ML20150F737
| ML20150F737 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/08/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| TAC-R00385, TAC-R385, NUDOCS 8807190027 | |
| Download: ML20150F737 (9) | |
Text
_ - _ - _ _
TENNESSEE VALLEY AUTHORITY CH ATTANOOG A. TENNESSEE 374o1 SN 157B Lookout Place JUL 081988 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) - RELIEF REQUEST REQUIRED FOR FOUR UNIT 1 HYDROGEN ANALY2ER SAMPLING VALVES FOR SQN'S IN-SERVICE TEST (IST) PROGRAM
References:
1.
TVA letter to NRC dated January 21, 1988, "Sequoyah Nuclear Plant (SQN) - Relief Request Required for Six Solenoid-Actuated Hydrogen Analyzer Sampling Valves for SQN's In-Service Test (IST) Program" f
2.
TVA letter to NRC dated February 26, 1988, "Sequoyah Nuclear Plant (SQN) - Additional Information for SQN Unit 2 Hydrogen Analyzer Sampling Valve Relief Request" 3.
NRC letter to TVA dated March 14, 1988 "' Request For Relief From ASME Boiler and Pressure Vessel Code,Section XI, Inservice Testing Program (TAC 61835, 61836)"
In response to a recent design change to SQN's unit 1 Hydrogen Analyzer Sampling System, four new containment isolation valves (FSV-43-450, -451,
-452, and -453) are being added to SQN's IST program. These valves are colenoid-actuated, totally enclosed valves whose valve position cannot be i
visually observed as required by IWV-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 position. contains:
(1) a revised Appendix C to SQN's valve program (reference SQN's Final Safety Analysis Report, section 6.8) to reflect the addition of these unit 1 valves to the test program; and (2) the cssociated request for relief PV-15.
To support NRC review and concurrence with this relief request, a schematic diagram of the unit I hydrogen analyzer system and the proposed alternate pressure test methods have been provided in attachment A to enclosure 1.
A summary statement l
of the commitment contained in this submittal is provided in enclosure 2.
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.qfil An Equal Opportunity Employer
m TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ol SN 157B Lookout Place JUL 081988 U.S. Nuclear ~ Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Noo. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SQN) - RELIEF R3 QUEST REQUIRED FOR FOUR UNIT 1 HYDROCEN ANALYZER SAMPLINC VALVES FOR SQN'S IN-SERVICE TEST (IST) PROCRAM
References:
1.
TVA letter to NRC dated January 21, 1988, "Sequoyah Nuclear Plant (SQN) - Relief Request P.equired for Six Solenold-Actuated Hydrogen Analyzer Sampling Valves for SQN's In-Service Test (IST) Program" l
2.
TVA letter to NRC dated February 26, 1988, "Sequoyah Nuclear Plant (SQN) - Additional Information for SQN Unit 2 Hydrogen Analyzer Sampling Valve Relief Request" 3.
NRC letter to TVA dated March 14, 1988, "Request For Relief From ASME Boller and Pressure Vessel Code,Section XI Inservice Testing Progrart (TAC 61835, 61836)"
In response to a recent design change to SQN's unit 1 Hydrogen Analyzer Sampling System, four new containment isolation valves (FSV-43-450
-451,
-452, and -453) are being added to SQN's IST program. These valves are solenoid-actuated, totally enclosed valves whose valve position cannot be visually observed as required by IWV-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 position. contains:
(1) a revised Appendix C to SQN's valve program (reference SQN's Final Safety Analysis Report, section 6.8) to reflect the addition of these unit 1 val res to the test program; and (2) the associated request for relief PV-15.
To support NRC review and concurrence with this relief request, a schematic diagram of the unit I hydrogen analyzer system and the proposed alternate pressure test methods have been provided in attachment A to enclosure 1.
A summary statement of the commitment contained in this submittal is provided in enclosure 2.
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L-U.S. Nuclear Regulatory Commission J A 081988 It should be noted that the inboard containment isolation valves (FSV-43-201, -202 [ train Al and FSV-43-207, -208 (train B)) were previously incorporated into SQN's IST program (references 1 and 2) for the unit 2 hydrogen analyzer system.
Because the unit i valves are identical in design (solenoid actuated, totally enclosed), the alternate pressure test' methods that were previously submitted and approved (reference 3) will be used for the unit 1 hydrogen analyzer inboard containment isolation valves.
Because NRC approval of this relief request is required for unit I restart, TVA requests that this submittal be expediently reviewed and a Safety Evaluation Report (SER) be issued to address this relief request.
If an SER cannot be completed to support unit I restart, a written respot.se documenting NRC review and concurrence with SQN's relief request 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.
Enclosed is a check for the $150 review fee required by 10 CPR 170.12.
Please direct questions concerning this issue to D. V. Goodin at (615) 870-7734.
Very truly yours, TENNESSEE y N.EY AUTHORITY
[.
- 0 R. Gridley, Director Nuclear Licensing and Regulatory Affairs Subscribed and sworn to before me t is day of
. n&w f aua kotary Public /@
sh7 My Commission # Expires Enclosures cc:
See page 3
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U.S. Nuclear Regulatory Commission cc (Enclosures):
Mr. F. McCoy, Assistant Director for Inspection Programs TVA Projects Division
.U.S. Nuclear Regulatory Commission Region II 101 Mariotta Street, NW, Suite 2900 Atlanta, Georgia 30323 Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 l
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ENCLOSURE 1 Revised Appendix 0 to SQN In-Service Valve Test Program (SQN Final Safety Analysis Report, section 6.8) 4 f b'
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ATTACHMENT A to ENCLOSURE 1 ALTERNATE TESTING FOR UNIT 1 HYDROGEN ANALYZER SAMPLING VALVES FSV-43-450. -451. -452. -453 In lieu of a visual observation requirement, SQN requests relief to perform an siternate pressure test to verify proper operation.
The following steps provide a simplified description of SQN's alternate test methods.
This alternate test method will be incorporated into SQN's surveillance instructions for testing the subject valves during unit I restart (before mode 4).
(Refer to the Hydrogen Analyzer System Schematic)
TRAIN A VALVES 1.
FSV-43-450 a.
Attach test rig with air supply to point B.
b.
Open FSV-43-201 c.
Open Test Connection (TC) #2 d.
Pressurize test rig e.
Open FSV-43-450 and verify a pressure drop f.
Close FSV-43-450 and verify test rig pressure returns to initial pressure g.
Verify test rig pressure remains steady h.
Remove test rig and return valves to normal position 2.
FSV-43-451 a.
Attach test rig with air supply to point A b.
Open FSV-43-202 c.
Open TC #4 d.
Pressurize test rig e.
Open FSV-43-451 and verify a pressure drop f.
Close FSV-43-451 and verify test rig pressure returns to initial l
pressure l
g.
Verify test rig pressure remains steady h.
Remove test rig and return valves to normal position The train B valves will be tested in a similar fashion as the train A valves.
I
e PV-15 Systems Sampling.
Valve:
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 FSV-43-200A, FSV-43-201, FSV-43-202, FSV-43-207 FSV-43-208, FSV-43-210A, FSV-43-450, FSV-43-451 FSV-43-452, FSV-43-453 Class:
2 Category:
A - Active Function:
To permit reactor coolant system and containment atmosphere sampling in a postaccident condition.
Impractical Requirement:
Observe valve 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.
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3 ENCLOSURE 2 Commitment 1.
An alternate pressure test method will be incorporated into SQN's surveillance instructions for testing FSV-43-450
-451. -452, and -453 during unit i restart (before mode 4).
NOTE: TVA, in a' previous commitment for the unit 2 hydrogen analyzer sampling valves, stated that surveillance instruction (SI) 166.4 would be revised to incorporate and test the new unit 2 valves.
Because of recent procedural enhancements, all of the unit 2 and unit I hydrogen analyzer system valves will be tested under SI-166 rather than SI-166.4.
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