ML18026A900
| ML18026A900 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/10/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 8403060076 | |
| Download: ML18026A900 (6) | |
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Docket Nos. 50-259/260/296 February 10, 1984 Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401
Dear Mr. Parris:
SUBJECT:
INSERVICE TESTING OF PUMPS AND VALVES Re:
Browns Ferry Nuclear Plant, Units 1, 2 and 3
Reference is made to your submittal of August 31, 1982 as supplemented by your letter of April 6, 1983.
We have reviewed this information and con-clude that we need the information identified in the enclosure to this letter in order to complete our review.
We would appreciate a'esponse within 45 days of receipt of this letter.,
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.
Sincerely,
Enclosure:
As stated cc w/enclosure:
See next page DISTRIBUTION NRC PDR Local PDR ORB¹2 Reading DEisenhut OELD ELJordan JMTaylor Orginal Signed by /
Domenic, B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing RClark SNorris ACRS (10)
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Mr. Hugh G. Parris Tennessee Valley Authority Browns. Ferry Nuclear plant, Units 1, 2 and 3
CC:
H. S. Sanger, Jr., Esquire General Counsel Tennessee Valley -Authority 400 Commerce Avenue E llB 330 Knoxville, Tennessee 37902 Mr. Ron Rogers Tennessee Valley Authority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401 Mr. Charles R. Christopher
- Chairman, Limestone County Commission post Office Box 188
- Athens, Alabama 35611 Ira L. Myers, M. D.
State Health Officer State Department of public Health State Office Building Montgomery, Alabama 36130 Mr. H.
N. Culver 249A HBD 400 Commerce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902 James
- p. O'Reilly Regional Administrator Region II Office U. S. Nuclear Regulatory Commission
-101 Marietta Street, Suite 3100
- Atlanta, Georgi a 30303 U. S. Environmental protection Agency Region IV Office Regional Radiation Representative 345 Courtland Street, N.
W.
Atlanta, Georgia 30308 Resident Inspector U. S. Nuclear Regulatory Commission Route 2, Box 311
- Athens, Alabama 35611 Mr. Donald L. Williams, Jr.
Tennessee Valley Authority 400 West Sum'mit Hi 1? Drive, W10885 Knoxville, Tennessee 37902 George Jones Tennessee Valley Authority Post Office Box 2000
- Decatur, Alabama 35602 Mr. Oliver Havens U. S. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411
REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE BROWNS FERRY UNITS 1,,
ND 3 PR GR R
NSER V
F PUMPS ND V LV S 1.
The pump portion of the IST program was reviewed to verify that all pumps that are important to safety are included in the program and are subjected to the testing required by the ASME Code.
In the staff's judgement there
are additional systems wherein the associated pumps should be in the program.
These systems are:
Plant Service Water PSC Head Tank Fuel Oil Transfer Please justify the omission of the pumps in these systems or revise the IST program to include them.
2.
Likewise, in the staff's judgement the following valves should be in the IST program:
Combustible Gas Control System valves Primary Containment Atmosphere valves Fuel Oil Transfer System valves Transverse In-Core Probe valves Valves in the portions of the Instrument and Control Air System that perform a function important to safety Valves in ventilating systems that perform a function important to safety Sampling System valves Torus Drain Valves Drywe'll Pressure Suppression Chamber (PSC) and PSC - Reactor Building vacuum breakers SRV discharge line vacuum breakers (Valves10-506, 507, 519, etc.)
Primary Containment H, and 0, Analyzer valves EECW valves for the Unit 1 and 2 Diesel Generator Engine Coolers Diesel Generator Air Start valves All relief valves important to safety except ADS valves '(e.g.,
valves75-543 A and B)
Keep-Fill valves in Core Spray System (e.g.,
valves75-609 and -610)
Please provide technical justification for the omission of these valves or revise the IST program to include them.
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If the licensee desires to request additional relief from the requirements of Section XI of the 80W80 ASI1E Code, the following information should be provided for each.valve for which relief is requested:
Valve number and brief description PE IO and coordinates Function Category (ASME Section XI)
Normal position Relief requested and basis for request You, requested relief for all pumps from the requirements of paragraph IWP-3220 that all pump test data be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of-the test.
Me agree that a delay of an additional day before pump test data is completely analyzed is not significant if there is no delay in performing preliminary reviews of test data (incMu ing vibration levels) immediately after the test, and any pumps whose measured test para-meters fall within the Code "Required Act'ion Range" are immediately declared inoperable upon completion of the preliminary reviews.
Confirm that this is your intent.
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You requested relief from paragraph IWV-3411 for valves63-525 and 63-526 and propose to exercise these valves during refueling to verify that they will close.
You must also verify that these valves will perform their safety-related function by passing design flow from the SLCS to the core.
Please verify that this function will also be tested during refueling.
You requested relief from paragraph IWV-3411 for valves74-661 and 74-662 and propose to exercise these valves at each refueling because such a test entails entry into containment.
We approve this request with the condition that these valves also're tested during a cold shutdown whenever the con-tainment is de-inerted.
Please provide a commitment to perform tests during col'd shutdown whenever possible (not to exceed three months frequency) or provide justification for not commiting to this schedule.
From a review of your IST Program, the staff finds that you have elected to leak test pressure-isolation valves to verify integrity. It is the staff's position that, when leak-rate testing is used to verify the integrity of pressure isolation valves, the leakage limits selected must assure that valve sealing function has not excessively degraded.
The staff does not consider relief valve capacity in setting pressure isolation valve leakage limits.
The staff recommends a leakage limit for pressure isolation valves of 0.5 gpm per nominal inch of valve size with a maximum leakage rate of 5 gpm.
State whether you comply with this position.
If you do not comply state and justify your acceptance test limits.
Your IST program did not indicate performance of position indicator verifications as required by the Code.
Please verify that you meet this Code requirement or justify your failure to do so.