ML20063H631
| ML20063H631 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/17/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063H635 | List: |
| References | |
| NUDOCS 8209020044 | |
| Download: ML20063H631 (11) | |
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendaent No. 15 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Sequoyah Huclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated August 2,1982, complies with the standards and requirements of the Atoraic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; 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 j
in compliance with the Commission's regulations; 0.
The issuance of this amendment will not be inimical to the cannon 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 hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachments to this license amend-
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ment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby i
amended to read as follows:
r (2) Technical Spacif1 cations The Technical Specifications contained in Appendix A, as revised through Amendment No.15, are hereby incorporated into the license.
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, The licensee shall operate the facility in accordance 'with the Technical Speciftcations.
3.
This license amenduent was effective August 3,1982.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing Attach 1ent:
Appendix A Technical Specification Changes Date of Issuance: August 17, 1982 t
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ATTACHMENT TO LICENSE AMENDMENT NO. 15 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 m
Replace the following pages of the Appendix "A". Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The correspondin'g over-leaf pages are also provided to maintain document completeness.
Overleaf Amended Page Page 3/4 3-51 3/4 3-52 3/4 3-54 3/4 3-53 E
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TABLE 3.3-9 m
j REMOTE SHUTDOWN MONITORING INSTRUMENTATION 5!>*
MINIMUM READOUT MEASUREMENT CHANNELS E
INSTRUMENT LOCATION RANGE OPERABLE w
6 w
1.
Source Range Nuclear Flux NOTE 1 1 to 1 x 10 cp,
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2.
Reactor Trip Breaker Indication at trip switchgear OPEN-CLOSE{.,.
1/ trip oreaker 3.
Reactor Coolant Terrperature -
NOTE 1 0-650*F 1
Hot Leg 4.
Pressurizer Pressure NOTE 1 0-3000 psig' 1
5.
Pressurizer Level NOTE 1 0-525 in 1
x
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6.
Steam Generator Pressure NOTE 1 0-1200 psig 1/ steam generater b
7.
Steam Generator Level NOTE 2 or near Auxilary F. W. 0-100%
Pump 1/ steam generator 8.
Full Length Control Rod Position Auxilary Instrument I insertion limit limit Switches Room: Racks R41-44 On-off switch / rod 9.
RHR Flow Rate NOTE 1 0-4500 gpm 1
10.
RHR Temperature NOTE 1 50-400 F 1
11.
Auxiliary Feedwater Flow Rate NOTE 1 0-880 gpm.
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REMOTE SHUTOOWN MONITORING INSTRUMENTATION S
E MINIMUM READ 0UT MEASUREMENT CHANNELS E
INSTRUMENT LOCATION RANGE OPERABLE w
H 12.
Pressurizer Relief Tank Pressure NOTE 1 0-100 psig 1
- 13. Containment Pressure NOTE 1
-1 to +15 psig 1
NOTE 1:
Auxiliary Control Room Panel 1-L-10 NOTE 2:
Auxiliary Control Room Panels 1-L-llA and 1-L-llB M
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TABLE 4.3-6 mS REMOTE SHUTDOWN MONITORING INSTRUMENTATION
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SURVEILLANCE REQUIREMENTS x
=
CHANNEL CHANNEL
{
INSTRUMENT CHECK CALIBRATION
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1.
Source Range Nuclear Flux M
R 2.
Reactor Trip Breaker Indication M
N.A.
3.
Reactor Coolant Temperature - Hot Leg M
R 4.
Pressurizer Pressure M
R 4
5.
Pressurizer Level M
R 6.
Steam Generator Pressure M
R 7.
Steam Generator Level M
R w2 8.
Full Length Control Rod Position Limit Switches M
R w
m 9.
RHR Flow Rate M
R 10.
RHR Temperature M
R
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Auxiliary Feedwater Flow Rate M
R k
12.
Pressurizer Relief Tank Pressure M
R a
g 13.
Containment Pressure M
R ft.
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. INSTRUMENTATION CHLORINE DETECTION SYSTEMS sy=
1 LIMITING CONDITION FOR OPERATION
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3.3.3.6 Two independent chlorine detection ~ systems, with their alarm / trip setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm, shall b2 OPERABLE.
1 APPLICABILITY: ALL MODES ACTION:
a.
With one chlorine detection system inoperable, restore the inoperable detection system to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operation of the control room emergency ventilation _ system in the recirculation mode of operation.
' 'si: 1 b.
With both chlorine detection systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate i
and maintain operation of the control room emergency ventilation 1-system in the recirculation mode of operation.
t c.
The provisions of Specification 3.0.4 are not applicable.
d.
The provisions of Specification 3.0.3 are not applicable in MODE 6.
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SURVEILLANCE REQUIREMENTS 4.3.3.6 Each chlorine detection system shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
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SEQUOYAH - UNIT 1 3/4 3-54
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TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMEN 0HENT TO FACILITY OPERATING LICENSE Amendment No. 6 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated August 2,1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; r
B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; 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 (11) 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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have l
been satisfied.
l 2.
Accordingly, the license is hereby amended by page changes to the Appendix A l
Technical Specifications as indicated in the attachments to this license anendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
l (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 6, are hereby incorporated into the license.
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.2-i The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment was effective August 3,1982.
FOR THE NilCLEAR REGULATORY COMMISSION Elinor G. Mensam, Chief Licensing Branch No. 4 Division of Licensing i
Attaclinent:
Appendix A Technical-i Specification Changes Date of Issuance: August 17, 1982 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 6 FACILITY OPERATING LICENSE NO. DPR-79 c>
DOCKET NO. 50-328 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding over-leaf pages are also provided to maintain document completeness.
Overleaf Amended Page Page 3/4 3-53 3/4 3-54 ca 4
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T[*BLE 3.3-9 (Continued)
'[j REMOTE SHUTDOWN MONITORING INSTRUMENTATION 5
MINIMUM ci READOUT MEASUREMENT CHANNELS q
INSTRUMENT LOCATION RANGE OPERABLE TV
- 12. Pressurizer Relief Tank Pressure NOTE 1 0-100 psig 1
- 13. Containment Pressure NOTE 1
-1 to +15 psig i
NOTE 1:
Auxiliary Control Room Panel 2-L-10 NOTE 2:
Auxiliary Control Room Panels 2-L-11A and 2-L-11B is J
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TABLE 4.3-6 m
.o"g REMOTE SHUT 00WN MONITORING INSTRUMENTATION g
SURVEILLANCE REQUIREMENTS
=
t c5 CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Source Range Nuclear Flux M
R 2.
Reactor Trip Breaker Indication M
N.A.
3.
Reactor Coolant Temperature - Hot Leg M
R 4.
Pressurizer, Pressure M
R 5.
Pressurizer Level M
R
=
6.
Steam Generator Pressure M
R c.n 7.
Steam Generator Level M
R 8.
Full Length Control Rod Position Limit Switches M
R 9.
RHR Flow Rate M
R 10.
RHR Temperature M
R 11.
Auxiliary Feedwater Flow Rat 6 ;
M R
N e
12.
Pressurizer Relief Tank Pressure M
R S
13.
Containment Pressure M
R E
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