ML19344E247
| ML19344E247 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/05/1980 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8008280231 | |
| Download: ML19344E247 (7) | |
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UNITED STATES ype g
NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 J
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'+, +.....o August 5,1980 4
Docket No. 50-368 l
i Mr. William Cavanaugh, III Vice President, Generation and Construction Arkansas Power & Light Company P.O. Box 551 Little Rock, Arkansas 72203 l
Dear Mr. Cavanaugh:
We have reviewed the Arkansas Power & Light Company submittal dated December 19, 1978 which addressed the fracture toughness of the steam generator and reactor coolant pump supports.for the Al40-2 plant.
The attachment identifies additional information which we require in order to complete our review. Please advise us within seven days of receipt of this letter of your schedule for responding to this request for information.
Sincerely, Thomas fi. Novak, Assistant Director for Operating Reactors Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page 0
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Arkansas Power & Light Company, cc:
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, L ce s jcv on Arkansas Power & Light Company Office of Radiation Programs P. O. Box 551 (AW-459)
Little Rock, Arkansas 72203 U. S. Environmental Protection Agency r
gto nia 20460 ener anag Arkansas Nuclear One U. S. Environmental Protection Agency P. O. Box 608 Region VI Office Russellville, Arkansas 72801 ATTN: EIS COORDINATOR 1201 Elm Street First Inter, national Building S
u ar gu atory Comission Dallas, Texas 75270 P. O. Box 2090 Russellville, Arkansas 72801 cc w/ enclosure (s) and incoming D e r
ureau of Environmental abco W Icox Nuclear Power Generation Division 48 et ar
- a. Street Suite 420, 7735 Old Georgetown Road Little Rock, Arkansas 72201 Bethesda, Maryland 20014 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
20006 Arkansas Polytechnic College Russellville, Arkansas 72801 Honorable Emil Grant l
Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Mr. Paul F. Levy, Director Arkansas Department of Energy 3000 Kavanaugh Little Rock, Arkansas 72205 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems 4953 Cordell Avenue, Suite A-1 Bethesda, Maryland 20014 k
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REQUEST FOR ADDITIONAL INFORMATION FRACTURE TOUGHNESS EVALUATION i
STEAM GENERATOR AND REACTOR COOLANT PUMP SUPPORTS Plant:
Arkansas One Unit 2.
Plant Rating:
NUREG 0577, Group I.
References:
- 1) Arkansas Power and Light Co. (APL) Response Letter, f
Dec. 19, 1978 to USNRC.
- 2) Franklin Research Center (FRC) Report of Technical Evaluation Arkansas One, Unit 2 May 29, 1980, to USNRC.
- 3) NUREG 0577, Sept., 1979.
ITEM 1.0 CONCERN Lugs for the RCP horizontal snubber mechanism are constructed of ASTM A-283 steel.
This steel is classified by NUREG 0577 as Group I (i.e., a steel of relatively poor fracture toughness) and also does not meet the NDT screening criteria for materials generally acceptable for S/G and RCP support structures.
Moreover, these lugs appear to be thick and therefore possibly prone to brittle behavior.
Since the lugs are important to RCP support structural integrity, a fracture-toughness evaluation of lug adeque:y is needed.
REQUEST, ITEM 1.0 Please provide the folicwing information:
1)
Identify the grade of the ASTM A-283 used for these lugs.
Provide the mill test report for
.these members.
Indicate supplementary material requirements (if any) specified for these mem-bers.
Provide any other available data that may be indicative of fracture toughness.
2)
Indicate how the final rolling direction of the plate from which the lugs were cut is related to the direction of principal stress imposed by the snubber mechanism.
3)
Provide geometric details of the seismic lug and of the welding attachment of the RCP motor Case.
4)
Provide a ' fracture-toughness evaluation of the lug most highly stressed in tension under the most severe loading any lug experi-ences.
ITEM 2.0 CONCERN Some details needed to complete the fracture-toughness adequacy evaluation of the S/G hydraulic snubber system were not included in the information supplied.
REQUEST, ITEM 2.0 Please provide drawings showing how the S/G sritbber system is supported and anchored at the wall.
Indi.cate the materials for snubber connecti.ons, snubber supports, and its anchorage.
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ITEM 3.0 CONCERN The extent of the information furnished with respect to welding practice was not considered sufficient to provide an adequate basis for fracture-toughness adequacy assessment.
RE0 VEST, ITEM 3.0 For the following weld joints:
a)
Combustion Engineering (Chattanooga Division)
Dwg. 234-803 (Support Skirt Details and Assembly) weld preparations and joints s5'ch as those,
shown in Detail G, Detail B, Section DD Detail E.
b)
Combustion Engineering (Chattanooga Division)
Dwg. 234-804 (External Supports-Details and Assembly-Arkansas Nuclear Steam Generator) weld preparations and joints such as those f
(
shown for key brackets 114-01 (Section A-A) and assembly drawings shown in Sections C-C l
and E-E.
c)
Byron Jackson Dwg. ZF-1442. Revision 6 (Verti-cal Reactor Coolint Pump) welds joining lugs 1, 2, 3, 4 on pump Nos. ZP32A and ZP32D. Also joining of seismic lugs on RCP (details on drawings provided unfortunately were not cler.r).
Please furnish the following information:
a)
Welding process (es) used for these joints.
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b)
Electrode types, diameters", or other con-sumable welding materials (such as fluxes, if applicable) used.
c)
Welding conditions used.
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d)
The sequences of welding oasses used.
e)
Were any of the weldments given a post-weld heat treatment?
If so, what were the time and temperatures used?
How were the tempera-tures monitored?
f)
Were the welds inspected during fabrication?
What techniques were used?' Have subsequent weld inspections been made?
When and with what results?
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