ML20100N193
| ML20100N193 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/01/1996 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20100N197 | List: |
| References | |
| NUDOCS 9603060211 | |
| Download: ML20100N193 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
\\.....J WASHINGTON, D.C. 2cespect TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 219 License No. DPR-77 j
i 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 8, 1995, 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.
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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:
l (2) Technical Soecifications The Technical Specificatiens contained in Appendices A and B, as revised through Amendment No. 219, 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 when the proper plant conditions can be established.
FOR THE NUCLEAR REGULATORY COMMISSION
, N))n.<
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Frederick J. Hebdon, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 1, 1996 t
ATTACHMENT TO LICENSE AMENDMENT NO. 219 FACILITV' 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 indicating the area of change.
REMOVE INSERT 3/4 3-27a 3/4 3-27a 3/4 3-27b 3/4 3-27b i
l
TABLE 3.?-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS c
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES ii. RCS Loop AT Equivalent to R145 Power > 50% RTP Coincident with Steam
=15.0% of narrow range a14.4% of narrow R155l Generator Water Level--
instrument span range instrument span Low-Low (Adverse)
R145 and Containment Pressure (EAM) so.5 psig s0.6 psig l
or Steam Generator Water a10.7% of narrow range-a10.1% of narrow range R155l Level--Low-Low (EAM) instrument span instrument span d.
S.I.
See 1 above (all SI Setpoints) e.
Loss of Power Start 1.
Voltage Sensors a5520 volts a5331 volts 2.
Load Shed Timer 1.25 seconds 1.25 10.25 seconds f.
Trip of Main Feedwater N.A.
N.A.
Pumps g.
Auxiliary Feedwater Suction a3.21 psig (motor driven pump) a 2.44 psig (motor driven pump) lR187 12 psig (turbine driven pump)
Pressure-Low a13.9 psig (turbine driven a
(Pump) h.
Auxiliary Feedwater Suction 4 seconds (motor driven pump) 4 seconds 10.4 seconds Transfer Time Delays (motor driven pump) 5.5 seconds (turbine driven pump) 5.5 seconds 10.55 seconds (turbine driven pump) j l
SEQUOYAH - UNIT 1 3/4 3-27a Amendment No. 29, 94, 129, 141, 151, 183, 219 m.
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1
-TABLE 3.3-4 (Continu*d)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 7.
LOSS OF POWER lR145 l
a.
6.9 kv Shutdown Board Undervoltage i
Loss of Voltage 1.
Voltage Sensors a 5520 volts a 5331 volts 2.
Diesel Generator Start
~ 1.25 seconds 1.25 10.25 seconds and Load Shed Timer I
b.
6.9 kv Shutdown Board-Degraded Voltage
[
1.
Voltage Sensors
'6456 volts a 6403.5 volts (dropout) s 6595.5 volts (reset) 2.
Diesel Generator Start and s 300 seconds s 370 seconds f
Load Shed Timer 3.
'SI/ M raded Voltage Logic
[
Enable Timer 9.5 seconds 9.5 1 2.0 seconds I
8.
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.
Pressurizet Pressure 1.
Not P-1.1, Automatic Unblock s1970 psi 3 s1975.2 psig of Safe';y Injection on Increasing Pressure i
2.
P-11, Enable Manual Block of a1962 psig als56.8 psig R145 Safety Injection on Decreasing Pressure i
i i
I i
SEQUOYAH - UNIT 1 3/4 3-27b Amendment No. 33, 129, 141, 219 r
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UNITED STATES y
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j NUCLEAR REGULATORY COMMISSION i
2 WASHINGTON, D.C. enana mi
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 209 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 8, 1995, 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 l
Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the
-Connission;
~~
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangerir.g 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.
L
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 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 209, 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 when proper plant conditions can be established.
FOR THE NUCLEAR REGULATORY COMMISSION p
w.
4 Frederick J. Hebdon',' Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of Issuance:
Harch 1,19%
4
\\
ATTACHMENT TO LICENSE AMENDMENT NO. 704 FACILITY OPERATING LICENSE NO. OPR-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 3-27a 3/4 3-27a 3/4 3-27b 3/4 3-27b 1
i i
r
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS~
FUNCTIONAL UNIT
. TRIP SETPOINT ALLOWABLE VALUES ii. RCS Loop AT Equivalent to Power > 50% RTP Coincident with Steam a15.0% of narrow range a14.4% of narrow R132 Generator Water Level--
. instrument span range instrument span Low-Low (Adverse) and Containment Pressure (EAM) s0.5 psig so.6 psig or Steam Generator Water a10.7% of narrow range
=10.1% of narrow range Level--Low-Low (EAM) instrument span instrument span d.
S.I.
See 1 above (all SI Setpoints) e.
Loss of Power Start 1.
Voltage Sensors a5520 volts a5331 volts 2.
Load Shed Timer 1.25 seconds 1.25 10.25 seconds f.
Trip of Main Feedwater N.A.
N.A.
Pumps g.
Auxiliary Feedwater Suction 3.21 psig (motor driven pump) a 2.44 psig (motor a
driven pump) lR175 12 psig (turbine lR84 Pressure-Low a 13.9 psig (turbine driven a
pump) driven pump)-
l h.
Auxiliary Feedwater Suction 4 seconds (motor' driven pump) 4 seconds 10.4 seconds Transfer Time Delays
.(motor driven pump)-
R116 5.5 seconds (turbine driven pump) 5.5 seconds 10.55 seconds (turbine driven pump)
SEQUOYAH - UNIT 2 3/4 3-27a Amendment Nos. 18, 84, 116,' 132, 175, 209
TABLE 3.3-4 (Continued)'
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT-TRIP SETPOINT ALLOWABLE VALUES 7.
LOSS OF POWER a.
6.9 kv Shutdown Board Undervoltage Loss of Voltage 1.
Voltage Sensors a 5520 volts a 5331 volts 2.
Diesel Generator Start 1.25 seconds 1.25 20.25 seconds and Load Shed Timer b.
6.9 kv Shutdown Board-Degraded voltage 1.
Voltage Sensors 6456 volts a 6403.5 volts (dropout) s 6595.5 volts (reset) 2.
Diesel Generator Start and Load Shed Timer s300 seconds s 370 seconds 3.
SI/ Degraded Voltage Logic Enable Timer 9.5 seconds 9.5 1 2.0 seconds 8.
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS a.
Pressurizer Pressure 1.
Not P-11, Automatic Unblock s1970 psig s1975.2 psig of Safety Injection on Increasing Pressure R132 2.
P-11, Enable Manual Block of a1962 psig a1956.8 psig Safety Injection on Decreasing Pressure SEQUOYAH - UNIT 2
.3/4 3-27b Amendment Nos. 18, 25, 116, 132, 209 f
..