ML20217D264

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Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively, Deleting License Condition 2.C(22).A from License DPR-77 & License Condition 2.C.(16).b from License DPR-79
ML20217D264
Person / Time
Site: Sequoyah  
Issue date: 10/12/1999
From: Peterson S
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217D270 List:
References
NUDOCS 9910150097
Download: ML20217D264 (7)


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t-UNITED STATES E

j NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20555 4001

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 248 License No. DPR-77

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. ' The application for amendment by Tennessee Valley Authority (the licensee) dated f

March 2,1999, complies with the standards ano 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; 8.

The facility will o' perate 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

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PDR ADOCK 05000327 P

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l 2.' Accordingly, the license is amended as indicated in the attachment to this license j

amendment.

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 l

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_hdx Sheri R. Peterson, Chief, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License Date of issuance:

October 12, 1999

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ATTACHMENTTO LICENSE AMENDMENT NO. 248 4

FACILITY OPERATING l.lCENSE NO. DPR-77 DOCKET NO. 50-327

. Replace the following page of Operating License No. DPR-77 with the attached page. The revised page is identified by amendment number and contains a vertical line indicating the arr. ;f change.

Remove Paae insert Pace 8.

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- (19) Mechanical Snubbers This condition is deleted.

l R239 l

(20) ' Low Temoerature O'veroressure Protection (Section 5.2.21 l

At the first outage of cufficient duration, but no later than startup following the second refueling outage TVA shallinstall an overpressure mitigation system which meets NRC requirements, L

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' (21) Control Rod Guide Thimble (Section 4.2)

Prior to startup after first refueling, TVA shall submit the details of the inspection program for control rod guide thimble tube wall wear for NRC approval.

(22) TMI Action Plan Full-Power Conditions l

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Each of the following conditions shall be completed to the satisfaction of the NRC by the times indicated:

l A,! Safarv Enoineerina Groun (Section 22.2.1.B.1.21 This condition is deleted.

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Short-Term Accident Analvais and Procedure Revision (Section 22.2. l.C.11 Within thirty effective full-power days, TVA shall revise Emergency Operating Procedures and brief the operators on the revision.

C.'.

Control Room Desion (Section 22.2. l.D.11.

TVA shall consider the benefits of installing da'a recording and logging equipment in the control room to correct the deficiencies R27 associated with the trending of important parameters on strip chart recorders used in the control room as part of the Detailed Control Room i

Desion Raview, implementation shall be carried out in accordance with j

SECY 821118.

j Amendment 23, 235, 248 l

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  1. Mou g-UNITED STATES j

,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20S55 0001 4-* * * +,o 9

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 239 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 i

March 2,1999, 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

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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 ;an 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.

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2. Accordingly, the license is amended as indicated in the attachment to this license amendment.
3. This license amendment is effective as of its date of issuance, to be implerr.< coted no later than 45 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Y

hs Sheri R. Peterson, Chief, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation -

Attachment:

Changes to the Facility Operati,ng License Date of issuance: October 12, 1999 a

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l l-l' ATTACHMENT TO LICENSE AMENDMENT NO. 239 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following page of Operating License No. DPR-79 with the attached page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.

Remove Paae Insert Paae 6-6 j

(13). Fire ProtecGn TVA shall implement and maintain in effect all provisions of the approved fire protection program referenced in Sequoyah Nuclear Plant's Final Safety Analysis Report and as approved in NRC Safety Evaluation Reports contained in NUREG-0011, Supplements 1, 2, and 5. NUREG 1232, Volume 2, NRC letters R218 dated May 29 and October 6,1986, and the Safety Evaluation issued on August 12,1997, for License Amendment No. 218, subject to the following provision:

TVA may make changes to ue approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(14) Comoliance With Reaulatorv Guide 1.97 TVA shall implement modifications necessary to comply with Revision 2 of Regulatory Guide 1.97, ' Instrumentation for Light Water Cooled Nuclear Power Plants to assess Plant CoMitions R45 During and Following an Accident," dated December 1900 by startup from the Unit 2 Cycle 4 refueling outage.

(15)

Corrosion of Carbon Steel Pioino TVA shall carry out a surveillance program on corrosion of carbon steel piping in accordance with TVA document SORD j 328/81-10 dated August 25,1981, and procedures for implementation are to be submitted for NRC concurrence by i

October 15,1981.

(16) NOREG-0737 Conditions (Section 22.21 Each of the following conditions shall also be performed to the satisfaction of the NRC:

R2 a.

Shift Technical Advisor (Section 22.2.1, A 1.11 TVA shall provide a fully-trained on-shift technical advisor to the shift operations supervisor.

l R169 b.

Indeoendent Safetv Enoineerino Groua (Section 22.2. l.8.1.21 This condition is deleted.

l Amendment Nos. 45, 169, 218, 239