ML20028E259
| ML20028E259 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/17/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 8301210150 | |
| Download: ML20028E259 (5) | |
Text
DCD-o/(p t.
s i
74 Distribution
$7 3AN 171983 c' Ncket FilD
^
NRC PDR Local PDR ORB #2 Rdg D. Eisenhut S. Norris Docket Nos. 50-259 D. Clark 50-260 OELD and 50-296 E. L. Jordan NSIC J. M. Taylor ACRS 10 Gray File Mr. Ilugh G. Parris Manager of Power Tennessee Valley Authority 500 A Chestnut Street, Tower II Chattanooga, Tennessee 37401
Dear Mr. Parris:
SUBJECT:
INSERVICE Put!P AND VALVE TESTING PROGRAM Re: Browns Ferry Nuclear Plant, Units 1, 2, and 3 By letter dated August 31, 1982 you submitted a revised inservice pump and valve testing program in accordance with the requirements of the ASME Section XI code. Based on our review of your tub-mittal, we need the additional information identified in the enclosure to this letter. We request a response within 60 days of receipt of this letter.
This request for additional information is specific to one licensee.
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, "0RIGlini. SIGNED Bh" Domenic B. Vassallo, Chief Operating Reactors Branch f2 Division of Licensing l
Enclosure:
As stated l
cc: See next page 8301210150 830117 PDR ADOCK 05000259 P
PDR i
DL:0RB#2 DL:0RB DL:0RB#2
. S.8. c.N......
D.Clar D.Vassallo sunum)
...]f/jg3
,1,/g/83 1, /[......./83 oan >
Nnc ronu ats oo M NRCM OMJ OFFICIAL RECORD COPY us w mi-33w o
v,.
a Mr. Hv;h G. Parris cc:
H. S. Sanger, Jr.', Esquire U. S. Environmental Protection General Counsel Agency Tennessee Valley Authority Region IV Office 400 Commerce Avenue Regional Radiation Representative E 11B 33C 34S Courtland Street
~
Knoxville, Tennessee 37902 Atlanta, Georgia 30308 P
Mr. Ron Rogers Resident Inspector Tennessee Valley Authority U. S. Nuclear Regulatory Comission 400 Chestnut Street Tower II Ro.ute 2, Box 311 Chattanooga, Tennessee 37401 Athens, Alabama 35611 Mr. Charles R. Christopher Mr. Donald L. Williams, Jr.
Chairman, Limestone County Commission Tennessee Valley Authority P. O. Box 188 400 West Summit Hill Dr...W10B85 Athens, Alabama 35611 Knoxville, Tennessee 37902 Ira L. Myers, M.D.
State Health Officer George Jones State Cepartment of Public Health Tennessee Valley Authorit~y State Office Building P. O. Eox 2000 4
Montgomery, Alabama 36104 Decatur, Alabama 35502 Mr. H. N. Culver Mr. Oliver Havens 249A HED U.S. Nuclear. Regulatory Commission 400 Ccr.erce Avenue Reactor Trcining Center Tenrtessee Valley Authority Osborne Office Center, Suite 200 Knoxville, Tenne'ssee 37902 Chattanooga, Tennessee 37411 l
James P.. O'Reilly l
Regional Administrator, Region II l
U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 l
1
n
- s k
M.
REQUEST FOR ADDITIONAL INFORMATION INSERVICE PUMP AND VALVE TESTING PROGRAM
-TENNESSEE VALLEY AUTHORITY BROWNS FERRY UNIT N05.1, 2, AND 3 DOCKET N05. 50-259, 50-260 AND 50-296 1.
The program states.that it will be applicable until September 1988. Explain the basis for extending the program to that date.
2.
The Brookhaven National Laboratory reviews of your previous inservice testing (IST) programs, as documented in reports BNL-NUREG 26617. and -
26583, will, in'part, provide a basis for the NRC's safety evaluation of your IST program.
For valves that were included in the IST programs reviewed by Brook-haven, but which are not included in your new IST program, it is
. requested that you submit the basis for the deletions.
For any instances where your n'ew IST program proposes a reduction of testing requirements -(including test frequencies), other than those attributal to the use of the 1980 code, it is requested that you submit the basis for the changes.
3.
Why doesn't your program specify valve position indication checks in accord-ance with IWV-33007 e
4.
Your IST program relief request PV-1 requetts, in part, relief from require-ments for bearing temperature measurements on your RHR, Core Spray, SLC and RHRSW pumps. You state that the bearings of these pumps are lubricated by water supplied by the pumps themselves and that " satisfactory pump operation is indicative of sufficient bearing lubrication." It is our understanding
' that the intent of the code in requiring bearing temperature measurements was to ' assure detection and correction of changes in bearing performance while the p 'mps are still capable of satisfactory operation. This being the case, your ha sis for reli,ef appears faulty. Provide additional details. Do you propose any alternate test to replace bearing temperature measurement?
5.
Your new IST program shows differential pressure being measured for the SLC pump. Is this correct?
i 6.
For your new IST program relief request PV-2 submit your specific controls on inlet head.
7.
For relie'f request PV-3 in your new IST program Why do you now state that "the pumps are tested by circulating liquid i
to a tank for 2 minutes,"; whereas, in a similar request for relief j
submitted in your letter of March 3, 1979 (Request for Relief 32), you l
indicated that you would circulate liquid to the tank for 3 minutes j
during such a test?
~ - -
6 w
2 At what point in the test do you consider that the data you are obtain-ing is stable? Provide data to verify stability after two minutes.
8.
, Request for relief PV-4 in your new IST program is somewhat unclear. Veri fy that The person who performs the test has the authority to and will imme-diately review the test values an/_ determine whether they fall in the required action range of the code (ASME Section XI)
Wh'en 'the above review identifies test values in the required action range, the related pump or pumps will immediately be declared inopera-tive and not returned to service until the,cause of the deviation has been determined and corrected.
9.
Your relief request PV-5 proposes alternative testing requirements. Provide specific details of the alternative test ccmmitment including Background information on th'e alternative testing justifying - -1'ts usefulness.
A description of the alternate test procedures, including allowable ranges of test values and their bases.
10.
Relative to your relief request PV-6 45 Verify that you are only requesting relief from the portions of IWV-3417 and IWV-3523 that state "when corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup."
Shouldn't the statement given under the heading " Alternate Testing" be part of your " Basis for Relief?" It does not propose an alternate test.
11.
Relative to your relief request PV-7 Are there valves located in the lines with the CRD scram function valves which, if closed, would permit testing' of the scram function valves without scramming the control rods?
Could not symetrically opposed valves be tested simultaneously in pairs duripg operation without resulting in any requirement for significant fuel preconditoning?
12.
For the valves addressed in relief request PV-8 Why do you propose to test the valves only each refueling outage rather than at each cold shutdown?
L_
o
.s
.3 r
?
Do the subject valves ~ have permissible leakage rates specified in accordance with IWV-34267 Will analysis of leakage rates and corrective action be undertaken for the subject valves in accordance with IWV-3425 and IWV-3426, respec-tively?
- 13. Cannot the. valves addressed'in relief request PV-9 be partial-stroke exer-cised quarterly?
- 14. Guidance-provided to you by the NRC in a letter. dated January 13, 1978~
stated-that your IST program should include all safety related valves.
It appears that you do.not include all safety related valves in your program.
For. example, you do not include valves in the diesel generator fuel oil transfer lines or in the diesel generator starting air system. Why are such items not' included in your program?
4 e
9 G-9