ML20204H671
| ML20204H671 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/14/1988 |
| From: | Black S NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20204H674 | List: |
| References | |
| NUDOCS 8810240453 | |
| Download: ML20204H671 (10) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION f*
WASH WGYON, D. C. 20656 g
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TEhNESSEE VALLEY AUTHORITY I
DOCKET NO. 50-327 3EQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application f or amendment by Tennessee Valley Authority (the licensee) dateo July 25, 1988, corrplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
ano the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will opcrate in conformity with the application, the provisions of ;he Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducte1 without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Ccmission's regulations; D.
The issuance of this ar.:endment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations ard all applicable requirements have been satisfied.
8810240453 881014 PDR ADOCK 05000327 P
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-2 2.
Accordingly, the license is amended by enanges to the Technical Specifications as indicated in the ettacnment to this license amendment and paragraph 2.C.(2) of Facility Operating License Nc. DPR-77 is hereby amended to read as follows:
(2) Technica_1 Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 90, are hereby incorporated in the license.
The licensee shall cperate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hh Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: October 14, 1985 l
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ATTACHMENT TO LICENSE AMENOMENT NO. 90 e
FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by ?r,3ving the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of chanoa. Asterisked page* is provided to maintain document completeness.
REMOVE INSERT 3/4 6-5 3/4 6-5*
3/4 6-6 3/4 6-6 3/4 6-6a 3/4 6-6a e
TABLE 3.6-1 mg BYPASS LEAKAGE PATH 5 TG THE AUXILIARY BUILDING g
SECONDARY CONTAIMENT BYPASS LEAKAGE PAIHS a
E PENETRATION DESCRIPTION RELEASE LOCATION Sq X-2A Personnel Lock Auxiliary Area X-28 Personnel Lock Auxiliary Area r
X-3 Fuel. Transfer Tube Auxiliary Area F-15 Letdown Auxi1iary Area
. 23 Postaccident Sampling, Hot Leg 3 Auxiliary Area X-25A Pressurizer Gas Sample Auxiliary Area X-2SD Pressurizer Liquid Sample Auxiliary Area X-2nB Control Air Auxiliary Area X-2/C ILRT Auxiliary Area X-M CCS Auxiliary Area x-30 Accumulatoi fill Auxiliary Area e
X-31 Control Air Auxiliary Area u
x-b CCS Auxiliary Area
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X-39/t N to Accumulators Auxiliary Area g
2 m
X-3W N to Pressurizer Relief Tank Auxiliary Area X-4bD Hydrogen Purge Auxiliary Area X-41 Normal RB Sump Auxiliary Area X-47 Primary Water Auxiliary Area X-44 RCP Seal Water Injection Return Auxiliary Arta l
X-45 RC Drain Tank Auxiliary Area X-46 RC Drain Iank Auxiliary Area X-47A Glycol Auxiliary Area X-4/B Glycol Auxiliary Area E
X-St)A CCS Auxiliary Area S
X-50B CCS Auxiliary Area E
X-Si Fire Protection Auxiliary Area X-52 CCS to RCP Oil Cooler Auxiliary Area X-%
ERCW Auxiliary Area 5
X-5/
ERCW Auxiliary Area X-58 ERCW Auxiliary Area C
X-59 ERCW Auxiliary Area X-w ERCW Auxiliary Area Auxiliary Area
- f F-61 LRCW Auxiliary Area x -i,J IRCW-I Auxiliary Area M
LRCW g..t
D TABLE 3.6-1 (Continued)
BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING 2
SEGnDARY CONTAINMENT BYPASS LEAKAGE PATHS 2
E l>l fit I RAi10N DESCRIPTION RCLEASE LOCATION c5 X-64 A/C Chilled Water (ERCW)
Auxiliary Area x-65 A/C Chilled Water (ERCW)
Auxiliary Area X-66 A/C Chilled Water (ERCW)
Auxiliary Area X-6/
A/C Chilled Water (ERCW)
Auxiliary Area X-68 ERCW Auxiliary Area X-69 ERCW Auxiliary Area X- /0 ERCW Auxiliary Area x-/l ERCW Auxiliary Area
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ERCW Auxiliary Area X-/1 ERCW Auxiliary Area d- /4 ERCW Auxiliary Area A-/5 ERCW Auxiliary Area s
1 X - /e, Service Air Auxiliary Area r.
x-//
Demineralized Water Auxiliary Area J.
A- /u Fire Protection Auxiliary Area e b2 fuel Pool Auxiliary Area X-b3 Fuel Pool Auxiliary Area h-84A Pressurizer Relief Tank Gas Sample Auxiliary Area x-BLA Excess Letdown Heat Exchanger Auxiliary Area X-90 Control Air Auxiliary Area x-91 Postaccident Sampling,llot Leg 1 Auxiliary Area X - 92 A.Ll Hydrogen Analyzer Auxiliary Area l
X-93 Accumulator Sample Auxiliary Area E
X-94A,B,C Radiation Sample Auxiliary Area l
E X-95A,B,C Radiation Sample Auxiliary Area E
X-96C Hot Leg Sample Auxiliary Area x-98 ILRT Auxiliary Area x-%
Hydrogen Analyzer Auxiliary Area 5
x-100 Hydrogen Analyzer Auxiliary Area
~
X-lul Postaccident Sampling, Containment Auxiliary Area M
x-103 Postaccident Sampling, Liquid Discharge Auxiliary Area to Containment
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W X
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TABLE 3.6-1 (Continued)
E BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING j!
SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS Y
x PENIINAll0N DESCRIPTION RELEASE LOCATION E
^j X-lo6 Postaccident Sampling, Air Discharge Auxiliary Area to Containment X-lb8 UHI.
Auxiliary Area X-109 UHI Auxiliary Area X-Il0 UHI Auxiliary Area X-114 Ice Condenser Auxiliary Area X-Il5 Ice Condenser Auxiliary Area x-llnA Postaccident Sampling, Containment Auxiliary Area Air Sample t"i l
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.0 889 UNITED STATES i
4
~g NUCLEAR REGULATORY COf4 MISSION a
wAsHmot cN,0. c. 2*sts g
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_ENNESSEE VALLEY AUTHORITY T
DOCKET N0 50-328 2
SEQll0YAH hUCLEAR PLANT, UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.79 License No. OPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 1, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without encangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will rot be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
. t 2.
Accordingly, the license is amended by changes to the Techatcal Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of facility Operating License No. OPR-79 is hereby amended to read as follows:
(2) Technica1Jpecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment flo. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE fiUCLEAR REGULATORY COMMISSION Suzann ssistant Director for Projects TVA Projects Division Office of Special Projects l
Changes to the Technical Specifications 4
Date of Issuance: October 14, 1983 e
e ATTACFFENT TO LICENSE AMENDMENT NO. 90 cACIL(TY OPERATINO LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 6-6a 3/4 6-6a a
J G
t
=
~
TABLE 3.6-1 (Continued)
BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING j
SECONDARY CONTAIMIENT BYPASS LEAKAGE PATHS 5
x PENElRATION DESCRIPTION RELEASE LOCATION C
l
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X-92A,8 hydrogen Analyzer Auxiliary Area X-93 Accumulator Sample Auxiliary Area X-94A B.C
. Radiation Sample Auxiliary Area l
X-95A,B.C Radiation Sample Auxiliary Area i
X-96C Hot Leg Sample Auxiliary Area X-98 ILRT Auxiliary Area X-99 Hydrogen Analyzer Auxiliary Area l
X-100 Hydrogen Analyzer Auxiliary Area l
X-161 Postaccident Sampling, Containment Auxiliary Area X - lid Postaccident Sampling, Liquid Auxiliary Area Discharge to Containment R
A-lo6 Postaccident Sampling, Air Auxiliary Area Discharge to Containment T
A-loa UHI Auxiliary Area T
r.- l u9 UHI Auxiliary Area X-Il6 UHI Auxiliary Area X-114 Ice Condenser Auxiliary Area X-11S Ice Condenser Auxiliary Area X-116A Postaccident Sampling, Auxiliary Area Containment Air Sample 3I il e
E 4
.