ML20084R593
| ML20084R593 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/01/1995 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20084R595 | List: |
| References | |
| NUDOCS 9506090343 | |
| Download: ML20084R593 (14) | |
Text
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UNITED STATES i
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20556 4001
'+9
,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 201 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 6, 1995, 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 (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 Comission's regulations; D.
The issuance of this ameedment 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 amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9506090343 950601 PDR ADOCK 05000327 P
.c-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment i
and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Soecifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 201, 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.
A FOR THE NUCLEAR REGULATORY COMMISSION eb r
Frederick J. Hebd n, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 1, 1995
. =.
o ATTACHMENT TO LICENSE AMENDMENT NO. 201 FACILITY OPERATING LICENSE NO. DPR-77 i
DOCKET NO. 50-327 i
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 JJigggI 1-2 1-2 1-5 1-5 1-8 1-8 t'
-w
,n_.
DEFINITIONS CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:
a.
Analog channels - the injection of a simulated signal into the channel
-as close to the sensor as practicable to verify OPERABILITY including alarm and/or. trip functions.
b.
Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
~
c.
Digital channels - the injection of a simulated signal into the channel as close to the sensor input to the process racks as practicable to verify OPERABILITY including alarm and/or trip functions.
CONTAINMENT INTEGRITY l.7 CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident conditions are either:
1)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2)
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-2 of Specification 3.6.3.
b.
All equipment hatches are closed and sealed.
c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3, d.
The containment leakage rates are within the limits of Specification 4.6.1.1.c, e.
The sealing mechansim associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE, and I
f.
Secondary containment bypass leakage is within the limits of Specification 3.6.1.2.
i CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
CORE ALTERATION 1.9 CORE ALTERATIONS shall be the movement of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMIT REPORT 1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.14.
Unit operation within these operating limits is addressed in individual specifications.
SEQUOYAH - UNIT 1 1-2 Amendment No. 12,71,130,141,155, 176, 201
~
9-t i
[
t 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube i
leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel' wall.
i PROCESS CONTROL PROGRAM (PCP) 1.23 The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that the processing
. and packaging of solid radioactive wastes based on demonstrated processing of i
actual or simulated wet solid wastes will be accomplished in such a way as to i
assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; and other requirements governing the disposal of solid radioactive wastes.
PURGE - PURGING 1.24 PURGE or PURGING is the controlled process of discharging air or gas' f
from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
OUADRANT POWER TILT RATIO l
1.25 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.
I RATED THERMAL POWER (RTP) 1.26 RATED THERMAL POWER (RTP) shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.
REACTOR TRIP SYSTEM RESPONSE TIME 1.27 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.
REPORTABLE EVENT 1.28 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
SEQUOYAH - UNIT 1 1-5 Amendment No. 12, 71, 141, 148, 155, 201
TABLE 1.1 OPERATIONAL MODES j
i REACTIVITY
% RATED AVERAGE COOLANT HQQE CONDITION. K;,,
IHERMAL POWER
- TEMPERATURE 1.
POWER OPERATION 20.99
>5%
2350*F l
2.
STARTUP 20.99
$5%
2350*F 3.
HOT STANDBY
<0.99 0
2350*F l
1 4.
HOT SHUTDOWN
<0.99 0
350*F > T,,
>200*F 5.
COLD SHUTDOWN
<0.99 0
s200*F 6.
REFUELING **
$0.95 0
s140*F l
Excluding decay heat.
- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
SEQUOYAH - UNIT 1 1-8 Amendment No. 71, 201
a uauq
_y-t UNITED STATES i
E NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2055%0001
'+,.....f TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0VOYAH NUCLEAR PLANT. UNIT 2
' AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 191 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 April 6, 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 (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.
f
>i
. 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 i
amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised t'hrough Amendment No. 191, 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 1
r-Frederick J. Hebd#n, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 1, 1995 i
l
ATTACHMENT TO LICENSE AMENDMENT NO.191 FACILITY OPERATING 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.
r REMOVE INSERT 1-2 1-2 1-5 1-5 1
I i
I i
w I
DEFINITIONS j
CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:
a.
Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
b.
Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
c.
Digital channels - the injection of a simulated signal into the chan-nel as close to the sensor input to the process racks as practicable to verify OPERABILITY including alarm and/or trip functions.
CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident conditions are either:
1)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2)
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-2 of Specification 3.6.3.
b.
All equipment hatches are closed and sealed.
c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3, d.
The containment leakage rates are within the limits of Specifica-tion 4.6.1.1.c, e.
The sealing mechansim associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE, and f.
Secondary containment bypass leakage is within the limits of Speci-fication 3.6.1.2.
CONTROLLED LEAKAGE 1.6 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
CORE ALTERATION 1.9 CORE ALTERATIONS shall be the movement of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the head removed and fuel in the vessel.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMIT REPORT 1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document j
that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.14.
Unit operation within these operating limits is addressed in individual specifications.
SEQUOYAH - UNIT 2 1-2 Amendment No. 63,117,132,146, 167, 191
e DEFINITIONS e
OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise ;;eroved by the Commission.
PRESSVRE B0VHDARY LEAKAGE 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.
PROCESS CONTROL PROGRAM (PCP) 1.23 The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; and other requirements governing the disposal of solid radioactive wastes.
PURGE - PURGING 1.24 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
OVADRANT POWER TILT RATIO 1.25 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated l
output to the average of the lower excore detector calibrated outputs, whichev-er is greater.
SEQUOYAH - UNIT 2 1-5 Amendment No. 63, 134, 146, 191
-