ML20070H509

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TMI-1 Recovery:Regenerative Neutron Source Retainer Exam
ML20070H509
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 05/20/1982
From: Bain G, Mcinteer W
BABCOCK & WILCOX CO.
To:
Shared Package
ML20070H501 List:
References
RDD:83:5489:01, RDD:83:5489:1, NUDOCS 8212270042
Download: ML20070H509 (22)


Text

{{#Wiki_filter:____ _ __ __ ______ _ _ F5rm LRC-139 Raso2rch cad D;v;lspm;;t Disisita LYNCHBURG RESEARCH CENTER babcock & W.lCOX i LYNCHBURG, VIRGINIA [ID J. E. MATHESON, FUEL ENGINEERING, NPGD RRADIATED MATERIALS TECHNOLOGY, LRC [ From [.(( INTER Cust. File No. GPUN or Rel. RDD:83:5489:01 Subj. Date TMI-l RECOVERY - RNS RETAINER EXAMINATION MAY 20, 1982 m.1.++., to c .., a. cu,+...r . d . bi.c, fy.

SUMMARY

As part of the TMI-l recovery effort, a RNS retainer was examined at the LRC Hot Cell Facility. Although it was unirradiated, the retainer had been installed in-core since the EOC-4 outage in late 1978. Detailed testing of the retainer and its component. parts included: o visual examinations a spring load-deflection and full-compression tests g a sodium azide spot tests o liquid penetrant checks a bend tests a metallography and JEM examinations

                     =    chemical analysis of surface wipe samples While sulfur compounds were found on the external retainer surfaces, there was no evidence of mechanical property degradation or sulfur assisted intergranular I            attack.                                                                                                             f DISTRIBUTION (COMPANY LIMITED) This information is freely available to all Company personnel. Written approval by the sponsoring unit's                                         ,

R&D coordinator is required only when release outside the Company is l requested. DISTRIBUTION: R&DD NPGD Baty, DL Irman, SC Baker, RJ (30) Garner, GL l Bh.da, RK Library /LRC (2) Carey, RO Piascik, RS CIS/ ARC Li [ (3) Lynch, ED Culberson, DG Stein, KO Davis, HH Mayer, JT DeMars, RV Uotinen, VO Engelder, Project File Dideon, CG Shield, WA 8212270042 821027 PDP ADCCK 05000289 I P PDP l

i 1 ! I l I I! l I I B6W makes no warranty or representation, exprested or implied:

           . with respect to the accuracy, completeness, or usefulness of the information contained in this report
           . that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights.

B&W assumes no liability with respect to the use of, or for damages

  • sulting from the use of:
           . any information, apparatus, method, or process disclosed in this report
           . experimental apparatus furnished with this report.

I I E I E k I

L [ BABCOCK & WILCOX RDD:83:5489:01 Page 1 [ ACKNOWLEDGMENTS E The authors greatly appreciate the contributions of J. E. Bullard (chemical analysis), V. D. Downs (scanning electron microscopy), and B. J. Parham (metallography) to the successful completion of this effort. E E E , I l I l L r u I - l l ' l l l I I

I I BABCOCK & WILCOX R10:83:5489:01 Page 2 l

1. INTRODUCTION l

x Analysis of cracked tubes from both A and B steam generators at TMI-l indicated I the failure mode was intergranular stress corrosion cracking with a reduced form o'f sulfur most likely acting as the corrosive agent.1 Since the tube { cracks were initiated from the ID surface, the presence of sulfur contaminents in the primary system implies the potential for material degradation of other RCS components. , A detailed examination of a regenerative neutron source (RNS) retainer from the TMI-l core was conducted at B&W's Lynchburg Research Center as part of an effort to assess potential damage to various core components.2 Although the ( retainer was unirradiated, it had been installed during the end-of-cycl'e four outage, and the retainer spring and load legs had been in a stressed condition while exposed to the RCS environment. A RNS retainer was selected for exami-nation since it contained materials representative of a wide range of core components (304 SS, 308 SS veld metal, and Inconel X750). After receipt at the LRC, the retainer (#L106) was visually examined and load-l deflection tests of the spring were performed. The retainer was then dis-assembled and the following tests were conducted on the components: o detailed visual examination l o spring compression test o sodium azide spot tests l l o liquid penetrant checks l o bend tests o metallography o SEM examinations E ' Chemical analyses were also performed on cloth wipe samples from the retainer - components and on samples obtained at the reactor site. Wipe samples taken at l TMI-l were from the north face of a new fuel assembly (NJ0132) and from the retainer, prior to shipment. 4 L I

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b BABCOCK & WILCOX RDD:83:5489:01 Page 4 [

2. EXAMINATIONS AND RESULTS 3 ,4 2.1 Visuel Examinations 2.1.1 Method visual examination of the retainer and its component parts was conducted at magnifications up to 60X with a stereo microscope. Photographic records of visual observations were taken with a 4XS camera attached to the microscope.'

Macrophotographs of the retainer were taken with a MP-3 copy camera. 2.1.2 Results { A visual inspection of the retainer, prior to disassembly, showed no cracks in the weld, knee, or foot regions of the retainer legs. A schematic view of a retainer identifying its various components is shown in Figure 1. Typical macrophotos of the leg weld, knee, and foot regions are shown in Figure 2. Virtually no crud was observed on the outside surface. Overall views of the retainer are shown in Figures 3 and 4. After disassembly all retainer components were examined in detail. Disassem-bly consisted of cutting the top fitting off the can and cutting the numbered leg from the hub through the weld area. Examination of the retainer legs showed no cracks or evidence of sulfur assisted attack of the surfaces. Sev-eral areas of black and white deposits and two small areas of yellow deposits were noted. The black areas are most likely crud and the white areas appear to be boron crystals from the coolant. Attempts to identify the composition of the yellow deposits by SEM/EDAX analysis were unsuccessful, and the previously ) ( reported compositions4were obtained from a contaminated sample. Other EDX analyses on similar deposits found on the reactor vessel o-ring indicate the composition is mostly Fe with some Cr.5 The spring surface was a uniform dark gray with localized areas of black and white deposits (see Figure 5). Two small areas also had yellow deposits similar to those found on the retainer leg. Examination of the retainer can showed no signs of surface degradation. The outside of the can had a thin, black oxide layer with a blue tint. The in-side of the can had a dark, powdery crud layer with several areas of localized crud deposits. _ _ _ _ _ _ _ _ _ _ _ _ _ . _ J

I -

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BABCOCK & WILCOX RDD:83:5489:01 Page 5 2.2 Spring Load-Deflection Tests 2.2.1 Method Prior to disassembly the X750 spring was tested for preload and spring rate using a load-deflection test rig previously used for irradiated retainers from Oconee 3.6 The retainer spring was compressed using known weights of up to 100 pounds, while spring deflection was measured with two dial indicators accurate to 0.001 inch. 2.2.2 Results Three load-deflection curves were recorded and are shown in Figure 6. Measured spring preloads ranged from 40 to 41 pounds and spring rates from 47-50 pounds I per inch. These values are considered normal and agree with other retainer data. I 2.3 Spring Compression Test 2.3.1 Method After the retainer was disassembled, the spring was compressed to its solid spring height using five lead bricks. Eack brick weighed a nominal 26 pounds. Relaxed spring height was measured before and after full compression with dial calipers accurate to 0.001 inch. 2.3.2 Results Relaxed spring height before and after full compression was 4.00 inch, indicat-ing no plastic deformation occurred during testing. After testing, the outer surface of the spring was visually examined at 10X magnification with a stereo microscope. No cracks or other forms of damage were observed. I 2.4 Sodium Azide Spot Tests 2.4.1 Method 7 f Sodium azide spot tests for the presence of reduced forms of sulfur were con-ducted by placing drops of test solution on surfaces of interest (spring, leg, I l i

BABCOCK & WILCOX RDD:83:5489:01 Page 6 [ weld area, inner and outer can surfaces). The areas where the drops were placed ( were then observed through the stereo microscope. Bubbles from the solution indicate the presence of reduced forms of sulfur (sulfide, thiosulfate, etc.). The basis for the test is the catalytic acceleration of the iodine-azide re- { action by reduced forms of sulfur. This reaction evolves free nitrogen gas to produce bubbles and will detect reduced forms of sulfur at concentrations less than one ppm. 2.4.2 Results Outside surfaces of the retainer components showed positive reactions to the sodium azide spot test. The inner surface of the can and the retainer spring showed negative reactions. Results of the tests are summarized below: Retainer Component Run Spring L3 Leg-Weld Can (outside) Can (inside) I neg. pos. neg. pos. neg. 2 neg. pos. pos. pos, neg. Tests indicated the presence of reduced sulfur on outer surfaces of the retain-er. The inside of the can and the Inconel X750 spring showed no evidence of reduced sulfur, but results may have been affected by crud deposits. 2.5 Liquid Penetrant Tests 2.5.1 Method Liquid penetrant tests were conducted on the retainer leg and hub and on the spring using the procedure specified in Reference 6. The ,icces were ultra-sonically degreased with tichloroethylene, cleaned with Spotcheck Cleaner / Remover, and dried with clean cloths. The parts were sprayed with Spotcheck Penetrant and kept thoroughly wetted for 20 minutes. The spring was tested while under compression to open any cracks that may have been present. After removing excess penetrant, the parts were uniformly covered with Spotcheck developer and visually inspected.

RABCOCK & WILCOX RDD:83:5489:01 Page 7 2.5.2 Results l No indications of cracks were observed in either the leg, weld area, or spring. The only positive indications observed were from elongated surface inclusions on the sides of the leg. 2.6 Bend Tests 2.6.1 Method Bend tests were performed on the leg / hub weld region and a 1-1/2 inch piece 1 - from the middle coil of the spring. The parts were clamped in a vise and bent to open any cracks which may have been present. 2.6.2 Results The leg veld was bent through appror.imately 45 degrees with no visible crack initiation, indicating a sound weld. The spring sample was bent and fractured. The fracture surface vai examined with an SEM to characterize the mode of failure. The SEM examination showed the fracture surface was new and failure was 100 percent ductile. Examples of the appearance of the fracture surface are shown in Figure 7. No evidence of intergranular cracking was observed. 2.7 Metallography 2.7.1 Method ( Samples from the leg, knee, weld area, and the active coil and contact region of the spring were mounted in Buehler Epomet. The samples were ground flat on silicon carbide through 600 grit and polished with alumina. Final polishing was done with 0.05 micron alumina. The samples were then metallographically examined at 400X magnification for evidence of intergranular attack. The samples were examined in both polished and etched conditions. The Inconci X750 spring material was etched with copper regia and the 304 and 308 stainless steel samples with glycerol regia.

s C BABCOCK & WILCOX RDD:83:5489:01 Page 8 2.7.2 Results The microstructure of all the samples appeared normal and no evidence of inter-granular attack was observed. Figure 8 shows typical etched microstructures of the 304 SS base metal, 308 SS weld metal, and X750 sp ing. The weld area and heat-affected zone are shown at 50X in Figure 9. 2.8 Chemical Analysis of Surface Wipe Samples 2.8.1 Method 1 - Cloth wipe samples were taken from the RNS retainer and a new fuel assembly, NJ0132, at TMI-2 prior to shipment of the retainer to the LRC. The retainer wipe covered 15.5 square-inches of the leg area. The fuel assembly wipes covered one face of a grid and across 15 rods just below a grid. Wipe samples were taken from the retainer af ter disassembly at the LRC. Samples were ob-tained from one retainer leg, two coils of the spring, and the inner and outer surfaces of the can. Wipe samples from the disassembled retainer were analyzed for chlorine content by a LRC procedure similar to ASTM D512. " Tests for Chloride Ion in Water and Waste Water," and for sulfur content by a procedure similar to ASTM D516. " Tests for Sulfate Ion in Water and Waste Water." Since the chloride ion results were low (8 pg total or less) and used half the wipe sample, wipe samples from TMI-l ( were only tested for sulfate content. 2.8.2 Results Chloride and sulfate ion contents of wipe samples from the retainer parts were low, < 5 to 8 pg total Cl and < 20 to 50 pg total S0 2 . When the back-ground from the cloth samples was subtracted, only the sample from the spring showed any removable sulfur. Results of the sulfate analysis of wipe samples are given below: r --

BABCOCK & WILCOX RDD:83:5489:01 Page 9 LRC Wipe Sample Results (cloth batch 67) l RNS Total Less Total

  • Wipe Removable Component S0s, vg Blank Sample S. pg Area, in2 Sulfur, pg/in2 blank 18 blank 15 Avg <20 Leg <20 - --

20 -- Spring 50 >30 >20 9 %2 3 Can 25 >5 >3 28 -- (outside) Can <20 I (inside)

  • on a whole cloth basis Cloth wipe samples taken from the retainer after it was removed from the core and from the fuel assembly grid and rods showed slightly higher levels of re-movable sulfur, in the range of three to five ug/in2 Results of the sulfate analysis arc given below:

TMI-l Wipe Sample Results Cloth Total Less Total Wipe Removable Batch Sample SO4, pg Blank Sulfur, pg Area, in2 Sulfur, pg/in2 75 blank 30 1 blank < 10 Avg < 20 Zr Fuel 50 > 30 > 10 2.7 44 Rods Inconel 90 >70 >23 8.1 %3 Grid i 71 blank blank Avg

                             <10 20
                             <l5 Cloth           20           >5         >1.7 Dipped in core Retainer        243          228             76        15.5                                       45 l

l 1

BABCOCK & WILCOX RDD:83:5489:01 Page 10

3. CONCLUSIONS I While reduced forms of sulfur were detected on the retainer components, there was no evidence of mechanical property degradation or intergranular attack.

I I 'I I I I I I I I I I 4 lI 1 il -_ _. . _ - _ __ _ __ _

I BABCOCK & WILCOX RDD:83.3489:01 Page 11

4. REFERENCES I 1. M. A. Rigdon and E. B. S. Pardue, " Evaluation of Tube Samples from TMI-l -

Final Report," RDD:83:5390-03:01, Babcock & Wilcox, Lynchburg, Virginia. April 1982.

2. C. G. Dideon to D. G. Culberson, Memorandum, "TMI-1 Recovery - Core Exami-nation Task," FPO-82-41, March 24, 1982.

I 3. W. A. McInteer and G. M. Bain to Distribution, Memorandum, TMI Core Re-covery - Initial Retainer Exam," April 30, 1982.

4. W. A. McInteer to C. G. Dideon, Memorandum, "TMI Core Recovery - RNS Re-tainer Detailed Exam," May 6, 1982.
5. D. L. Baty. " Examination of TMI-2 Reactor Vessel 0-Ring and CRDM Closure Insert," RDD:83:5490/5491:01, Babcock & Wilcox Lynchburg, Virginia, May 25, 1982.
6. E. B. S. Pardue, " Examination of Oconee 3 RNS Retainers," LRC 9085, Babcock
       & Wilcox Lynchburg, Virginia February 1982.
7. F. Feigl Laboratory Manual of Spot Tests, p. 163-166, Academic Press, New York, 1943.

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