ML20064E480
| ML20064E480 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-77-A-018, DPR-77-A-18, DPR-79-A-009, DPR-79-A-9) |
| Issue date: | 12/23/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064E484 | List: |
| References | |
| NUDOCS 8301060022 | |
| Download: ML20064E480 (10) | |
Text
4 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDiiENT TO FACILITY OPERATING LICENSE Anendment No. 18 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated July 22, 1932, 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; 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 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 Connission'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-ment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.18, are hereby incorporated into the license.
8301060022 821223 PDR ADOCK 05000327 P
PDR omcE)
........aa..."na a
...aa..
SUHNOME)
........... ~......
........ ~.......
......."a.a
=
a.anaaaana.a.
DATE)
..."...a...~..
..a n.
. a eaa na
......="..a..
. ***.aaa a
"aa*
~~~" "
anc ronu m pmeci sacu ano OFFICIAL RECORD COPY usa m su-m eco
w F
q)
U
-2.
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 NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing Attactnent :
Appendix A Technical Speciftcation Changes Date of Issuance: December 23, 1982 T
O-
.D. O B AD:L.....
.Y....csg... [......
. L.A..:.D.JL L.B..#. 4 DL.: L B.... #.4...
D.L.. :
- . 4....... O..E L..D....t...
j orric,6
.e--o.stac.a.nz.tm
..mm.M1',.s
- e.......@sar a
.1....e
.s.w...........m.............uaotw....
..g../.ty 82 gg/.82
}.
,..2...........10/.17.82 9/tb/.82.
.../.../.8 2
.. /..(L.../.82 9
9 o.ro wnc ronu ais o>sa nscu oao OFFICIAL RECORD COPY usapo. au-asm L
ATTACHMENT TO LICENSE AMENDMENT NO. 18 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Anendment number and contain vertical lines indicating the area of change.
Araended Page 3/4 6-15 3/4 7-14 OF FICE )
suauue >
oare y wnc ronu aia tio-so> uncu ono OFFICIAL RECORD COPY usam mi--m.we
CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.9 One pair (one purge supply line and one purge exhaust line) of containment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed.
Operation with purge supply or exhaust isolation valves open for either purging or venting shall be limited to less than or equal to 1000 houre oer 365 days.
The 365 day cumulative time period will begin every January 1.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With a purge supply or exhaust isolation valve open in excess of the above cumulative limit, or with more than one pair of containment purge systera lines open, close the isolation valve (s) in the purge line(s) within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
.c_
SURVEILLANCE REQUIREMENTS l
4.6.1.9.1 The position of the containment purge supply and exhaust isolation valves shall be determined at least once per 31 days.
4.6.1.9.2 The cumulative time that the purge supply and exhaust isolation valves are open over a 365 day period shall be determined at least once per 7 days.
t t
l SEQUOYAH - UNIT 1 3/4 6-15 Amendment No. 18 l
PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5 The ultimate heat sink shall be OPERABLE with:
a.
A minimum water level in the forebay at or above elevation 668 feet Mean Sea Level, USGS datum, and b.
The average temperature of water at the ERCW system suction of less than or equal to 83 F.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
a.
With the water level in the forebay less than 668 feet Mean Sea Level USGS datum.be at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The forbay portable makeup water pumping station shall be deployed within 5 days.
b.
With the average temperature of the water at the ERCW system suction greater than 83 F be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in v'
COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIRMENTS 4.7.5.1 The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the a~verage temperature and water level to be within their limits.
4.7.5.2 The components of the makeup water system shall be inspected and the forebay portable makeup pumps and drives tested at least once per 92 days.
SEQUOYAH - UNIT 1 3/4 7-14 Amendment No.18
1 Q
\\
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 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 July 22, 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; B.
The facility will operate in confomity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; 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 hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereoy amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 9, are hereby incorporated into the license.
omcs) sunsauc>
oarr y anc ronu sta oo.co) Nacu cao OFFiClAL RECORD COPY usa mi--mm
- t. -
. The licensee shall operate the facility in accordance with the Technical Sp2cifications.
3.
This license anendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensaa, Chief Licensing Branch No. 4 Division of Licensing Attactinent:
Appendix A Technical Specification Changes Date of Issuance: December 23, 1982 l
l l
l l
l
)
.u;pl.gs...a
..ph.;LB.14
..oL:M4
.,0 ELD D%) #,,
,, m 9. [,
..C5,8.. lJb o,na, sun-o MIS &mc..mineB.2..c.s.t M..
M.;f, v,,,,,,,,
Yd....s.am..
...Mvf
........wau.ue,r...
~
. 9/.l.b 82........S/.f.2/82.....9/.\\b82...
II9/M/82..../l)/M/82..
Jy.7 B2.......10/d/82..
/
oan y
! anc ronu ais oo-so> nncu eno OFFICIAL RECORD COPY usceo: im-mwo
.?
~
ATTACHMENT TO LICENSE AMENDMENT NO.9 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by knendment ntanber and contain vertical lines indicating the area of change.
Anended Page 3/4 6-15 3/4 9-7 orrice >
sonaur >
ua1r >
rac ronu ais now recu oua OFFICIAL RECORD COPY usam ini-mm
CONTAINMENT SYSTEMS T
CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.9 One pair (one purge supply line and one purge exhaust line) of.
containment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed.
Operation with purge supply or exhaust isolation valves open for either purging or venting shall be limited to less than or equal to 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per 365 days.
The 365 day cumulat.ive time period will begin every January 1.
APPLICABILITY:
MODES 1, 2, 3, and 4 ACTION:
With a purge supply or exhaust isolation valve open in excess of the above cumulative limit, or with more than one pair of containment purge system lines open, close the isolation valve (s), in the purge line(s) within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.9.1 The position of the containment purge supply and exhaust isolation valves shall be determined at least once per 31 days.
4.6.1.9.2 The cumulative time that the purge supply and exhaust isolation valves are open over a 365 day period shall be determined at least once per 7 days.
SEQUOYAH - UNIT 2 3/4 6-15 Amendment No.9
REFUELING OPERATIONS 3/4.9.6 MANIPULATOR CRANE LIMITING CONDITION FOR OPERATION 3.9.6 The manipulator crane and auxiliary hoist shall be used for movement of drive rods or fuel assemblies and shall be OPERABLE with:
a.
The manipulator crane used for movement of fuel assemblies having:
1.
A minimum capacity of 2750 pounds, and 2.
An overload cut off limit less than or equal to 2700 pounds.
b.
The auxiliary hoist used for latching and unlatching drive rods having:
1.
A minimum capacity of 610 pounds, and 2.
A load indicator which shall be used to prevent lifting loads in excess of 600 pounds.
APPLICABILITY:
During movement of drive rods or fuel assemblies within the reactor pressure vessel.
ACTION:
With the requirements for crane and/or hoist OPERABILITY not satisfied, suspend use of any inoperable manipulator crane and/or auxiliary hoist from operations involving the movement of drive rods and fuel assemblies within the reactor pressure vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.6.1 Each manipulator crane used for movement of fuel assemblies within the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 2750 pounds and demonstrating an automatic electrical load cut off when the crane load exceeds 2700 pounds.
4.9.6.2 Each auxiliary hoist and associated load indicator used for movement of drive rods within the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 610 pounds.
t-SEQUOYAH - UNIT 2 3/4 9-7 Amendment No.9 l
-