ML20153A961
| ML20153A961 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Sequoyah, 05000000 |
| Issue date: | 07/06/1988 |
| From: | Black S NRC OFFICE OF SPECIAL PROJECTS |
| To: | White S TENNESSEE VALLEY AUTHORITY |
| References | |
| REF-GTECI-105, REF-GTECI-NI, TASK-105, TASK-OR 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 8807120669 | |
| Download: ML20153A961 (4) | |
Text
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b,,,,, *#g July 6, 1988 Docket No. 50-259/260/296/50-327/328 Mr. S. A. White Senior Vice President, Nuclear Group Tennessee Valley Authority 6N 38A Lookout Street 1101 Market Street Chattanooga, Tennessee 37402-2801
Dear Mr. White:
SUBJECT:
GENERIC LETTER 87-06, PERIODIC VERIFICATION OF LEAX TIGHT INTERITY OF PIVs (TAC N0s. R00379, R00380, R00181, R00182, R00183)
In Generic Letter (GL) 87-06, Periodic Verification of Leak Tight Integrity uf Pressure Isolation Valves (PIVs), dated March 13, 1987, the NRC requested information from operating reacter licensees concerning the methods used for testing PIVs in order to assure the integrity of the reactor coolant pressure boundary during plant operation. The Tennessee Valley Authority (TVA) responded for Browns Ferry Units 1, 2 and 3 and Sequoyah Units 1 and 2 in its lett'er dated June 19, 1987. The GL did not require any licensee action other than the submission of the requested information.
PIVs are defined for each interface as any two valves in series within the re. actor coolant pressure boundary which separates the high pressure reactor coolant system from an attached low pressure system. There are essentially two types of PIVs.
The first type are PIVs whose sizes are small or that are not connected to any accident mitigation systems. The second type are PIVs whose sizes are of some significance and are connected to an accident mitigation system.
One purpose of inservice testing (IST) is to ensure the leak tight integrity of certain PIVs whose failure may impair the plant's ability to shutdown the reactor or to mitigate an accident. The general requirements for leak testing of PIVs are established by 10 CFR Part 50, Appendix A, General Design Criteria (GDC) 14, 30 mid 32, which establish that PIVs are ASME Section XI Category A valves (seat leakage important).
For Category A valves, 10 CFR 50.55a(g) requires that seat leakage testing be conducted on such valves to meet the requirements of ASME Code,Section XI.
However, the GDC and the regulations have been interpreted differently by industry ~and by the NRC.
Consequently, PIV leak rate testing varies widely from licensee to licensee depending upon when the plant was licensed.
The Office of Research (RES), NRC, is presently working on two generic issues that involve PlVs, namely: Generic Issue II.E.6.1, In-situ Testing of Valves, and Generic-Issue 105, Intersystem LOCA for LWRs. At the time of issuance, GL 87-06 was considered to oe part of the resolution of these generic issues.
RES intends to develop and seek approval for a generic letter that will I U 8807120669 880706 DR ADOCK 05000259 PDC
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state the staff's position on PIV testing and implementation; specifically the planned generic letter will address and may require written responses on:
- scope of PIV testings,
- leak rate criteria, and
- expanded periodic surveillance testing requirements to be covered in the IST program and plant Technical Specifications (TS).
In its responses to GL 87-06, for Browns Ferry, TVA ttated that the 12 PIV's are tested once per refueling outage not to exceed two years between tests.
The PIVs are in the plant ASME Section XI Pump and Valve Testing program.
The. loop pressure for the PIV's is also monitored on a daily basis.
For Sequoyah, TVA stated that the Sequoyah Units 1 and 2 TS require ASME Section XI IST for all the PIVs with the exception of two valves. These two are included in TVA's proposed TS change 87-35 which has been submitted to NRC and is under review.
It further stated that the surveillance instruction for these two PIVs includes the requirement to test these valves. Thus, TVA has concluded that the PIVs necessary to ensure the integrity of the Sequoyah reactor coolant pressure boundary are subject to the appropriate surveillance testing.
Your response to GL 87-06 for Browns Ferry and Sequoyah Nuclear Plants is acceptable and this letter closes out the staff's action on GL 87-06.
If you have any questions on this letter, please contact J. Donohew, Sequoyah P,rojectManagerat(301)492-0704, or G. Gears, Browns Ferry Project Manager at(301)492-0767.
i Sincerely, l-Original Signed by i
l Suzanne Black, Assistant Director l
for Projects TVA Project Division Office of Special prd ects Distribution
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'e Units 1, 'J.*y Nuclear Plant Browns Ferr Mr. S.-A. White and 3 Tennessee Valley Authority cc:
General Counsel Regional Administrator, Region 11 Tennessee Valley Authority U.S. Nuclear Regulatory Commission 400 West Summit Hill Drive 101 Marietta Street, N.W.
Ell B33 Atlanta, Georgia 30323 Knoxville, Tennessee 37902 Resident inspector / Browns Ferry NP Mr. R. L. - Gridley U.3. Nuclear Regulatory Commission Tennessee Valley Authority Route 12, Box 637 SN 1578 Lookout Place Athers, Alabama 35611 Chattancoga, Tennessee 37402-2801 Mr. Richard King Mr. H. P. P.omrehn c/o U.S. GA0 Tennessee Valley Authority 710 Locust Streat Browns Fewry Nuclear Plant Suite 137 P.'. Box E000 '
Knoxville, Tenriessee 37901 0
Decatur, Alabama 35602 Dr. Henry Myers. Science Advisor Mr. M. J. '.'ay Committee on Interior Tennessee Valley Authority and Insular Affairs Browns Ferry Nuclear Plant U.S. House of Representatives P.O. Box 2000 Washington, D.C.
20515 Decatur, Alabama 35602 Mr. D. L. Willfahs Tennessee Valley Authority 400 West Summit Hill Drive W10 B85 Knoxville, Tennessee 37902 Chairman, Lir.estone County Commission P.O. Box 138 Athens, Alabama 35611 C?3ude Earl Fox, M.D.
State Health Officer State Departnent of Public Health State Office Building Montgomery, Alabama 36130
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t Mr. S. A. White Tennessee Valley Authority Sequoyah Nuclear Plant cc:
General Counsel Regional Administrator, Region II Tennessee Valley Authority U.S. Muclear Regulatory Commission 400 West Summit Hill' Drive 101 Marietta Street, N.W.
Eli B33 Atlanta, Georgia 30323 Knoxville, Tennessee 37902 Resident Inspector /Sequoyah NP Mr. R. L. Gridley c/o U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou Ferry Road SN 157B Lookout Place Soddy Daisy, Tennessee 37379 Chattanooga, Tennessee 37402-2801 Mr. Richard King Mr. H. L. Abercrombie c/o U.S. GA0 Tennessee Valley Authority 1111 horth Shore Drive Sequoyah Nuclear Plant Suite 225, Box 194 P.O. Box 2000 Knoxville, Tennessee 37919 Soddy Daisy, Tennessee 37379 Mr. M. R. Harding Mr. Michael H. Mobley, Director Tennessee Valley Authority Division of Radiological Health Sequoyah Nuclear Plant
.T.E.R.R.A. Building, 6th Floor
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P.O. Box 2000 150 9th Avenue North Soddy Daisy, Tennessee 37379 Nashville, Tennessee 37219-5404 Mr. D. L. Williams Dr. Henry Myers, Science Advisor Committee on Interior Tennessee Valley Authority
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and Insular Affairs 400 West Summit Hill Drive W10 B85 U.S. House of Representatives Knoxville, Tennessee 37902 Washington, D.C.
20515 County Judge Hamilton County Courthouse Chattanooga, Tennessee 37402
. _., ~ _,