ML20034G603
| ML20034G603 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/04/1993 |
| From: | Fenech R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-90-001, IEB-90-1, NUDOCS 9303100217 | |
| Download: ML20034G603 (4) | |
Text
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A Tennessee Volley Authonty, Post Office Box 2000, Soddy-Daisy, Tennessee 37379-2000 Robert A. Fenech Vice President. Sequoyan teclear Plant March 4, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 SEQUOYAH NUCLEAR PLANT (SQN) - NRC BULLETIN 90-01, SUPPLEMENT 1 - LOSS OF FILL-0IL IN TRANSMITTERS MANUFACTURED BY ROSEMOUNT
References:
1.
TVA letter to NRC dated December 4, 1992, "Se. oyah Nuclear Plant (SQN) - NRC Bulletin 90 Loss of Fill-Oil in Transmitters Manufactured by Rosemount -
Updated Response" 2.
IVA letter to NRC dated July 13, 1990, "Sequoyah Nuclear i
Plant (SQN) - NRC Bulletin 90 Loss of Fill-Oil in Transmitters Manufactured by Rosemount" This letter provides TVA's response to the subject bulletin supplement.
Reference 2 provided TVA's initial response to the original bulletin.
In that response, TVA listed ten transmitters that are installed in safety systems at SQN. TVA committed to replace one transmitter and create a trending program for the remaining nine. As Rosemount continued to update the master suspect list, SQN identified four additional transmitters within the original list (Reference 2) as being in the suspect category. This information was transmitted in Reference 1.
l The attached enclosure provides a detailed response to each action requested by the supplement to the bulletin.
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9303100217 930304
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U.S. Nuclear Reguintory Commission Page 2 March 4, 1993 i
Please direct questions concerning this issue to W. C. Ludwig at (615) 843-7460.
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Sincerely, i
Y Robert A. Fenech Enclosure cc (Enclosure):
Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 1
NRC Resident Inspector 1
Sequoyah Nuclear Plant 2600 Igou Ferry Road Seddy-Daisy, Tennessee 37379-3624 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-0199 i
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e Enclosure l
Sequoyah Nuclear Plant (SQN) Units 1 and 2 presently have a combined total of nine pre-1989 Model 1153, Series D Rosemount transmitters installed in safety systems (one of the original transmitters was replaced during the Unit 1 Cycle 5 refueling outage). The following is a direct response to each reporting requirement and a requested action from NRC Bulletin 90-01, Supplement 1 " Loss of Fill-Oil in Transmitters Manufactured by Rosemount."
Reportine Requirements:
" Provide within 60 days after receipt of this bulletin, a response that includes the following:
"1.
A statement whether the licensee will take the actions requested above."
Response
It is TVA's intent to take appropriate actions as delineated in the subject bulletin supplement. The following is a list of transmitters installed in the auxiliary feedwater system (AFW) and containment spray (CS) system. The AFW system and the C4 System numbers are 3 and 72 respectively.
FSAR FIGURE NO.
.IIEM UNIT ID NO.
MODEl,_E02 SERIAL N0 AND C00RDINAIE_
i 1
1-FT-3-142 1153DBSPB 405348 10.4.7-7 (G-9) 2 2-FT-3-142 1153DB5PB 405349 10.4.7-7 (G-9) 3 1-FT-3-147 1153DBSPB 405448 10.4.7-7 (H-7) 4 1-FT-3-155 1153DB5PB 405452 10.4.7-7 (F-7) 5 1-FT-3-163 1153DB5PB 405568 10.4.7-7 (D-7) 6 1-FT-72-13 1153DB4PB 405344 6.2.2-3 (D-8) 7 1-FT-72-34 1153DB4PB 405345 6.2.2-3 (H-8) 8 2-FT-72-13 1153DB4PB 405343 6.2.2-3 (D-8) 9 2-FT-72-34 1153DB4PB 405346 6.2.2-3 (H-8)
The following discussion pertains to the actions listed:
1.a.
SQN has no Rosemount Model 1153 R ries D transmitters installed in a system with a normal operating p essure greater than 1500 pounds per square inch (psi) and that are installed in reactor protection trip systems, engineered safety feature (ESF) actuation systems, or anticipated transient without scram (ATWS) systems.
Therefore, no action is required.
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1.b.
SQN has no Rosemount Model 1153, Series D transmitters installed in safety-related application with system-operating pressure greater l
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i than 1500 psi but are not installed in reactor protection trip systems, ESF actuation system, or ATWS system. Therefore, no action is required.
1.c. 'SQN has no Rosemount Model 1153, Series D transmitters installed in systems with normal operating pressure of greater than 500 psi and less than or equal to 1500 psi and that are installed in reactor.
protection trip system, ESF actuation systems, or ATWS systems.
Therefore, no action is required.
1.d.
Items 1 through 5 in the above listing are Rosemount Model 1153, Series D transmitters that are installed in the AFW system.
Item 5 l
. will be subjected to elevated static pressure during normal plant l
operation. The transmitters associated'with Items 1 through 4 will l
only sense operating pressures during pump operation as they are isolated from the feedwater system by two series check valves. The-
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AFW system is normally operated during plant start-up and shutdown j
and for unpredicted unit trips and safety injection. Response he of Reference 2 provides a description of the failure consequences for each of these transmitters.
Based upon this, TVA has elected to continue trencing calibration data each refueling outage.
If the transmitter is replaced with a newly manufactured unit, it will be deleted from the trending program.
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1.e.
Item 5 is the only transmitter installed that can be classified in this category. As described in 1.d.,
TVA will continue'to' trend
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this transmitter even though calculations indicate that it has exceeded the threshold criterion of psi per month below which i
failures hsve been shown to occur. Although not required by j
Supplement 1 to this bulletin, TVA is currer.tly continuing to i
monitor these transmitters under our previously established j
program.
1.f.
Items 6 through 9 are transmitters located in the CS system. The normal system operating pressure is less than 500 psi.
This system j
is only operated during the quarterly flow surveillance tests and i
during the operability test every refueling outage. Although not required by Supplement 1 to this bulletin, TVA is currently continuing to monitor these transmitters under our previously established program.
"2.
Evaluate the enhanced surveillance monitoring program to ensure that the program provides measurement data with an accuracy. range consistent with that needed for comparison with manufacturer drift data criteria for determining degradation caused by a loss of fill-oil."
Respranet In Reference 2, TVA established a monitoring program with the September'1985 calibration data as the baseline. Each set of recalibration data is then compared with this. baseline, and the deviation from this baseline is used to determine the drifts.
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