ML20237J794
| ML20237J794 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/11/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8708180346 | |
| Download: ML20237J794 (4) | |
Text
- _ _ _.
TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 37401 SN 157B Lookout Place AdjB 111987 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SQN) NRC INSPECTION REPORT NOS. 50-327/87-36 AND 50-328/87 RESPONSE TO NOTICE OF VIOLATION 50-327, -318/87-36-01 Enclosed is our response to Gary G. Zech's July 16, 1987 lotter to S. A. White that transmitted the subject Notico of Violation.
If you have any questions, please telephone M. R. Harding at 615/870-6422.
To the best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours, TENNESSEE VALLEY AUTHORITY R. Gridley, D rector Nuclear Safet and Licensing Enclosure cc:
See page 2 l
l l
O 8708180346 G70011 PDR ADOOK 05000327 h g%
PDR S
o Ik i
An Equal Opportunity Employer
__- _____-______ A
'. '!G.;
.. U.S. Nuclear Regulatory Commission
[-
cc (Enclosure):
J Mr. G. G. Zech,' Assistant Director
'for' Inspection Programs lj Office of Special Projects.
U.S. Nuclear Regulatory Commission
.101 Marietta Street, NW, Suite 2900
' Atlanta, Georgia. 30323 Mr,. J. A. Zwolinski, Assistant Director
- for Projects Division of TVA Projects-Office of Special Projects 4
U.S. Nuclear Regulatory Commission 4350 East' West Highway 1
EW 322 j
Bethesda, Maryland 20814 Sequoyah Resident. Inspector Sequoyah Nuclear Plant l
.2600 Igou Ferry Road 1
Soddy Daisy, Tennessee 37379 1
'i
ENCLOSURE' NOTICE OF. VIOLATION (NOV) 50-327,.-328/87-36-01 Violation 50-327. -328/87-36-01 Technical Specification 3.3.3.6 states that two independent chlorine detection systems. (CDS), with their alarm / trip setpoints adjusted to actuate 'at a
-chlorine concentration of less than-or equal to 5 ppm, shall be OPERABLE.
i Surveillance Requirement 4.3.3.6 states that each chlorine. detection system shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at l
1 east once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
Contrary to the above, neither the CHANNEL CALIBRATION nor the CHANNEL 1
FUNCTIONAL TEST have been adequately performed for the period of f
January 1, 1982 (since the preoperational test phase) to the present, in that J
the isolation of the control room (the CDS. trip function) is not functionally
]
tested using the chlorine detector signal as an initiation signal.
(Note:
.j one special test was performed at.the request of the NRC in 1987.) Both
]
channels of the CDS were considered to be inoperable at the time of the
)
inspection, and to have been inoperable for the period that these tests were
)
not adequately performed.
I This is a Severity Level IV violation (Supplement I),
1.
Admission or Denial of the Alleged Violation TVA concurs the violation occurred as stated.
2.
Reason for the Violation t
This violation resulted from an improper application of the technical
)
specification requirements associated with the chlorine Detection System (CDS) and the Control Room Emergency Ventilation System (CREVS).
Technical specification 4.7.7.e.2 did not specifically require the actuation of the CREVS from a CDS signal.
3.
Corrective Steps Which Have Been Taken and Results Achieved Surveillance Instruction 168, " Calibration of Control Room Air Intake Chlorine Detection System," which fulfills the 18-month CHANNEL CALIBRATION requirement, was revised and. approved by Plant Operations
' Review Committee on June 6, 1987. This revision includes a verification of the CREVS isolation from a CDS initiation. This procedure was
)
l successfully performed on July 7, 1987.
Testing of the CREVS function on CDS initiation in this manner is consistent with the testing requirements for the safety injection and high radiation actuation test requirements specified in technical specification 4.7.7.e.2.
j
)
- w, Additionally, TVA has requested a revision to the SQN-technical specifications to delete the requirements for the CDS.-
This request was submitted.on January 21, 1987, and is based on the fact that SQN no
~
longer keeps significant~ quantities of chlorine onsite and the absence of railroad or barge traffic of chlorine within five miles of SQN.
It is
]
TVA's understanding that NRC has found the proposed technical specification revision technically acceptable and is in the' final' l
administrative process of issuing the technical specification anandments.
4.
Corrective Steps Which Will Be Taken to Avoid Further Violations Same as above.
l l
S.
Date When Full Compliance Will Be Achieved l
Full compliance relative to this violation has been achieved.'
1 I
I
]
-