ML20041E931
| ML20041E931 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/24/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 8203150291 | |
| Download: ML20041E931 (6) | |
Text
(f p.
DISTRIBUTION:
Docket File NRC PDR L PDR ORB #2 Rdg D. Eisenhut R. Clark S. Norris OELD AE0D IE ACRS-10 Gray Docket Hos. 50-259 50-260 FEB 2 4 1982 50-296 9
Mr. Hugh G. Parris
'4 j'
Manager of Power N
Y-D lTD h Tennessee Valley Authority 6/. -
500A Chestnut Street, Tower II O
g L-Chattanooga, Tennessee 37401
{
b?7
Dear Mr. Parris:
D' g
s j
Subject:
Inservice Inspection Program o,
3 Re: Browns Ferry Nuclear Plant, Units 1, 2 and 3 Reference is made to your letter of November 16, 1981 in which you sub-mitted a revised inservice inspection program for all three Browns Ferry units. We have completed our initial review and have detemined that we need additional infomation or justification on six of the relief requests. The requested information is discussed in the enclosure to this letter.
If you can provide the information requested within 30 days of receipt of this letter, we expect to be able to provide you a complete response including auendments revising the technical specifications (submitted by your letter of November 17, 1981) by April 30, 1982.
If you have any questions or comments, please discuss then with Dick Clark, the Browns Ferry Project Manager (FTS 492-7162).
This request for information is specific to Browns Ferry Nuclear Plant.
Units 1, 2 and 3; accordingly, OMB clearance is not required for this request under P.L.96-511.
Sincerely, p p.uu s M
~
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Enclosure:
Request for Additional Information cc w/ enclosure:
DL:
v.
R'Ci.sFk,#2,, b,.,,,,,DL ;,QRH2,...
L:0RB
"""3N6' s
- ao DVassa ilo
- >.....gj a 8.g.
......ggy.jg2
- ~2jggjtg~
~~~
8203150291 820224 PDR ADOCK 05000259 G
PDR JFFICIAL RECORD COPY
" '** - 29 24 :
NRL
Mr. Hugh G. Parris cc:
H. S Sanger, Jr., Esquire General Counsel Tennessee Valley Authority 400 Commerce Avenue E llB 33 C Knoxville, Tennessee 37902 Mr. Ron. Rogers Tennessee Valley Authority 400 Chestnut Street, Tower II.
Chattanooga, Tennessee 37431 Mr. H. N. Culver 249A HBD 400 Commerce Avenue l
l Tennessee Valley Authority Knoxville, Tennessee 37902 l
Robert F. Sullivan U. S. Nuclear Regulatory Commission Route 2, Box 311 Athens, Alabama 35611 Athens Public Library South and Forrest Athens, Alabama 35611 Mr. John F. Cox Tennessee Valley Authority W9-D 207C 400 Commerce Avenue
~
^
Knoxville, Tennessee 37902 Mr. Herbert Abercrombie Tennessee' Valley Authority P. O. Box 2000 Decatur, Alabama 35602 James P. O'Reilly Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
____.__________A__.
Enclosure REQUEST FOR ADDITIONAL INFORMATION Inservice Inspection Program Browns Ferry 1, 2, and 3 1.
Request for R'elief ISI-2 (Page 354, ref. 1)'
Thi's relief request applies to the volumetric examination requirement for reactor pressure vessel pressure-retaining welds, examination categories B-A and B-B.
Only those welds above the sacrificial shield are accessible for inservice examination Access has not been provided in the sacrificial shield area for external examinations nor does the BWR design permit internal exami-nations in this area.
Only those welds above the sacrificial shield and portions of welds as may be accessible at nozzle access points will be examined during the inservice inspection intervals.
The following additional information is requested:
(a)
Identify the welds that cannot be examined.
(b)
Identify the welds that can be examined.
(c)
For each category estimate (1) the code-required weld length that can be inspected, (2) the code required weld length that is in^ accessible, and (3) the accessible weld length, which can be examincd, but wnose examination is'not required by the code. Please supply sketches and/or other information to support your estimates.
~.
2.
Request for Relief ISI-3 (Page 355, ref.1)
This relief request applies to the volumetric examination requirement for the support attachment weld to the reactor pressure vessel, examina'. ion category B-H.
Approximately 6 feet of the attachment weld would require exainination to meet code requirements.
However, non-removable reactor vessel insulation limits inservice examination.
Two access ports, approximately 180 degrees apart, provide access for examination of two 2-foot lengths.
Four feet of'the support skirt-to-reactor vessel weld will be ultrasonically examined during each inspection interval.
l 2
l
~
The following additional information is requested:
(a)
Is it possible to perform a surface examination to supp'lement the volumetric examination.2 (b)
Please provide sketches / drawings showing the arrangement of these welds.
If previously documented in submittals to NRC, please supply r7ference(s).
~
3.
Request for Relief ISI-4 (Page 356, ref. 1)
This relief request applies to the visual examination requirement for internal pressure boundary surfaces of reactor recirculation pumps, examination category B-L-2.
In absence of required maintenance, disassembly of a recircula-tion pump solely to perform a visual examination of internal surfaces is imprac-tical.
This would represent unnecessary exposure of employees to high radiation ~
and contamination areac and excessive expense to TVA..Since the multiple units at Browns Ferry Nuclear Plant operate under similar conditions, TVA concludes that if one pump is disassembled for maintenance during the 10-year interval, the visual examination performed satisfies examination category B-L-2 requirements for the three multiple units.
Alternate inspection plans are also proposed.
The following additional information is requested:
(a ) What are the manufacturer's recommendations about disassembly of these pumps for regular maintenance?
x (b) Based on the industry experience with these pumps, what is the
~
likelihood that any Browns Ferry Unit will operate' for 10 years without disassembling one pump for maintenance?
4.,, Request for Relief ISI-5 (Page 357, ref. 1)
This relief request applies to the visual examination requirement of internal pressure boundary surfaces of valves exceeding 4-inch nominal pipe size,
-2 n
6
examination category B-M-2.
During routine maintenance, visual examinations of valve body internal pressure boundary surfaces are performed and documented.
Since the multiple units at Browns Ferry operate under similar conditions, if a valve from one of.the multiple units is disassembled for maintenance within a 10-year interval, TVA feels that the, visual examination performed would be represefitative of all three units and would be sufficient to satisfy the exami-r.ation requirements for all three units for that particular valve classification as defined in examination category B-M-2.
The following additional information is requested from TVA:
(a) i' lease furnish 'mor.e detailed justification for cude relief including man-rem and man-hour estimate:.
(b) Has ultrasonic wall thickness measurement been considered as an alternate examination?
5.
Request for Relief ISI-8 (Page 364, ref.1)
This relief request applies to the volumetric examination requirement of longitudinal, circumferential, and pipe branch connection welds of pressure-retaining welds in piping, examination categories B-J and C-F.
In some cases it'will be impractical to inspect all welds in accordance wita paragraph T 532 of Article 5,Section V, of the ASME Code, i.e., non-removable hanger inter-ference or valve and pump casings adjoining the welds.
The following additional information is requested:
-(a)
Identify -the Class 2 welds which are included in this relief request.
(b) Furnish a more detailed technical justification demonstrating that an examination is impractical to perform.
(c)
Estimate the extent of code-required examination possible for each weld for which relief is requested.
6.
Request for Relief ISI-12 (Page 381, ref. 1)-
This relief request applies to the volumetric examination requirement of pressure-retaining longitudinal welds in the Residual Heat Removal and Main 3
... ~
Steam piping systems, examination category B-J.
Three longitudinal pipe welds (adjoining circumferential welds) are partially inaccessible for inservice examination.
The following additional information is requested:
(a) Furnish a more detailed technical justification demonstrating that en examination is impractical to perform.
(b) Estimate the extent of code-required examination possible for each weld for vthich relief is requested.
(c) Have any alternate examinhtions been considered?
REFERENCE 1.
Submittal of ISI Program for Browns Ferry Plant Units 1, 2 and 3, L. M. Mills (TVA) to Harold R. Denton (NRC), November 16, 1981.
x_
e e
e 2/5/82 l