ML20215L436
| ML20215L436 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Sequoyah, 05000000 |
| Issue date: | 06/19/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-87-06, GL-87-6, TAC-R00181, TAC-R00182, TAC-R00183, TAC-R00379, TAC-R00380, TAC-R181, TAC-R182, TAC-R183, TAC-R379, TAC-R380, NUDOCS 8706260050 | |
| Download: ML20215L436 (5) | |
Text
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TENNESSEE VALLEY AUTHORITY CH ATTANOOG A, TENNESSEE 37401 5N 157B Lookout Place
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JUN 191987
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U.S. Nuclear Regulatory Commission.
Attn: Document Control Desk j
Hashington, D.C.
20555 q
Gentlemen:
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In the Matter of
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Docket Nos. 50-259 Tennessee Valley Authority
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50-260 50-296 50-327 50-328 i
PERIODIC VERIFICATION OF LEAK TIGHT INTEGRITY OF PRESSURE ISOLATION VALVES (GENERIC LETTER 87-06)
Enclosed is TVA's response to the subject generic letter for Browns Ferry (BFN) 2.nd Sequoyah (SQN) Nuclear Plants. lists the reactor coolant pressure boundary pressure isolation valves at BFN and describes the program for. ensuring the leak-tight integrity of these valves.
provides the appropriate technical specification references which address these valves for SQN.
If you have any questions concerning this matter, please telephone R. A. Westbrook at (615) 751-8083.
I Very truly yours, TENNESSEE VALLEY AUTHORITY R. L. Gridley, Director Nuclear Safety and Licensing Enclosures cc:
See page 2
[0 A$ocK $
Q9 An Equal Opportunity Employer f
, U.S. Nuclear Regulatory Commission JUN 191987 cc'(Enclosure):
Mr G. G. Zech Assistant Director.
Regional Inspections-
' Division of TVA Projects Office of Special Projects U.S. Nuclear.. Regulatory Commission j
l Region II' l
l-101-Marietta Street ~,-NW,' Suite 2900
. Atlanta, Georgia 30323 Mr. J. A. Zwolinski, Assistant Director i
for Projects j
Division of:TVA-Projects 1
Office of Special: Projects U.S. Nuclear Regulatory Commission' i]
4350 East West Highway EHW 322
,Bethesda, Maryland 20'814~
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Browns Ferry Resident Inspector j
. Browns Ferry Nuclear Plant Route 2,:P.O.. Box 311 Athens,' Alabama.35611
.Sequoyah Resident Inspector-Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 1
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f ENCLOSURE 1 j
s Browns Ferry Nuclear Plant (BFN)
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Response to Generic Letter 87-06
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Leak-Tight Integrity of Pressure j
Isolation Valves j
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For plants licensed prior to 1979, provide the following information:
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. Question j
You are requested to submit a list of'all pressure isolation valves in your plant.
i TVA, Response The fo11owing is a list of all reactor coolant system pressure isolation valves for BFN:
74-47 Shutdown cooling supply outboard isolation valve 74 Shutdown cooling supply inboard isoihtiori valve j
74-53 Shutdown cooling injection isolation valve (Loop I) l 74-54 Shutdown cooling injection tw able check valve (Loop I) 74-67 Shutdown cooling injection isolation valve (Loop II) 1 74-68 Shutdowr, cooling injection testable check valve (Loop II) l
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74-661 Thermal relief check valves around shutdown cooling supply valves
-l 662 NOTE:
These valves are tested as a single barrier.
I 75-25 Core spray injection isolation valve (Loop I) j q
75-26 Core spray testable check valve (Loop I) j 75-53 Core spray injection isolation valve (Loop II) j 75-54 Core spray testable check valve (Loop II) f c
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! Question-For each valve, describ'e'the periodic tests or other measures performed to
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ensure the integrity of the. valve as an independent barrier at the reactor j
coolant' pressure boundary.
j TVA Response Th'e subject valves listed in this enclosure are in.the BFN American Society of Mechanical Engineers'(ASME),Section XI Pump and Valve Testing Program as implemented by plant Surveillance Instructions (SI).
Each valve is periodically leak-tested with water at a reduced pressure of 56 psig and adju:ted to " function maximum differential" in accordance with ASME,Section XI IWV-3423(e).
Other measures to ensure valve integrity consist of monitoring the respective
' loop pressure on a daily basis.
Any excess leakage would be detected by a pressure increase.
l Qu_estion i
For each valve, describe the acceptance criteria for leakage.
TVA Response Each valve's acceptance criteria is 50 percent of the lower pressure system's relief valve capacity. The relief valves are one-inch nominal diameter.
Question For each valve, describe the operational limits.
TVA Response Operational limits are the' system operability limits as listed in technical specifications. -If a loop of residual heat removal or core nray was determined to be leaking to the extent that it is determineu inoperable, then the appropriate technical ~ specification required actions would be implemented.
Question For each valve, describe the frequency of test performance.
TVA Response Each valve is tested once per refueling, not to exceed two years between tests in accordance with SI 4.7 A.2.g-3.
Data is corrected to the functional differential pressure per SI-3.2.5.
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' ENCLOSURE'2L
~Sequoyah Nuclear Plant.(SQN)
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' Response to Generic Letter 87-06 Leak-Tight Integrity of. Pressure.
Isolation ~ valves
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-l For plants licensed 'af,ter'1979, provide.the following information:
1 M
. Question
- If current plant technical _ specifications require leak-rate testing of all of i
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the pressure isolation valves in the plant, your reply to.that effect will.be:
1 sufficient.
'TVA Response.
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W The Safety Evaluation Report (SER) on SQN Inservice Test Program for'pumpsiand i
valves' includes a'11st of all valves which perform a pressure boundary'.
isolation function.
This list.contains all valves necessary to maintain redundant isolation..andl system integrity.-
1 The SQN Technical Specifications::(TS) include all valves. listed in the SER
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with'the' exception of two' upper-head injection' flow control. valves (FCV-87 l Land FCV-87-8); 'A proposed TS change 87-35 has'been submitted to include these l
valves. Surveillance Instruction (SI)166-11, Upper Head Injection Check Valve. Integrity," already includes ~ requirements to test these valves.-
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- Thus, all valves'necessary to ensure that the 'ntegrity of the reactor coolant isystem' pressure. boundary is maintained are subject to appropriate' surveillance testing by Surveillance Requirement 4.4.~6.2.2.
'SI-166.10,:" Accumulator /
Injection Primary and. Secondary Integrity," and SI-166.18, "RHR Return Valve
' Leak Rate Test,".also support.this surveillance' requirement.
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