ML20148C233
| ML20148C233 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/21/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8801250145 | |
| Download: ML20148C233 (7) | |
Text
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k TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ol SN 157B Lookout Place JAN 211988 U.S. Nuclear Regulatory Coaulssion ATTN: Document Control Deuk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SQN) - RELIEF REQUEST REQUIRED FOR SIX SOLENOID-ACTUATED HYDROCEN ANALYZER SAMPLING VALVES FOR SQN'S IN-SERVICE TEST (IST)
PROGRAM In response to a recent desir,n change to SQN's uni
':ontainment isolation valves (FCV-43-201. -202. -207, and -208) with solenold-actuated valves having a totally enclosed valve design. These valves are presently tested under SQN's IST Program; however, because of the change in valve design, valvo positica cannot be visually observed as required by IW"-3300 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI.
In lieu of the visual observation requirement, SQN requests relief to perform an alternate pressure test to verify proper valve operations In addition, four other solenoid-actuated hydrogen analyzer sampling valves i
(FSV-43-200A, -200I, -210A, and -210I) will be added to SQN's IST Program.
These valves are located on the existing hydroger; analyzer calibration and reagent air lines and will be designated as outboard containment isolation valves. The 200A and 210A valves (located on the reagent lines) are classified as active valves and are required to be tested under the Section XI code. The 200I and 210I valves (located on the calibration lines) are l
classified as passive valves and are not required to be tested under Section i
XI.
Because the 2004 and 210A solenoid valves are active valves and similar l
in design to the inboard containment isolation valves, relief is requested to l
perform an alternate pressure test similar to the inboard containment isolation valves.
l 1
The enclosure contains:
(1) a envised Appendix C to SQN's valve program (reference SQN's Final Safety Analysis Report, section 6.8) to reflect the additions and changes to the ter t program; and (2) the associated additions to l
relief request PV-15 which is al existing NRC approved relief request.
I Because this program change co.itains a request for relief from the ASME Boiler and Pressure Vessel Code, Sect.lon II, this item constitutes a startup
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8801250145 880121 Ok PDR ADOCK 05000327 b
g PDR I\\
An Equal Opportunity Employer
, U.S. Nuclear Regulatory Commission
{}ggg requirement. TVA requests that this submittal be expediently reviewed and a Safety Evaluation Report (SER) be issued to address this change.
If an SER cannot be completed to support plant restart, a written response documenting NRC review and concurrence with SQN's valvo program would be beneficial. Upon receipt of either an SER or NRC concurrence, SQN will change its valve program to be consistent with NRC's approved position.
If you have any questions concerning this issue, please telephone M. R. Harding at (615) 870-6422.
Very truly yours, TENNESSEE VALLEY AUTHORITY
/
R.
ridley, Director Nuclear Licensing and Regulatory Affairs Enclosures cc (Enclosures):
Mr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division Office of Special Projects U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
[
Mr. G. G. Zech, Assistant Director l
for Projects Mail Stop 7E23 TVA Projects Division Office of Special Projects U.S. Nealear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Sequoyah Resident Inspector l
Sequoyah Nuclear Plant l
7600 Isou Ferry Road l
Soday Daisy. Tennessee 37379 l
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ENCLOSURE Revised Appendix C to Sequoyah Nuclear Plant's (SQN)
In-Service Valvo Test Program (SQN Final Safety Analysis Report, section 6.8) l t
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Sequoyah Nuclear Plant inservice Valve Testing Program
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6.8C-19 Revised by Amendment 4
SNP-3 PV_15 System:
Pcct2ce! dent Sampling Valvo:
FSV-43-250, FSV-43-251 FSV-43-287, FSV-43-288 FSV-43-307, FSV-43-309 FSV-43-310 FSV-43-317, FSV-43-318. FSV-43-319, FSV-43-325 FSV-43-341 f5 /- 43 2c s rs. 4 is v-4 3.2cc h, r,s v -+3. a z, rs y. 4 3. u f, p S v. v 3. zo y 2
3 2eA class:
and dvd l""""'g of,,s[fr.fG Category:
A - Active Function:
To permit reactor coolant system / sampling in a postaccident condition.
Impractical 3
Requirement:
Observe valvo movement every two years to verify remote valve indicators accurately reflect valve operation.
Basis for Relief:
These solenoid actuated valves are totally enclosed, and valve position cannot be determined visually.
Alternate Testing:
Pressure indicators will be used to independently verify valve operation.
Frequency for Alt Testing:
Every 2 years.
Added by Amendment 3 6.8C-69A
ENCLOSURE 2 LIST OF COMMITMENT j
/
1.
All 6 solenoid-actuated hydrogen analyzer sampling valves will be tested in accordance with the provisions presciibed in enclosure 1 before entering mode 2 for both units.
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