ML20206G369
| ML20206G369 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/04/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206G373 | List: |
| References | |
| NUDOCS 9905070184 | |
| Download: ML20206G369 (9) | |
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UNITED STATES t
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- j NUCLEAR REGULATORY COMMISSION o
t WASHINGTON, D.C. 20555-0001 4
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TENNESSEE VALLEY AUTHORITY l
. DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 244 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amenoment by Tennessee Valley Authority (the licensee) dated January 15,1999, 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 autho ized by this amendment can be conducted without endangering the c.ealth 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 9905070184 990504 PDR ADOCK 05000327 P
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i 1
j 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-77 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.,?A4 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 no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (i'tggd Pub ~
Sheri R. Peterson, Chief, Section 2 Project Directorate il Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
May 4, 1999
)
)
l L
l-ATTACHMENT TO LICEtJ9E AMENDMENT NO. 244 l
FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 1
Revise the Appendix A Technical Specifications by removing the page identified below and l
inserting the enclosed page. The revised page is identified by the captioned amendment l
number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 1-17 3/4 1-17 i
~
7.
l i
_P,EACTIVITY CONTROL SYSTEMS l
j POSITION INDICATION SYSTEMS - OPERATING 1
LIMITING CONDITION FOR OPERATION 3.1.3.2 -The. shutdown and control rod position indication system and the demand position indication system shall be OPERABLE and capable of determining the
' control rod positions within i 12 steps.
~
j j
l APPLICABILITY:
MODES l'.and 2.
'I ACTION:
With a maximum of one rod position indicator per bank inoperable a.
either:
j 1.
Determine the position of the non-indicating rod (s) indirectly lR217 by the movable incore detectors at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and
[
immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, l
b.
With more than one rod position indicator per bank inoperable either:
1.
Determine the position of the non-indicating rod (s) indirectly by the movable incore detectors at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and immediately.after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination i
of the rod's position, and
'2.
Place the control rods under manual control, and monitor and record Reactor Coolant System average temperature (Tavg) at least once per hour, and 3.
Restore the rod position indicators to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> such that a maximum of one rod position indicator per bank j
is inoperable, or 4.
Be in 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 />.
c.
With a maximum of one demand position indicator per bank inoperable l
either:
1.
Verify that all rod position indicators for the affected bank j
are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once pet 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or l
2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
lR217 SEQUOYAH - UNIT 1 3/4 1-17 Amendment No. 118, 213, 244
p p** "' Ng 13 UNITED STATES yo a-S NUCLEAR REGULATORY COMMISSION 5f WASHINGTON, D.C. 20555 4001 k..... f
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i TENNESSEE VALLEY AUTHORITY l
DOCKET NO. 50-3jiL8 l
SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 235 License No. DPR 79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i 1
A.
The application foi amendment by Tennessee Valley Authority (the licensee) j dated January 15,1999, 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.
i,
. 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. 235 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 no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
[h% k h h~-
Sheri R. Peterson, Chief, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 4, 1999
p; ATTACHMENT TO LICENSE AMENDMENT NO. 235 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 l
Revise the Appendix A Technical Specifications by removing the pages identified below and l
inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginallines indicating the area of change.
REMOVE INSERT 3/4 1-17 3/4 1-17 3/41-17a i
1 4
l 1.
i
1 s-e, REACTIVITY CONTROL SYSTEMS
-POSITION' INDICATION SYSTEMS-OPERATING LIMITING-CONDITION FOR OPERATION 3.1.3.2 The shutdown and control rod position indication system and the demand position indication system shall'be OPERABLE and capable of determinin,g the control rod positions within t'12 steps.
APPLICABILITY: Modes 1 and 2.
' ACTION:
With a maximum of one rod position indicator per bank inoperable a.
either:
1.
Determine the position of the non-indicating rod (s) indirectly by the movable incore detectors at least once por 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and l
immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.
Reduce THERMAL POWER TO less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, b.
With more than one rod position indicator per bank inoperable either:
1.
Determine the position of the non-indicating rod (s) indirectly by the movable incore detectors at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and
)
immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, and 2.
Place the control rods under manual control, and monitor and record Reactor Coolant System average temperature (Tavg) at least once per hour, and 3.
Restore the' rod position indicators to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> such that a maximum of one rod position indicator per bank is inoperable, or
- 4.
Be in 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 />.
c With a maximum of one demand position indicator per bank inoperable l
either 1.
Verify that all rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn-rod of the bank are.within a maximum of 12 steps of each other at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or l
2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
-SEQUOYAH - UNIT 2 3/4 1-17 Amendment No. 235 -
EEACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS-OPERATING SURVEILLANCE REQUIREMENTS 4.1.3.2 Each rod position indicator shall be determined to be OPERAELE by
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verifying that the demand position indication system and the rod position indication system agree within 12 steps at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indication system at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
o SEQUOYAH - UNIT 2 3/4 1-17a Amendment No. 235 i
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