ML20099H945
| ML20099H945 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/13/1985 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8503190544 | |
| Download: ML20099H945 (2) | |
Text
,
w' TENNECZEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 1630 Chestnut Street Tower II March 13, 1985 Director of Nuclear Reactor Regulation Attention:
Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Ms. Adensas:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 The TVA response to NRC Generio Letter 83-28, " Required Actions Based on Generio Implications of Salem ATWS Events," for the 3equoyah Nuclear Plant was provided to NRC by L. M. Mills' Novembsr 7, 1983 letter to you.
TVA's response to NRC's request for additional information, that was specified in the NRC Safety Evaluation Report (SER), was provided to you on August 27, 1984 by letter from L. M. Mills. As a result of telephone discussions with the NRC in December 1984 and as requested by NRC, enclosed are revised responses to questions 4, 9, and 10 previously provided to NRC by the August 27, 1984 letter.
If you have any questions concerning this matter, please get in touch with Jerry Wills at FTS 858-2683 Very truly yours, TENNESSEE A LEY UTHORITY I
R. H. Shell Nuclear Engineer Sworn t subscr before me thi,
day of etf/ 1985 ltdY MW r
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Enclosure 00 U.S. Nuclear Regulatory Commission (Enclosure)
Region II Attn:
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 0
8503190544 850313 l l' (
POR ADOCK 05000327 p
PDR An Equal Opportunity Employer
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ENCLOSURE j
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NRC SAFETY EVALUATION REPORT ON THE WOG GENERIC DESIGN FOR AUTOMATIC,
ACTUATION OF THE SHUNT TRIP ATTACHMENT OF THE REACTOR TRIP BREAKER Question 4 State whether the test procedure / sequence used to independently verify l
operability of the undervoltage and shunt trip devices in response to j
an automatic reactor trip signal is identical to the test procedure
[
proposed by the Westinghouse Owners Group (WOG).
Identify any differences
[
between the WOG test procedure and the test procedure to be used and i
provide the rational / justification for these differences.
1 l
The intent of the test procedure proposed by the WOG to NRC by letter (No. OG101) dated June 14, 1983 to independently confirm l
the operability of the undervoltage trip and shunt trip devices
[.
in response to an automatic reactor trip signal will be incorporated into Sequoyah's automatic reactor trip functional test procedure.
i Sequoyah's functional test procedure will be revised when the shunt trip modification is implemented.
Question 9 Verify that the operability of the control room manual reactor trip switch contacts and wiring will be adequately tested prior to startup after each refueling outage. Verify that the test procedure used will not involve installing jumpers, lif ting leads, or pulling fuses and l
identify any deviations from the WOG procedure.
Permanently installed j
. test connections (i.e., to allow connection of a voltmeter) are acceptable.
l The control room manual reactor trip switch will be functionally tested before startup after each refueling outage. Sequoyah has not reviewed the drawings for the final design of the shunt trip attachment modification; however, our preliminary information indicates that the use of jumpers, lif ting leads, pulling fuses, or any significant deviations from the WOG procedure to test the l
shunt trip attachment will not be required.
-Question 10 l
Verify that each bypass breaker will be tested to demonstrate its operability prior to placing it into service for reactor trip breaker l
testing.
I l.
Each bypass breaker is presently tested to demonstrate its operability prior to placing it into service for reactor trip breaker testing by locally tripping the breaker open. TVA will continue to verify breaker operability af ter installation of the shunt trip attachment modification.
I