ML20069D803: Difference between revisions

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II September 17, 1982 TVA-SQN-TS-36 i
TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II September 17, 1982 TVA-SQN-TS-36 i
Mr. Harold R. Denton, Dhector Office of Nuclear 3eactor Regulation
Mr. Harold R. Denton, Dhector Office of Nuclear 3eactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
  ,      U.S. Nuclear Regulatory Commission Washington, DC 20555


==Dear Mr. Denton:==
==Dear Mr. Denton:==
 
In the Matter of
In the Matter of                                   )             Docket Nos. 50-327 Tennessee Valley Authority                         )                             50-328 In accordance with 10 CFR Part 50.59, we are enclosing 40 copies of a requested amendment to the operating licenses DPR-77 and DPR-79 for a change to the Sequoyah Nuclear Plant units 1 and 2 technical specifications. The proposed changes to the technical specifications and justifications for the changes are provided in the following enclosures.
)
Enclosure 1 - Change No. 1 - Diesel Generator Battery Float Voltage Enclosure 2 - Change No. 2 - Isolation Times for Containment Isolation Valves Enclosure 3 - Change No. 3 - Instrumentation Surveillance Requirement Test Frequency of Tables 4.3-1 and 4.3-2 Enclosure 4 - Change No. 4 - Changes to Reflect Installation of Permanent Hydrogen Mitigation System Enclosure 5 - Change No. 5 - Addition of Second Level of Undervoltage Protection NRC approval of the changes to the technical specifications, provided in Enclosures 4 and 5, is required for unit 1 of our Sequoyah Nuclear Plant before startup from the present refueling outage.
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 In accordance with 10 CFR Part 50.59, we are enclosing 40 copies of a requested amendment to the operating licenses DPR-77 and DPR-79 for a change to the Sequoyah Nuclear Plant units 1 and 2 technical specifications. The proposed changes to the technical specifications and justifications for the changes are provided in the following enclosures. - Change No. 1 - Diesel Generator Battery Float Voltage
, - Change No. 2 - Isolation Times for Containment Isolation Valves - Change No. 3 - Instrumentation Surveillance Requirement Test Frequency of Tables 4.3-1 and 4.3-2 - Change No. 4 - Changes to Reflect Installation of Permanent Hydrogen Mitigation System - Change No. 5 - Addition of Second Level of Undervoltage Protection NRC approval of the changes to the technical specifications, provided in Enclosures 4 and 5, is required for unit 1 of our Sequoyah Nuclear Plant before startup from the present refueling outage.
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                                                                                        /@
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PDR ADOCK820922O277 P           05000327 82f917 PDR An Equal Opportunity Employer
PDR ADOCK820922O277 82f917 05000327 P
PDR An Equal Opportunity Employer


4-                                   .
4-
Mr. Harold R. Denton, Director                             September 17, 1982 In accordance with the provisions of 10 CFR Part 170.22, we have determined the proposed amendment to be Class IV for unit 1 and Class I for unit 2.
. Mr. Harold R. Denton, Director September 17, 1982 In accordance with the provisions of 10 CFR Part 170.22, we have determined the proposed amendment to be Class IV for unit 1 and Class I for unit 2.
This classification is based on the fact that the amendment involves several changes of the Class III type incorporated into this amendment and involves a second essentially identical unit at the same site. The remittance of $12,700 is being wired to the Nuclear Regulatory Commission, Attention: Licensing Fee Management Branch.
This classification is based on the fact that the amendment involves several changes of the Class III type incorporated into this amendment and involves a second essentially identical unit at the same site. The remittance of $12,700 is being wired to the Nuclear Regulatory Commission, Attention: Licensing Fee Management Branch.
Very truly yours, TENNESSEE VALLEY AUTHORITY DS W D. S. Kammer Nuclear Engineer Sworn to   d subscrib d be ore me this./7 day of,.         -
Very truly yours, TENNESSEE VALLEY AUTHORITY DS W D. S. Kammer Nuclear Engineer Sworn to d subscrib d be ore me this./7 day of,.
                                    ,  1982 ftWJwk   ~
1982 ftWJwk Notar[Public
Notar[Public My 06mmission Expires     -
~
i    9,![ 6 M Enclosures (40) cc: U.S. Nuclear Regulatory Commission Region II Attn:     Mr. James P. O'Reilly, Regional Administrater 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303}}
My 06mmission Expires 9,![ 6 M i
Enclosures (40) cc:
U.S. Nuclear Regulatory Commission Region II Attn:
Mr. James P. O'Reilly, Regional Administrater 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303}}

Latest revision as of 11:00, 16 December 2024

Application to Amend Licenses DPR-77 & DPR-79,revising Tech Specs Re Diesel Generator Battery Float Voltage, Isolation Times for Containment Isolation Valves & Instrumentation Surveillance Requirement Test
ML20069D803
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 09/17/1982
From: Kammer D
TENNESSEE VALLEY AUTHORITY
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20069D807 List:
References
TVA-SQN-TS-36, NUDOCS 8209220277
Download: ML20069D803 (2)


Text

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II September 17, 1982 TVA-SQN-TS-36 i

Mr. Harold R. Denton, Dhector Office of Nuclear 3eactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Denton:

In the Matter of

)

Docket Nos. 50-327 Tennessee Valley Authority

)

50-328 In accordance with 10 CFR Part 50.59, we are enclosing 40 copies of a requested amendment to the operating licenses DPR-77 and DPR-79 for a change to the Sequoyah Nuclear Plant units 1 and 2 technical specifications. The proposed changes to the technical specifications and justifications for the changes are provided in the following enclosures. - Change No. 1 - Diesel Generator Battery Float Voltage

, - Change No. 2 - Isolation Times for Containment Isolation Valves - Change No. 3 - Instrumentation Surveillance Requirement Test Frequency of Tables 4.3-1 and 4.3-2 - Change No. 4 - Changes to Reflect Installation of Permanent Hydrogen Mitigation System - Change No. 5 - Addition of Second Level of Undervoltage Protection NRC approval of the changes to the technical specifications, provided in Enclosures 4 and 5, is required for unit 1 of our Sequoyah Nuclear Plant before startup from the present refueling outage.

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/@

PDR ADOCK820922O277 82f917 05000327 P

PDR An Equal Opportunity Employer

4-

. Mr. Harold R. Denton, Director September 17, 1982 In accordance with the provisions of 10 CFR Part 170.22, we have determined the proposed amendment to be Class IV for unit 1 and Class I for unit 2.

This classification is based on the fact that the amendment involves several changes of the Class III type incorporated into this amendment and involves a second essentially identical unit at the same site. The remittance of $12,700 is being wired to the Nuclear Regulatory Commission, Attention: Licensing Fee Management Branch.

Very truly yours, TENNESSEE VALLEY AUTHORITY DS W D. S. Kammer Nuclear Engineer Sworn to d subscrib d be ore me this./7 day of,.

1982 ftWJwk Notar[Public

~

My 06mmission Expires 9,![ 6 M i

Enclosures (40) cc:

U.S. Nuclear Regulatory Commission Region II Attn:

Mr. James P. O'Reilly, Regional Administrater 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303