ML20064G652
| ML20064G652 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/07/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.A.1.3, TASK-2.E.1.1, TASK-2.E.1.2, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.K.2.08, TASK-2.K.2.13, TASK-2.K.3.03, TASK-2.K.3.12, TASK-TM GL-82-16, NUDOCS 8301110585 | |
| Download: ML20064G652 (3) | |
Text
_._,
d TENNESSEE VALLEY AUTHORITY
.CH ATT,ANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II January 7, 1983 Director of Nuclear Reactor Regulation Attention:
Ms. E. Adensam, Chier Licensing Branch No. 4 Diviaion of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Ms. Adensam:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 As requested by D. G. Eisenhut's September 20, 1982 letter to "All Pressurized Power Reactor Licensees" regarding NUREG-0737 Technical Specifications (Generic Letter #82-16), we have completed the review of our Sequoyah Nuclear Plant (SQN) Technical Specifications (T/S) to determine consistency with NRC's guidance provided in enclosure 1 to that letter. The enclosure provides our response to items 1 through 13 except for item 10 which was not provided in enclosure 1 to D. G. Eisenhut's letter.
If you have any questions concerning this matter, please get in touch with J. E. Wills at FTS 858-2683 Very truly yours, TENNESSEE VALLEY AUTHORITY N) l L. M. Mills, anager -
Nuclear Licensing SwornAo nd subsce bed before me 1983 this /
day of..
1 Notary Public My Commission Expires
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[oV6 Enclosure oc:
U.S. Nuclear Regulatory Commission (Enclosure)
Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 8301110585 830107 PDR ADOCK 05000327 An Equal Opportunity Employer
ENCLOSURE Response to D. G. Eisenhut's September 20, 1982 Letter NUREG-0737 Technical Specifications (Generic Letter #82-16)
Sequoyah Nuclear Plant Item (1) - STA Training (I.A.1.1.3)
This item is already addressed in SQN T/S 6.2.4.
Item (2) - Limit Overtime (I.A.1.3)
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The SQN unit 1 T/S previously specified overtime limits..';By letter 'from M. R. Wisenburg (TVA) to H. R. Denton dated December 15, 1981, TVA requested removal of the overtime limits to make the SQN unit 1 T/S consistent with the SQN unit 2 T/S issued by NRC on September 15, 1981. NRC approval of removal of overtime limits for SQN unit 1 was received in a letter from E. G. Adensam to H. G. Parris dated March 25, 1982. We do not plan to submit a T/S to reinsert the overtime limits.
Item 3 - Short-Term Auxiliary Feedwater System Evaluation (II.E.1.1)
This item is already addressed in SQN T/S 3 7.1.2.
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Item 4 - Safety Grade AFW System Initiation and Flow Indication (II.E.1.2)
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This item is already addressed by SQN T/S 3 3.2, functional unit 6 of table 333 Item 5 - Dedicated Hydrogen Penetrations (II.E.4.1)-
This item is not applicable to SQN.
. Item 6 - Containment Pressure Setpoint (II.E.4.2.5)
TVA's revised response to containment pressure setpoint was submitted to NRC by letter from L. M. Mills to A. Schwencer dated February 23, 1981. NRC has accepted the current containment setpoint.
i Item 7 - Containment Purge Valve (II.E.4.2.6)
This item is already addressed by SQN T/S 3.6.19 and T/s 4.6.3.4.
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- c Item 8 - Radiation Signal on Purge Valves (II.E.4.2.7)
This item has already been addressed by SQN T/S 3 3 2, runctional unit 3.c or table 3.3.3 Item 9 - Upgrade B&W AFW System (II.K.2.8)
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This item is not applicable to SQN.
Item 10 - Not provided in enclosure 1 to D. G. Eisenhut's letter.
Item 11 B&W Thermal-Mechanical Report (II.K.2.13)
This item is not applicable to SQN.
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Item 12 - Reporting SV and RV Failures / Challenges (II.K.3 3) t This item has already been addressed by SQN T/S 6.9.1.10.
i Item 13 - An'ticipatory Trip on Turbine Trip (II.K.3 12) i This item has already been' addressed by SQN T/S 2.2.1, items 17 and 25 or table 2.2-1.
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