ML20237K277
| ML20237K277 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/16/1987 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Lear G NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-87-12 OLA-I-SC-003, OLA-I-SC-3, VPNPD-87-48, NUDOCS 8709040283 | |
| Download: ML20237K277 (27) | |
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WISCONSIN Elecinc posen coumr s, sus 26 ea :02 231 W MJCHIGAN.P.o BOX 2046. MILWAUKEE.Wl53201 g
(414)277 2345 VPNPD-87448
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February 11, 1987 Document Control Desk U.S. NUCLEAR REGULATORY-COMMISSION Washington, D.C.
20555 Attention:
Mr. George Lear, Director PWR Project Directorate No. 1 3
Gentlemen:
DOCKET NOS. 50-266 AND 50-301 RESULTS OF EXAMINATION OF POISON INSERT ASSEMBLIES REMOVED FROM THE SPENT FUEL STORAGE RACKS et POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Our July 23, 1986 letter advised you of our intent to remove two poison insert assemblies from the spent fuel storage racks and examine them.
In that letter, we also committed to provi-ding you the results of our examination.
Our report, "Results of Boraflex Examination, Point Beach Nuclear Plant" is enclosed with this letter and provides the examination results and our conclusions.
In the enclosure, we note that the full-length inserts in the spent fuel fuel racks ere in excellent condition.
The full-length Boraflex inserts have behaved largely as predicted for the gamma exposure received, experiencing embrittlement and some dimensional shrinkage.
Overall, the Boraflex inserts were found suitable for performing their intended function.
On the other hand, the 2" x 2" sampler; in our surveillance program have reached a state whT reJ the Boraflex is friable and easily degraded.
The neutrun attenuation-proparties of I
the samples were confirmed by testing at the Georgia Institute l
of Technology.
However, tgirphysicalintegrityshoweddeteri-I oration at doses of 1 x 10 rads gamma and greater.
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Document Control Desk February 11, 1987 Page 2 ~
i
Currently, the average spent fuel rack position has accumulated a gamma dose equivalent to six years exposure or 3 x 10 rads The gamples have been irradiated to gamma exposures up gamma.
y tc 1.6 x 10 rads gamma.
wss examined received accelerated gamma exposures of 1 x 10The full-le rads, because it was adjacent to the sample location.
is equivalent to 20 years for the average spent fuel rack loca-This dose tion.
We have concluded from the comparison of the two programs that the samples are not representative of the full-length Boraflex inserts.
The differences obrarved between the physical condi-3 tions of the full-length sheets and smaller samples are possibly attributable to differences in methods of encapsulation, geometry, and handling frequency.
Boraflex permeation of acidic spent fuel poolWe do believe, however, that (SFP) water into Boraflex has a role in diminishing the integrity of the Boraflex material.
It further appears that the extent of SFP water permention into Boraflex is a function of gamma dose received.
" ides additional information to support these conclusions. pro-Our report To monitor the condition of boraflex in the Point Beach sp 1.
Since the samples do not appear representative of the full length Boraflex sheets and have limited value in predicting the onset of Boraflex degrada-tion in the spent fuel racks, we will terminate the Point Beach surveillance program in REI-2!, " Spent Fuel Rack Neutron Absorbing Material Surv(illance Specimen Program."
This includes eliminat ing the requirement to place freshly disebsrged sient fuel adjacent to the sample locati 3ry six months.
2.
In the place of the current surveillance program, we will examine another full-length Boraflex sheet in approximately 5 years from the present.
The recom-mended insert is at posit hasexposuresof1.5x10{gnSN-40/41, as it currently rads gamma.
3.
Subsequent examinations will be performed at locations and intervals to be determined after the next inspection.
4.
We will continue to follow the industry's development of data regarding Boraflex.
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Document Control Desk February 11, 1987 Page 3 -
f Overall,.we'believe our examination'has confirmed the continued serviceability of the full-length Boraflex inserts in the Point Beach spent. fuel racks.
If you have questions concerning our report, please do not hesitate to contact ~us.
j Very truly yours, i
1 (IjG C. W. Fay Vice President Nuclear Power Enclosure l
Copy to NRC Resident Inspector NRC Regional Administrator, Region III I
}
C_._________._____________________._________._._.__.___
February 11, 1987 RESULTS Of BORAFLEX EXAMINATION POINT BEACH NUCLEAR PLANT
(
Background,
Our license amendment application to increase the spent fuel storage capacity at Point Beach Nuclear Plant (PBNP) was submitted to NRC on March 21,'1978.
In response to NRC requests for additional information, we described a surveillance program to verify the continued integrity of the Boraflex material contained in the spent fuel storage racks.
This program utilized 30 standard, 2" x 2" Boraflex squares per pool that were control checked and placed in a surveillance train (See Figure 1).
These samples were then
&..spended in a poison box location in the spent fuel pool (SFP) such that n.shly discharged spent fuel assemblies could be placed next to the surveil-lance sample location, thus providing maximum irradiation to the samples.
Tests were to be performed after two years exposure, five years exposure, and ten years exposure.
Additional ter, ting or changes to the frequency of testing could be specified, depending upon the evaluation of specimens removed during the early portion of the program.
BISCO Report No. 1047-1, ".Boraflex I Suitability Report", Revision 1, dated May 5, 1978 provides information on the testing done to qualify Boraflex for use in the radiation and borated water environment found in the SFP.
Inthesegests,Bgraflexwasirradiatedtointegratedgammadosesofapprox-mately 10 and 10 rads.
At these dose levels, testing was done to measure changes in tensile strength, elongation, elastic modulus, dimensions, weight and hardness.
Additionally, a study of gases evolved in the test chamber
- 6 was conducted.
The qualification study also immersed Boraflex in 3,000 ppm borated water for a period in excess of 4,700 ho'brs.
The water temperature was 240*F, and the water pH was adjusted by the addition of NaOH to a range of 9.0 to 9.5.
In BISCO Report No. 748-10-1, " Irradiation Study of Boraflex Neutron Shielding Materials", dated July 25, 1979, the test program further checked the stability oftheBoraflexandtheneutrggattenuationcapabilityoftheboraflexata cummulative gamma level of 10 rads.
The qualification studies generally indicated Boraflex to be stable in the high temperature, water soak, and radiation environment found in a spent fuel pool.
ThedatagdicatedthatBoraflexwillgenerategasuptoirradia-tion levels of I x 10 rads gamma.
The qualification data indicateo that although the Borafier. embrittles with irradiation, there is little loss of neutron absorption properties or redistribution of boron.
Boraflex Use in Point Beach Spent Fuel Racks Boraflex was chosen for use as the neutron poison material in the Point Beach spent fuel racks with a recognition of its limitations.
For example, l
because Boraflex becomes embrittled and experiences some dimensional decrease i
due to gamma radiation, bonding of Boraflex in the spent fuel racks was eliminated from the Point Beach design and assembly procedure.
Instead, the
the Boraflex sheet was simply placed within stainless steel clad'that essentially forms a complete envelope around the Boraflex. This arrangement also eliminates any loading to be transmitted.to the Boraflex..To prevent poison assembly swelling due to offgassing, the tight-fitting stainless steel enve. lope was also vented at the top and made open to the SFP water environment.
[
Elimination bf the potential for galvanic corrosion was an important consid-eration in the selection of Boraflex over alternative metallic or metal-con-taining materials.
The sample test program has confirmed some of the known limitations, but the overall behavior of Boraflex in the racks is within expectations.
Neverthe-less, in the Point Beach spent fuel rack design, the poison inserts are individually replaceable should long-term neutron attenuation degradation develop in the Boraflex.
Surveillance Specimen Program - March 1985 Testing and Results In accordance with the Point Beach Nuclear Plant Boraflex sample surveillance program, six Boraflex specimen. (North Pool - N7, N8, & N9; South Pool - 54, i
55, & 56) were cut from their respective sample trains and shipped to the Georgia Institute of Technology in March.of 1985 for testing.
This testing program included neutron radiography of the samples, neutron attenuation testing utilizing a thermal beam of neutrons at an energy of 037 eV, weight and thickness measurements, hardness testing in r Shore A durometer, and isotopic analysis of the boraflex.
The specimens were dried.out in an attempt to decontaminate and reduce the radiation levels of the specimens prior to shipment to Georgia Tech.
ContactradiationreadingsofthesamplesatPBNgaveraged35-45 mrad beta gamma per hour.
Subsequent isotopic analysis of the samples at Georgia Tech determined that these radiation levels resulted principally from Cobalt-60, Cesium-134, and Silver-110.
In effect, the Boraflex samples had acted as a sponge and'had absorbed some spent fuel pool water.
In packaging for shipment, the Boraflex samples were retained inside the original clad channels that were cut from the sample trains.
The stainless steel clad was then inserted in a snug fit between lead shielding designed for a 2-2.5 inch pipe.
This was then banded, wrapped, and placed in a 55 l
gallon shipping drum.
When the drum was opened at Geor;ia Tech, it was j
observed that the stainless clad had bent somewhat and was applying a slight force to the Boraflex samples contained therein. This torsion may have contributed to some breakage of the already brittle samples.
At Georgia Tech the Boraflex specimens were observed to have broken into multiple smaller chips.
These chips were friable with a small amount of i
graphite-like particulate matter. loosely covering them.
The Boraflex chips were large enough to obtain neutron attenuation data, hardness data, and some of the thickness data requested in the' test program.
However, width and weight measurements could not be obtained as specified in the test program i
due to the crumbled state of the specimens.
Hardness of the specimens in the Shore A durometer was 100 or fully hard.
This is higher than the original material qualification Studies projected.
Neutron attenuation capability of the Boraflex was about 99%, slightly l
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higher than projected.
Sample thickness averaged about 0.1 inch and had decreased roughly as the qualification studies projected.
No conclusions could be drawn concerning the change in weight and width of the specimens duetotheirbrokensyte.
The total gamma dose to the north and south trains was 3
estimated at 1.4 x 10 R and 1.0 x 10 R, respectively.
p In reviewing the specimen degradation problems, several factors, *alone or in combination, were thought to have contributed:
The specimens were thoroughly dried out prior to shipping.
- Shipping and handling, although accomplished carefully, did apply some torsion and shocks to the specimens.
- The PBNP Boraflex specimens may have been exposed to an environment outside of BISCO's original material qualification envelope.
In other words, the Boraflex immersion tests in. BISCO's qualification study were done in a borated solution of 3,000 parts per million boron in the form of boric acid that was, however, pH adjusted by the addition of sodium hydroxide to a pH range of 9.0 to 9.5.
This differs from the Point Beach SFP environment in which the pH ranges from 4.5 to 4.9.
See Attachment 1 for typical chem-istry in the Point Beach SFP.
As initial resolution of the problems of specimen degradation and ensuing testing, several actions were taken.
Point Beach, Reactor Engineering Instruction REI-25, " Spent Fuel Rack Neutron Absorbing Material Surveillance Specimen Program," was revised to test additional Beraflex specimens immediately and in mid-1987.
This was in addition to the testing scheduled for 1990, the ten year test date.
- In preparing the Boraflex samples for shipment, they would be braced and shipped in a moist condition, with no loose water in the shipping package.
- Chemical analysis would be included in future Boraflex testing to deter-mine if the Boraflex may be undergoing a chemical reaction in the SFP environment Also at thi tirr, the geometry of poison inserts and lead-in guides in the spent fuel ;su w carefully reviewed.
It was determined that the nominally 0.11 inch thic,. k n. lex sheets were closely retained by the clad such that
" slumping" of the coraflex material could not occur even if it should crack.
The Boraflex material is sandwiched between two pieces of stainless steel sheet that are completely seam-welded on three sides and seam-welded on the top with intermittent fusion to allow gases to escape.
Supplemental Surveillance - October 1985 Testing and Results In October of 1985, three more boraflex samples (NIO, N11, & N12) were shipped i
toGeorgiaTechforasimilartegingprogram.
The total gamma dose received by the test samples was 1.6 x 10 rads.
The samples were shipped to Georgia Tech in a container of SFP water that was further packed in a shipping drum.
Upon unpacking the samples at Georgia Tech, it was observed that the water used to ship the samples was black.
Subsequent inspection and testing of the samples revealed that the corners of the Boraflex samples were rounded and the edges were eroded.
In fact, sample thickness, width, and weight for these samples decreased an average of 30%, 15%, and 50%, respectively.
Neutron attenuation capability of the Boraflexsamples,however,wasapproximately95%andwithinquallfication projections.
Hardness measurements in the Shore A durometer indicated one sample to be 100 and the other two only slightly less.
Chemical compo-sition testing (rpectographic analysis and gas chromatograph mass spectro-scopy) on a Boraflex sample and the surrounding graphite-like powder had been specified but could not be performed due to the contamination level of the samples.
While the water in the shipping container was black with graphite-like particulate shed from the samples, the Boraflex color itself was gray.
Successive immersions of the Boraflex sample into beakers of clear water darkened the water, but each time to a lesser extent.
The Boraflex sample, in turn, lightened to a whitish gray.
When a sample of this rinsed Boraflex was placed in a beaker and magnetically stirred for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, the water l
stayed clear and only " crumbs" from the sample came off.
No additional
" sooty" black material appeared.
It should be noted that the graphite-like particulate material shed from the Boraflex did not appear to dissolve to I
I any extent, but eventually settled to the bottom of the beakers, i
Again, transportation was suspected as having caused degradation of the bora-flex samples.
It was hypothesized that agitation of the Boraflex container during shipping caused erosion and wear on the Boraflex, much like might occur in a moving stream.
Supplemental Surveillance - April 1986 Testing and Results e c.
To further investigate sample thinning and degradation, an additional sample, N-13, was removed from the SFP in April 1986 and examined at PBNP.
Again, the decrease in sample thickness, width, and weight was 27%, 15%, and 50%, respectively.
The N-13 data indicated that sample thinning was occurring in the SFP environment and was not resulting primarily from transportation as suspected previously.
In summary, the neutron attenuating capability of the Boraflex was confirmed by the recent testing, but the Boraflex samples were found to be fragile and easily broken.
The following summarizes the doses the samples received:
Gamma Dose i
Boraflex Test Samples: N-7, 8, & 9
~1.44 x 10 rads S-4, 5, & 6
~1.0 x 10 rads (Tested at Georgia Tech in March 1985) 10 Botaflex Test Samples: N-10, 11 & 12
+1.55 x 10 rads (Tested at Georgia Tech in November 1985) 10 Botaflex Test Sample:
N-13
- 1.6 x 10 rads (Examined at PBNP in April 1986)
Full-length Boraflex Sheet Examination - August 1986 Since there are significant differences in the geometry and encapsulation R
methods between the Boraflex samples and the actual full-length sheets in the spent fuel storage racks, we decided to remove two full-length Boraflex sheets from the SFP and examine them on-site.
i4 On August 18-20, 1986 twoBoraflexpoisoninsertandlead-inguipeassemblies were removed from the SFP at PBNP and examined.
Af ter each asse!nbly was re-moved from tti'e spent fuel storage racks, a replacement poison assembly, manu-factured to original vaterial and dimensional specifications, was immediately
' installed.
The poison inserts were chosen for examination based on the gamma exposure received.
One poison insert was highly irradiated; the other was not.
This combination was intended to identify whether the SFP water was affecting the Boraflex, apart from known radiation embrittlement.
The location of these poison inserts in the SFP and their exposures were as follows:
SF_P LOCATION Gamma Dose SX-47 (West).
O rads 10 SP-40/41
~1 x 10 rads 10 Typical Boraflex insert in 1.B-2.0 x 10 rads spent fuel racks after 40 Years The projected 40 year exposure is based on placing fresh spent fuel in a typical location in the spent fuel racks three (3) times on thirteen (13) year cycles.
Hence, the recently tested samples had exposures approaching the 40 year design exposure of the Boraflex in the spent fuel racks.
The poison insert from SP-40/41 received one-half of this design exposure, or in,
other words, an equivalent dose equal to 20 years.
The Boraflex insert in position SP-40/41 received accelerated exposure, since it was adjacent to the location of the surveillance test samples, which'had recently discharged spent fuel assemblies placed next to them every six months.
This compares i
to a poison insert in the average spent fuel rack position which has received about six (6) years exposure or about 3.0 x 109 rads gamma.
Removal / replacement of the Boraflex insert and lead-in guide assemblies in SFP positions SX-47 and SP-40/41 was performed according to Point Beach Nuclear Plant Special Maintenance Procedure (SMP) - 728, " Examination of Bora-flex Sheets from Poison Insert Assemblies Removed from the Spent Fuel Racks."
This procedure required immediate replacement with a poison assembly manu-factured to the original material specifications after each poison insert was removed from the spent fuel storage racks.
The full length poison inserts selected for examination were chosen to l
contrast the effect of gamma irradiation and compare the effects of exposure I
to the SFP water environment on Boraflex.
This cause and effect approach was adopted because the original Boraflex material qualification studies were performed by BISCO at a pH level different than that of the Point Beach SFP.
In addition, the actual 5 year exposuie time to the SFP water environ-ment is more lengthy than that of the qualification testing.
l The Boraflex inserts were inspected according to Table 1 - Boraflex Qualita-I tive Inspection Criteria and Table 2 - Boraflex-Quantitative Inspection l
Criteria of SMP-728.
These tables are provided in Attachment 2.
Attach-l 1
~5-l l
ment 3 is a radiological survey of the samples taken from both of the larger Boraflex sheets. consists of pictures taken to document the examination of the larger Boraflex sheets.
It should 'be noted that both Boraflex sheets were wholly intact phen initially examined.
During the exam, the Boraflex was broken in many places to gauge its brittleness and hardness.
The photographs of Attachment 4 document this examination and corresponding cleavage fractures, not the as-found state of the Boraflex.
The poison insert at SX-47 received a negligible gamma dose as spent fuel was not placed in this position.
This assembly was selected to see if the acidic environment of the spent fuel pool water was causing the degradation observed in the surveillance specimens.
In the absence of gamma radiation, this did not appear to be the case.
The poison insert appeared to look brand new.
Only a whitish powder covering the Boraflex where it was in contact with the stainless steel clad distinguished the SX-47 Boraflex insert from new Boraflex.
0 The poison insert at SP-40/41 received accelerated irradiation to 1 x 10 rads gamma.
This insert had good integrity with no pieces missing, no cracking, or other degradation observed.
This is unlike the samples S4, 5, and 6 at the same dose.
The thickness of the Boraflex sheet was consistent over its length, nominally 0.1 inches.
Over most of the insert length, the Boraflex sheet was black and did not have dust or powder being shed from it.
There were some discolored areas along the edges of the Boraflex insert from SP-40/41.
These appeared as gray scallops working into the material and typically measured 0.25 inches deep by about 2.5 inches long. The largest gray patch observed was 0.5-0.75 inches deep by about 5 inches long.
The gray discolorations were spaced randomly along the edges and probably occupied about 1-2% of the entire Boraflex sheet surface area.
These gray l
areas when first observed were reminiscent of the color of the Botaflex samples.
Further examination showed that, although the thickness of the Boraflex at the gray areas was consistent with nominal Boraflex thickness, the gray area yielded a dust or powder much like the samples when rubbed.
Overall, the insert from position SP-40/41, although brittle, had good integrity with minimal degradation.
I Some additional observations on the full-length Boraflex inserts based on I
their radiation levels can be made. As stated previously, the Boraflex samples sent to Georgia Tech averaged 35-45 mrad / hour beta gamma, on contact.
These radiation levels were found to principally result from absorption of spent fuel water that contained cobalt and cesium.
The radiation levels of samples taken froe the unirradiated Boraflex insert from position SX-47 were less than 2 mrad / hour beta gamma.
This indicates l
the unirradiated insert hardly absorbed any spent fuel pool water.
The radiation levels of samples taken from the irradiated insert from position SP-40/41 were approximately 2 mrad / hour gamma and 8-12 mrad / hour beta, on contact.
These radiation levels are less than the surveillance samples, but still indicate some absorption of spent fuel pool water.*
1 1
Radiation levels on contact with the discolored, " gray" area from a section of the SP-40/41 insert were approximately 2 mrad / hour gamma, 80-90 mrad / hour beta, and some detectable alpha.
This perhaps indicates that spent fuel pool water was_being absorbed preferentially along the edges of the Boraflex.
It also leads to the following observations about the progression gf degradation intheBora{ lex:
1.
In the absence of gamma radiation, Boraflex appears to be inert to the SFP environment.
The unitradiated insert retained "like-new" Boraflex material properties and did not appear to absorb SFP water.
2.
With gamma irradiation, the Boraflex polymers appear to change in a manner that allows SFP water to permeate the Boraflex along the edges.
When the SFP water does penetrate the Boraflex, the material changes character.
It changes a material of good integrity and retention to one that is friable and yields a particulate-like powder.
It also changes color from black to gray.
Once it has reached the " gray" state, thinn'ng, weight loss, and general degradation appear to follow.
~
3.
It appears SFP water preferentially permeates the Boraflex on the edges where it was cut to a dimension apropriate for placement in the insert assembly.
The " finished" broad surface of the Boraflex appears to be resistant to water permeation.
The 2" x 2" samples in the surveillance program had relatively small distances between cut edges, hence the SFP water could totally saturate the sample in a short period.
Also, it would appear that the higher gamma radiation leve.ls received by the samples may have enhanced this process.
- 0 4.
In the case of Boraflex exposed to PBNP conditions, it appears that Boraficx may begin to be susceptible to water germeation and subsequent y
changes in material integrity at about 3 x 10 rads gamma.
Conclusions The Boraflex samples appear to have experienced more degradation for a given gamma dose than the full length boraflex insert.
This degradation only occurs in the presence of gamma irradiation.
It is possibly enhanced by differences in the method of encapsulation.
Sample degradation may be enhanced due to the fact that the edge area / surface area ratio of the samples is larger than that of actual full sheets.
This allows permeation of the SFP water through-out the sample relatively quickly.
In contrast, permeation is only evident at the edges of the larger irradiated Boraflex insert.
In either case.
however, when SFP water permeation occurs the Boraflex material changes from a material of good integrity to one that is easily degraded.
Theonsetgf y
permeation and subsequent Botaflex degradation occurs roughly at 1 x 10 rads gamma or at the 20 year point in the Boraflex design life at Point i
Beach.
It is believed that the chemical changes described are a second stage i
degradation mechanism separate from the shrinkage and embrittlement which occur initially in Boraflex in tervice.
Currently, the average spent fuel pool rack position hgs accumulated a gamma dose, equivalent to six (6) years exposure of 3.0 x 10 rads gamma.
It is observedthatafulllengthBgaflexinserthasgoodoverallintegritythrough 20 equivalent years or 1 x 10 rads gamma.
Thus, the Boraflex inserts in the racks are expected to retain their serviceability for another 10-20 years.
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Parameter Range
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pH 4.5 - 4.8 C1
<.05 ppm F1
<.05 ppm Boron s2000 ppm (TS Lower L'imit - 1800 ppm; 0
4-5 ppm 2
si s5 ppm Gross B y 8xlb4 pC/cc Temperature of the SFP water is controlled between 70 F and 90 F, and it typically runs in the eighties (80's) high in the SFP.
At the lower levels in the vicinity of the fuel, temperatures are considerably hotter.
I
ATTACHMENT 2 TABLE l' BORAFLEX QUANTITATIVE INSPECTION CRITERIA t.
Poison insert and lead-in guide assembly:
SFP Location
_5P-40/41 10 Total Gamma Dose 1 x 10 Rads Gamma Location Along Length of Boraflex Sheet Average Values of Top Middle Bottom l
l 1.
Thickness @ center (inches)
.095
.101
.096 l
(nom. = 0.11")
2.
Thickness O edges (inches)
.094
.111
.102 3.
Width (inches) 7.75 7.75 7.75 (nom. = 8.0")
4.
Weight:
IDEAL vs ACTUAL (gms)
Ideal 17.9 17.7 17.2 (Assume pboraflex = 3.69 gm/cc)
Actual,19.7 18.9 17.3-i
. l 1
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ATTACHMENT 2 TABLE 2 BORAFLEX QUALITATIVE INSPECTION CRITERIA y
Poison insert and lead-in guide assembly:
5FP Location SP-40/41 10 s
Total Gamma Dose 1 x 10 Rads Gamma Criteria Comments (Location, Extent, etc.)
- 1. White milky substance present Yellow staining on entire length where in contact with stainless sheet, like some sort of dried powder.
- 2. Missing pieces No
- 3. Cracking Yes - Some observed from cutting and handling; otherwise had good integrity.
- 4. Powdery substance accumulation in bottom of cladding No,
- 5. Slumping of boraflex None
- 6. Thinning on edges / fraying, strings on edge of boraflex Not occurring
- 7. Surface porosity and pitting None
- 8. Color:
gray vs. black Some gray patches on edges, which seems to " powder" like the samples did.
- 9. Friability Does not crumble, rather it snaps in brittle fashion.
- 10. Brittleness / flexibility Brittle, yet will bend over length.
=-
i ATTACHMENT 2 TABLE 1 BORAFLEX QUALITATIVE INSPECTION CRITERIA i
Poison insert and lead-in guide assembly:
SFP location SX-47 West Total Gamma Dose s0 Criteria
- Comments (Location, Extent, etc.)
- 1. White milkey substance pr.esent White stain entire. length, where in contact with the stainless sheet, mostly in middle of. ladder fashion.
- 2. Missing pieces No
- 3. Cracking No
- 4. Powdery substance accumulation in bottom of cladding No
- 5. Slumping of boraflex-No
- 6. Thinning on edges / fraying, strings on edge of boraflex No
- 7. Surface porosity and pitting No
- 8. Color:
gray vs. black All black
- 9. Friability No
- 10. Brittleness / flexibility Very flexible and bends well; breaks when pinched hard over.
l l
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.__.____________-___.2
__________-_______.________.__._____________._____U
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ATTACHMENT 2 TABLE 2 BORAFLEX QUANTITATIVE INSPECTION CRITERIA f.
Poison insert and lead-in guide assembly:
SFP Location SX-47 West Total Gamma Dose o
i Location Along Length of Boraflex Sheet Average Values of Top Middle Bottom 1.
Thickness @ center (irches)
.093
.094
.099 (nom. = 0.11")
2.
Thickness @ edges (inches)
.091
.104
.096 3.
Width (inches) 7,gg 7,gg 7,gg (nom. = 8.0")
4.
Weight:
IDEAL vs~ ACTUAL (gms)
Ideal 23.9 27.2 21.1 (Assume pboraflex = 1.69 gm/cc)
Actual 22.6 25.7 20.4 1
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ATTACHMENT 4 1
PHOTOGRAPHS OF FULL-LENGTH BORAFLEX INSERTS TAKEN DURING EXAMINATION ON AUGUST 18-20, 1986 s
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