance with good sampling practices. The additionalinformation contained in this submittal does not affect the significant hazards evaluation previously provided in the referenced letter.
Enclosed are the revised FSAR pages associated with SON's revised PAS Program.
t 9St ilI
{
9508280162 950821 PDR ADOCK 05000327 P
PDR a
w.
U.S". Nuclear Regulatory Commission
- Page 2 August 21,1995 4
l
- Please direct questions concerning this issue to D. V. Goodin'at (615) 843-7734.
l
. Sincerely,.
e
'L R. H. Shell ~
' Manager-SON Site Licensing
. Enclosure -
. cc (Enclosure):
.Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike.
Rockville, Maryland 20852-2739 NRC Resident inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator
' U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 J
4
-w
ENCLOSURE FINAL SAFETY EVALUATION HEPORT CHANGES ASSOCIATED WITH SEQUOYAH NUCLEAR PLANTS REVISED 00STACCIDENT i SAMPLING PROGRAM l
L L
i l
f-IE
--u&