ML20033F083
| ML20033F083 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/09/1990 |
| From: | Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20033F084 | List: |
| References | |
| GL-89-01, GL-89-1, TVA-SQN-TS-90-3, NUDOCS 9003150466 | |
| Download: ML20033F083 (2) | |
Text
TENNESSEE VALLEY - AUTHORITY--
CH ATTANOOGA. TENNESSEE 37401 g,
SN 157B Lookout Place MAR 0919E
.TVA-SON-TS-90-03 10 CFR 50.90 U.S. Nuclear Regulatory Commission
-ATIN: ' Document Control. Desk Washington, D.C.
20555-
. Gentlemen:
In-the Matter of
)
Dotket Nos. 50-327 Tennessee Valley Authority
)
50-328 zSEQU0YAH NUCLEAR PLANT (SQN)'- TECHNICAL SPEClflCATION (TS) CHANGE 90-03
^
'In accordance with 10 CFR 50.90, we are enclosing a requested amendment to Y
Licenses DPR-77 and DPR-79 to change the TSs of SQN Units 1 and 2.
The proposed change implements ~NRC's recommended alternatives for the Radiological Effluent-Technical Specifications (RETS) as contained in Generic Letter 89-01, 1" Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative' Controls Section of the-Technical
. Specifications and the Relocation of Procedural Details of.RETS to the Offsite
. Dose Calculation Manual or to the Process Control Program (Generic Letter-89-01)."
The~ proposed TS change is identified in Enclosure 1.
The justification for the proposed TS change is provided in Enclosure 2,: A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50~.92 is
~
7 provided in Enclosure 3.
Copies of SQN's Offsite Dose Calculation Manual and Process Control Program are provided in Enclosure 4.
s P_ lease direct questions concerning this issue-to D. V. Goodin at~
(615) 843-7734.
Very truly yours, TENNESSEE VALLEY AUTHORITY 9003150466 900309L
[/
DR ADOCK O 7
o E. G. Hallace, Manager Nuclear Licensing and Regulatory Affairs i
Swornfjo nd subsc d be re me this 7
' day of 1990 Notary Public My Commission Expires M 1.
Enclosur es cc; See page 2 i
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An Equal opportunity Employer
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' TU.S. Nuclear: Regulatory Commission MAR 091990:
-cc: Ms; S. C.' Black. Assistant Director (Enclosures) for Projects TVA Projects Division-U.S.. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike-
-Rockville, Maryland 20852 f
Mr. B. A. Wilson, Assistant Director (Enclosures) for Inspection Programs r
TVA' Projects Division
'7 J
U.S. Nuclear' Regulatory Comm)sston Region II-101-'Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 r
Mr. Michael H. Mobley, Director Division ~of Radiological Health
'T.E.R.R.A., Building 150 9th Avenue, N Nashville, Tennessee 37203 NRC Resident Inspector (Enclosures)
Sequoyah Nuclear Plant 2600 Igou. Ferry Road Soddy Daisy, Tennessee ~ 37379 American Nuclear Insurers (Enclosures)
-Attention:
Librarian The Exchange,, Suite 245
-270.Farmington Avenue Farmington, Connecticut -06032 v
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ENCLOSURE 1-PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327'AND 50-328 (TVA-SQN-TS-90-03) i LIST OF AFFECTED PAGES Unit i V
3/4 3-74 3/4 11-7 3/4 12-1 B3/4 11-2
.XI 3/4.3-75 3/4 11-9 3/4 12-2 B3/4.11-3 1-4 3/4 3-76 3/4 11-10 3/4 12-3 B3/4 11-4 1-5.
3/4 3-77 3/4 11-11 3/4 12-4 B3/4 11-5 1-6 3/4 3-78 3/4 11 3/4 12-5 B3/4 12-1 3/4 3-69 3/4 3-79 3/4 11-13 3/4 12-6 B3/4-12 '
3/4-3-70 3/4 3-80 3/4 11-14 3/4 12-7.
6-15 3/4 3-70A 3/4 11-1 3/4 11-15 3/4 12-8 6-17 3/4 3-71--
3/4 11-2 3/4 11-16 3/4 12-9 6-19 3/4 3-71A 3/4 11-3 3/4 11-17 3/4 12 6 '
3/4 3-72 3/4 11-4 3/4 11 3/4 12-11 6-23 3/4 3-72A 3/4 11-5 3/4 11-21 B3/4 3-5' 6-24' 3/4 3-73 3/4 11-6 3/4 11-22 B3/4 11-1 6-25 Unit 2-V 3/4 3-76 3/4 11-8' 3/4 12-4 B3/4 11-5 XI.
3/4 3-77 3/4 11-9 3/4-12 33/4 12-1 L
1-4' 3/4 3-78 3/4.11-10 3/4 12-6 B3/4 12-2 1 3/4 3-79 3/4 11-11 3/4 12-7 6-15 1-7 3/4 3-80 3/4 11-12 3/4 12-8 6-17 3/4 3-68 3/4 3-81 3/4 11-13 3/4 12-9 6-19 3/4 3-69 3/4 3-82 3/4 11-14 3/4 12-10 6-20 3/4 3-70 3/4 11-1 3/4 11-15 B3/4 3-4 23 3/4 3-71 3/4 11-2 3/4 11-18 B3/4 3-5 6-25 3/4 3-72 3/4 11-3 3/4 11-19 B3/4 11-1 3/4 3-73 3/4 11-4 3/4.12-1 B3/4 11-2 3/4 3-74 3/4 11-5 3/4 12-2 B3/4 11-3
-3/4 3-75 3/4 11-6 3/4 12-3 B3/4 11-4 L
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1 1
INDEX
~f{f '
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIR k.
SECTION '
PAGE 3/4.2 POWER DISTRIBUTION LIMITS-3/4.2.1.
Axial Flux Difference.....................................
3/4 2-1
-3/4.2.2 Heat Flux Hot Channel Factor..............................-
3/4 2-5 3/4.2.3 RCS Flowrate and R..........................'...............
3/4 2-10 3/4.2.4 Quadrant Power Tilt Ratio................................. ' 3/4 2-15 3/4.2.5 DNB Parameters............................................
3/4 2-18 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.......................
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.........................................
3/4 3-14
{
.3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation......................
3/4 3-39 Movable'Incore Detectors..................................
3/4 3-43 Seismic Instrumentation...................................
3/4 3-44
' Meteorological Instrumentation............................
3/4 3-47 Remote Shutdown Instrumentation...........................
3/4 3-50 Chlorine Detection Systems (De.leted).
3/4 3-54 R66 Accident Monitoring Instrumentation.T.....................
3/4 3-55 FireDetectionInstrumentation..................(.......d' 3/4 3-58 Delete.)
Radioactive Liquid Effluent Monitoring Instrumentation....
Radi c:yplos", ve. fas 3/4 3-69 i'
- tive C:::::: Ef' luer.t Monitoring Instrumentation...
3/4 3-74 SEQUOYAH - UNIT 1 V
Amendment No. 62 October 30, 1987
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