ML20069D818
| ML20069D818 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/27/1994 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069D821 | List: |
| References | |
| NUDOCS 9406060217 | |
| Download: ML20069D818 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20E0001 5
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE0V0YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 183 License No. DPR-77 1.
TM Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 8,1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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 Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
i 9406060217 940527 PDR ADOCK 05000327 P
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. 2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.183, 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, to be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
?-
Frederick J. Heb n, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: !!ay 27,1994
ATTACHMENT TO LICENSE AMENDMENT NO. 183 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 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 l
indicating the area of change.
REMOVE INSERT 3/4 3-27a 3/4 3-27a l
l l
I l
l 1
1 l
l 1
l l
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 85 FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES x
ii. RCS Loop AT Equivalent to E
Power > 50% RTP G
Coincident with Steam 215.0% of narrow range 214.4% of narrow Generator Water Level-instrument span range instrument span 1
Low-Low (Adverse) and l
Containment Pressure (EAM) 50.5 psig 50.6 psig or Steam Generator Water 210.7% of narrow range 210.1% of narrow range Level-Low-Low (EAM) instrument span instrument span d.
S.I.
See 1 above (all SI Setpoints) w I
2 e.
Loss of Power Start w
Ey 1.
Voltage Sensors 25520 volts 25472 volts 2.
Load Shed Timer 1.25 seconds 1.25 seconds 10.09 seconds f.
Trip of Main Feedwater N.A.
N.A.
g Pumps 1
tD E
g.
Auxiliary Feedwater Suction a 3.21 psig (motor driven pump) a 2.44 psig (motor driven pump) 4 Po Pressure-Low z 13.9 psig (turbine driven a 12 psig (turbine driven pump) i 5
pump) i z
P h.
Auxiliary Feedwater Suction 4 seconds (motor driven pump) 4 seconds 20.4 seconds L
Transfer Time Delays (motor driven pump) mw-e 5.5 seconds (turbine driven 5.5 seconds *0.55 seconds 6
p.*
pump)
(turbine driven pump)
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 175 License No. OPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 8, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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 Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
)
. 2.
Accordingly, the license is amended by changes to 'the Technical Specifications as. indicated in the attachment to this license amendment and paragraph 2.C.(2) of. Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.175,.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, to be implemented within 45 days.
(
FOR THE NUCLEAR REGULATORY COMMISSION ko M
/M Frederick J. He don, Director i
l Project Directorate 11-4 Division of Reactor Projects - I/II L
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 27, 1994 4
1 l
l ATTACHMENT TO LICENSE AMENDMENT N0.17s FACILITY OPERATING LICENSE NO. OPR-79 00CKET N0. 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 3-27a 3/4 3-27a i
4 d
i l
T
~
TABLE 3.3-4 (Continued) b ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 8
j FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES ii.
RCS Loop AT Equivalent to E
Power > 50% RTP Z
Coincident with Steam 215.0% of narrow range 214.4% of narrow
~
Generator Water Level-instrument span range instrument span Low-Low (Adverse) and Containment Pressure (EAM) 50.5 psig 50.6 psig or Steam Generator Water 210.7% of narrow range 210.1% of narrow range Level-Low-Low (EAM) instrument span instrument span d.
S.I.
See 1 above (all SI Setpoints) m s
[
e.
Loss of Power Start iy 1.
Voltage Sensors 25520 volts 25472 volts 2.
Load Shed Timer 1.25 seconds 1.25 seconds 20.09 seconds N
8 f.
Trip of Main Feedwater N.A.
N.A.
g Pumps
=
g.
Auxiliary Feedwater Suction a 3.21 psig (motor driven pump) a 2.44 psig (motor driven pump) l E
Pressure-Low a 13.9 psig (turbine driven a 12 psig (turbine driven pump) pump) 5 h.
Auxiliary Feedwater Suction 4 seconds (motor driven pump) 4 seconds 10.4 seconds
,2 Transfer Time Delays (motor driven pump)
=
5.5 seconds (turbine driven 5.5 seconds 10.55 seconds pump)
(turbine driven pump)
.b.
i
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