ML20236B545
| ML20236B545 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/09/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236B548 | List: |
| References | |
| NUDOCS 8903210151 | |
| Download: ML20236B545 (10) | |
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UNITED STATES
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WASHINGTON, D. C. 20655 j
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 q
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 6, 1988, 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 1
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 (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 Comission's regulations;
\\D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.f 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.
J 8903210151 890309 PDR ADOCK 0500 7'
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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-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as i
revised through Amendment No. 93, 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.
FOR THE NUCLEAR REGULATORY COMMISSION I
h
% h i[re Y ick, Assist Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
1 Changes to the Technical Specifications Date of Issuance: March 9, 1989 l
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i ATTACHMENT TO LICENSE AMENDMENT NO.'104
~ 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 indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE' INSERT 3/4 4-3 3/4 4-3 3/4 4-4' 3/4 4-4*
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i 3/4.4.2 ' SAFETY VALVES - SHUTDOWN l
1 LIMITING CONDITION FOR OPERATION 3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE # with l
a lift setting of 2485 PSIG i 1%.*
f APPLICABILITY:
MODES 4 and 5 ACTION:
d With no pressurizer code safety valve OPERABLE, immediately suspend all opera-
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tions involving positive reactivity changes and place an OPERABLE RHR loop into j
operation:in the shutdown cooling mode.
I SURVEILLANCE REQUIREMENTS 4.4.2 No additional Surveillance Requirements other than those required i
by Specification 4.0.5.
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- The lift setting pressure shall correspond to ambient conditions of the valve of nominal operating temperature and pressure.
- A safety valve is not required OPERABLE provided at least one safety valve is I
removed from the pressurizer and the associated RCS breech is not covered by l
a pressure retaining membrane.
SEQUOYAH - UNIT 1 3/4 4-3 Amendment No. 104
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-REACTOR COOLANT SYSTEM
- 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING J
e SAFETY VALVES - OPERATING i
LIMITING CONDITION FOR OPERATION 3.4.3.1' Al'1 pressurizer code safety valves shall be OPERABLE with a lift setting of 2485 PSIG + 1%.*
APPLICABILITY: ' MODES 1, 2 and 3.
ACTION:
'With'one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or 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 at least HOT' SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.
- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
J SEQUOYAH - UNIT 1 3/4 4-4
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UNITED STATES l'Og n
NUCLEAR REGULATORY COMMISSION l
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t TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328
, SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 6, 1988, 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 assur-a (1) that the activities authorized by this amendment can be cont...:ted 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.
e '
' Accordingly, the license is amended by changes to the Technical
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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 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 93, are hereby incorporated in the license.
The licensee sha11' 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 s
n Yh-r awe' lack, Assistant Director or Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 9, 1989 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 93 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages 1
identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal i
lines indicating the area of change. Overleaf pages* are provided to maintain document completeness, j
REMOVE INSERT l
3/4 4-5 3/4 4-5*
3/4 4-6 3/4 4-6 i
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' REACTOR C00LANTcSYSTEM
' COLD SHUTDOWN
-LIMITING CONDITION FOR OPERATION 3.4.1.4.lTwo#residualheatremoval(RHR)loopsshall.beOPERABLE*andat least one RHR loop shall be in operation.**
APPLICABILITY: MODE 5; I
ACTION:
a.-
With less than the above required RHR/ reactor coolant loops OPERABLE,
'immediately initiate. corrective action to return the required RHR/
reactor coolant loops to OPERABLE status as soon as possible.
b.
With no RHR loop in operation,. suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
SURVEILLANCE REQUIREMENTS
'4.4.1.4 The residual heat removal loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 0ne RIiR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other RHR loop is OPERABLE and in operation.
Four filled reactor 1
coolant loops with at least 2 steam generators having levels greater than or
' equal to 10 percent (wide-range indication) may be substituted for one RHR i
loop.
- The normal or emergency power source may be inoperable.
- The RHR pumps may be de-energized for up to I hour provided 1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and 2) core outlet temperature is maintained at least 10 F below saturation temperature.
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SEQUOYAH - UNIT 2 3/4 4-5 i
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L REA'CTOR COOLANT SYSTEM.
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3/4.4l2 SAFETY VALVES
' SHUTDOWN.
LIMITING CONDITION FOR OPERATION 3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE #.with a l
lift setting of 2485 PSIG-1%.*
APPLICABILITY: MODES 4 and 5.
ACTION:
With'no. pressurizer code safety valve OPERABLE,.immediately. suspend all-..
operations involving positive reactivity changes and place an OPERABLE residual heat removal. loop'into operation in the shutdown cooling mode.
SURVEILLANCE REQUIREMENTS 4.4.2 No additional Surveillance Requirements other than those required by Specification 4.0.5.
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- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
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- A safety valve is not required OPERABLE provided at least one safety valve is removed from.the pressurizer and the associated RCS breech is not covered by a pressure retaining membrane.
I SEQUOYAH - UNIT 2 3/4 4-6 Amendment No.
93 i
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