ML20214H085

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Forwards Electrical,Instrumentation & Control Sys Branch SER Accepting Util 860523 Tech Spec Changes in Response to Generic Ltrs 83-28 & 85-09,except for Listed Items.Salp Input Also Encl
ML20214H085
Person / Time
Site: Sequoyah, Vogtle, 05000000
Issue date: 07/07/1986
From: Rossi C
Office of Nuclear Reactor Regulation
To: Stahle C
Office of Nuclear Reactor Regulation
Shared Package
ML20213E629 List:
References
GL-83-28, GL-85-09, GL-85-9, TAC-55377, TAC-55378, NUDOCS 8607100296
Download: ML20214H085 (2)


Text

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JUL 7*

Cd Docket Nos.: 50-327/328 MEMORANDUM FOR:

C. Stahle, Project Manager, Project Directorate #4 Division of PWR Licensing-A FROM:

C. E. Rossi, Assistant Director Division of PWR Libensing-A

SUBJECT:

EICSB(PWR-A)INPUTFORSEQUOhAHNUCLEARPLANT GENERIC LETTER 83-28, ITEM 4.3.1 T.S.(MPA 8-90)

TECHNICAL SPECIFICATION CHANGES Plant Name:

Sequoyah Nuclear Plant, Units 1 and 2 Utility:

Tennessee Valley Authority Docket Nos.:

50-327/328 TAC Nos.:

55377/55378 Licensing Status:

OR Resp. Directorate: PD #4/DPA Project Manager:

C. Stahle Review Branch:

EICSB/DPA Review Status Incomplete By letter dated May 23, 1986, TVA submitted proposed Technical Specification changes for the Sequoyah Nuclear Station, Units 1 and 2 in response to Generic Letters 83-28 and 85-09.

Other proposed Technical Specification changes are also included. The enclosed Safety Evaluation Report pertains only to the Generic Letter 83-28 and 85-09 items. The other changes are to be reviewed under separate TAC numbers.

EICSB finds the proposed Technical Specification changes pertaining to Generic Letters 83-28 and 85-09 acceptable except for the following:

1.

For the Reactor Trip System Instrumentation, Table 3.3-1, Modes 3*,4*,5*

should be separated from Modes 1 and 2 for Functional Units 20 (Reactor Trip Breakers) and 21 (Automatic Trip Logic), and an action statement added, similar to Action 13 of Generic Letter 85-09, for Modes 3*,4* and 5* (asterisk means with the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal, and fuel in the reactor vessel).

2.

Table Notation (9) of Table 4.3-1 should be expanded to test the operability of the Bypass Breaker trip circuits.

Contact:

A. Toalston, EICSB/DPA X27243 W

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C. Stable 3.

A Functional Unit should be added to Table 4.3-1 for Channel Functional Tests of the Reactor Trip Bypass Breaker (including Table Notations) similar _to that for Functional Unit 23 of Generic Letter 85-09.

is the SALP input for this review.

Original aigdeib/,

Charles E. Rossi, Assistant Director Division of PWR Licensing-A

Enclosure:

As stated cc:

T. Novak B. J. Youngblood Distribution:

Docket File Nos.: 50-327/328 EICSB Rdg.

A. Toalston (PF)(2)

D. Lasher J. E. Knight F. Rosa C. E. Rossi V. Benaroya Sequoyah S/F 4

W EICSB/DPA EICSB/DPA SL/EICSB/DPA A g gon:ct DLgr hJEKnight BC/EICSB,/

F0B/DPA FRosa /f ;

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