ML18068A509

Forwards Response to 980731 RAI Re Reactor Vessel Fluence Calculation.Ltr Contains No New Commitments & Revs to Existing Commitments

ML18068A509
Person / Time
Site:	Palisades
Issue date:	12/15/1998
From:	Haskell N CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9812230160
Download: ML18068A509 (115)

Text

A CMS Energy Company Palisades Nuclear Plant Tel: 616 764 2276 27780 Blue Star Memorial Highway Fax: 616 764 2490 Covert, Ml 49043 Nathan L. Haskell Director. Licensing December 15, 1998 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT RESPONSE TO THE JULY 31, 1998 REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REACTOR VESSEL FLU ENCE CALCULATION By letter dated July 31, 1998, the NRC requested additional information related to the Palisades reactor vessel fluence calculation submitted on April 4, 1996. The information was requested to be submitted within 60 days of the request date. That due date was extended to December 31, 1998 by the NRC Palisades Project Manager.

The NRC staff requested this additional information to supplement other information which had been previously requested and was provided by Consumers Energy letters dated June 12, June 21, August 28, September 9, September 19 and October 1, 1996; June 26, 1997; and April 2, April 20, and April 21, 1998. Additionally, meetings were held on May, 15, 1996 and January 15, February 23, May 28, October 19 and December 7,1998 to facilitate technical dialogue between Consumers Energy and the NRC staff. As a result of the October 19, 1998 meeting, the Consumers Energy staff and the NRC staff agreed that the fluence calculation using plant specific measurements advocated by the Consumers Energy staff was not likely to be approved by the NRC staff at this time or in the near future; and, that a different fluence calculation based on industry average data was more likely to be approved. That industry average based approach was again discussed at the December 7, 1998 meeting where it was agreed that Consumers Energy would make three additional submittals modifying the fluence calculation to incorporate the industry average data and changes in plant parameters which have defined physical bases. Also, it was agreed that Consumer Energy would submit the response to the July 31, 1998 RAI by December 31, 1998. ,. ; . f . 1

• "', ~~ \.: \~ .......

r~~~=q~a7.122~3~0~1~6Cro~9a;1'125-~1!55~-~~.~~~~\

~DR ADOC~ 0500PoR.2{ I

I,

• • • ' f

\

2 The attachment to this letter provides our response to the July 31, 1998 RAI. It will bring the review of record relating to our plant specific measurement based fluence calculation to closure at a point where it could be systematically re-initiated in the future.

SUMMARY

OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.

}iathan L. Haskell Director, Licensing CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Attachment

\

~e.

ATTACHMENT CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255

• RESPONSE TO THE JULY 31, 1998 REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REACTOR VESSEL FLUENCE CALCULATION December 15, 1998

- f

• I. Uncertainty Values. In the methodology utilizedfor .fluence determination, the calculated

.fluence value and the contribution of high energy dosimeters is effectively ignored. The staffsuspects that this effect probably arose from the assignment of large uncertainties to the calculated l!alues in the methodology. Please provide a complete list of all the uncertainties, including the covariances (and associated gamma values), for all the quantities involved in the FERRET calculation andjustify application of these values to the Palisades plant.fluence determination. The justification should be based on analytical as well as physical reasoning. Any values and/or assumptions based on educated guesses or that are not quantified or justified with data should be clearly identified.

The above request states that the contributions of the fluence calculation and the high energy dosimeters are effectively ignored in the determination of Palisades best estimate fluence. This statement is essentially correct. The request implies that this represents a weakness. However, this is not a weakness, it is in fact what would be expected given the data used to calculate the best estimate fluence.

The calculated fluence is not ignored. It is essential to the methodology that the calculated fluence provides an accurate representation of the relative fluence within the vessel and at the measurement locations. However, the uncertainty of the calculated fluence is greater (2-3 times) than that of the measured data. When this information is mathematically combined in the least squares methodology, it is expected that the best estimate would come out looking like the measurements.

Any other answer would be troubling.

The high energy dosimetry is not ignored, it just has no significant value in the best estimate of the fluence above 1 Mev. These dosimeters do not see a significant portion of the fluence. When measurements from the high energy dosimeters are combined with calculated fluence in the higher energy bands, no adjustment is necessary. They agree and no correction/adjustment is made to this data. However, there is a significant difference at the lower energies. The final result is that -5 %

(high energy) of the neutrons see a correction/bias of 1.0 and -95% (low energy) see a correction/bias of 0.83, yielding an overall correction that is closer to 0.83 than 1.0. The high energy dosimetry is not ignored, it just is not informative. The reason for this difference is covered later in the response to NRC request 2.

The FERRET least squares evaluation requires reaction rates, dosimetry cross-sections, and calculated spectrum as well as the associated uncertainties for each. Each one of these parameters have been addressed in previous submittals in response to Staff Requests for Additional Information (RAI). These responses are summarized in Table 1-1.

• 1-1

... - t

• Table 1-1 Summary of Previous Submittals Addressing FERRET Input Uncertainty Values Parameter Response Reaction rates

• 3.1.2.5 ofRAI dated 05/15/96

. 08/14/96 Presentation to Staff on Accuracy of Reaction Rate Measurements .

Dosimetry cross sections

• 3.1.2.6 ofRAI dated 05/15/96

• 08/14/96 Presentation to Staff on Accuracy of Reaction Rate Cross-Sections Calculated spectrum

• 3.1.2.7 ofRAI dated 05/15/96 FERRET parametric study

• 3.4 ofRAI dated 08/14/96

• 3.5 of RAI dated 08/14/96

• 3.6 of RAI dated 08/14/96

• 3.9 of RAI dated 08/14/96 For the sake of continuity, all of the response to RAI 3.1 (05/15/96) is provided. This information was previously submitted (June 21, 1996, Attachment 1, pp. 17-25). Following this response is the presentation material made to the Staff on 08/14/96. In addition to the FERRET parametric studies conducted previously and identified in Table 1-1, a new FERRET parametric study was conducted which evaluated the effect on the best estimate fluence due to varying the calculated input spectrum and dosimetry uncertainties. This is presented after the responses to RAls 3.4, 3.5, 3.6, and 3.9 dated 08/14/96.

RA13.1 (05/15/96) Describe the uncertainty analysis for the accelerated capsule, the inner wall capsule and the cavity dosimeters. Include: position, counting, weighing, power history, calibrations, cross sections, etc.

3 .1.1. General Discussion The methodology used in the evaluation of the multiple foil dosimetry sets irradiated at the Palisades reactor utilizes a least squares adjustment procedure to produce a best fit among the calculated neutron spectrum at each sensor set location and the set of measured reaction rates from the dosimetry package. In this methodology, uncertainties in the derived exposure rates [<j> (E > 1.0 MeV), (E > 0.1 MeV), and dpa] at the measurement locations are dependent on the resultant fit of the adjusted spectrum to the measured data; and include a combination of the uncertainties in measured reaction rates, sensor cross-sections, and the calculated spectrum .

• 1-2

In the analysis performed for the Palisades reactor, both the "best estimate" exposure rates and the associated uncertainties were obtained from the measured reaction rates, dosimetry cross-sections, and calculated neutron spectra by means of the SAND-II/FERRET least squares adjustment procedure. See the response to Request 3.4 (05/15/96) for further discussion of the SAND-II/FERRET approach (Submitted June 21, 1996, Attachment 1, pp. 29-30).

The use of an adjustment procedure to evaluate neutron dosimetry from Light Water Reactors is described in ASTM E 944 - 89, "Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Vessel Surveillance", as follows:

"3 .3 .2.1 The algorithms of the adjustment codes tend to decrease the variances of the adjusted data compared to the corresponding input values. The least squares adjustment

.codes yield estimates for the output data with minimum variances, that is, the 'best' estimates. This is the primary reason for using these adjustment procedures."

In using the adjustment procedure, dosimetry measurements are provided as a set of reaction rates denoted by the following symbols:

R; i = 1,2, ...

Reaction cross-sections for the dosimetry sensors are obtained from the Sandia National Laboratories Radiation Metrology Laboratory (SNLRML) ENDF/B-VI based evaluated dosimetry cross-section file. The cross-sections for the ith reaction as a function of energy are denoted by the following:

cri (E) i = 1,2, ....

The calculated neutron spectrum input to the adjustment procedure are obtained on a location specific basis from the results of the cycle specific discrete ordinates transport calculation. The group fluxes from the transport calculation are denoted by the following:

<l>j j = 1,2, ... k The uncertainties associated with the measured reaction rates, dosimetry cross-sections, and calculated neutron spectrum are also input to the adjustment procedure in the form of variances and covariances. In the evaluations performed for the Palisades reactor, the assignment of the input uncertainties also follows the guidance provided in the ASTM standard E 944-89.

1-3

- r

• 3.1.2. Uncertainties in the Input to the Adjustment Procedure 3 .1.2.1 Measured Reaction Rates The determination of the individual reaction rates involves laboratory counting procedures, decay corrections to account for the operating history of the reactor, and corrections for competing reactions within the sensors. Each of these facets of the reaction rate determinations are discussed in this section.

3 .1.2.2 Counting Procedures Internal surveillance capsule and ex-vessel reactor cavity dosimetry packages employed at the Palisades reactor consist of comprehensive multiple foil sensor sets that make use of some or all of the following reactions:

63 Cu (n,a) 6°Co 46Ti (n,p) 46Sc s4Fe (n,p) s4Mn s8Ni (n,p) ssco 238 U (n,f) 137Cs 237Np (n,f) mes 59 Co (n,y) 60Co Following irradiation, the specific activity of each of the irradiated radiometric sensors is determined using the latest version of ASTM counting procedures for each reaction. In particular, the following standards are applicable to the radiometric sensors utilized in LWR programs:

E523 Standard Test Method for Measuring Fast Neutron Reaction Rates by Radioactivation of Copper E526 Standard Test Method for Measuring Fast Neutron Reaction Rates by Radioactivation of Titanium E263 Standard Test method for Measuring Fast Neutron Reaction Rates by Radioactivation of Iron E264 Standard Test Method for Measuring Fast Neutron Reaction Rates by Radioactivation of Nickel E704 Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238

• 1-4

E705 Standard Test Method for Measuring Reaction Rates by Radioactivation of N eptunium-23 7 E481 Standard Test Method for Measuring Neutron Fluence Rate by Radioactivation of Cobalt and Silver El 005 Standard Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance E 181 Standard General Methods for Detector Calibration and Analysis of Radionuclides Following sample preparation and weighing, the specific activity of each sensor is determined by means of a lithium drifted germanium, Ge(Li), gamma spectrometer. In the case of the multiple foil sensor sets, these analyses are performed by direct counting of each of the individual sensors, or, as is sometimes the case with 238 U and 23 7Np fission monitors from internal surveillance capsules, by direct counting preceded by dissolution and chemical separation of cesium from the sensor.

3 .1.2.3 Decay Corrections Having the measured specific activities, the operating history of the reactor, and the physical characteristics of the sensors, reaction rates referenced to full power operation are determined from

• the following equation:

R =

A where:

R Reaction rate averaged over the irradiation period and referenced to operation at a core power level of P,.r (rps/nucleus).

Measured specific activity (dps/gm).

Number of target element atoms per gram of sensor.

= Weight fraction of the target isotope in the sensor material.

Number of product atoms produced per reaction.

Average core power level during irradiation period j (MW).

= Maximum or reference power level of the reactor (MW) ..

Calculated ratio of <j>(E > 1.0 MeV) during irradiation period j to the time weighted average <j>(E > 1.0 MeV) over the entire irradiation period.

Decay constant of the product isotope (I/sec).

Length of irradiation periodj (sec) .

Decay time following irradiation periodj (sec).

1-5

and the summation is carried out over the total number of monthly intervals comprising the irradiation period.

In the above equation, the ratio [PY[P,.r] accounts for month by month variation of power level within any given fuel cycle as well as over multiple fuel cycles. For the sensor sets utilized in surveillance capsule and reactor cavity irradiations, the half-lives of the product isotopes are long enough that a monthly histogram describing reactor operation has proven to be an adequate representation for use in radioactive decay corrections for the reactions of interest in the exposure evaluations. The ratio Ci, calculated for each fuel cycle using discrete ordinates transport technology, accounts for the change in sensor reaction rates caused by variations in flux level induced by changes in core spatial power distributions from fuel cycle to fuel cycle. For a single cycle irradiation, such as is common with cavity dosimetry, Ci is taken to be 1.0. However, for multiple cycle irradiations, particularly those employing low leakage fuel management, the additional Ci correction must be employed. This additional correction can be quite significant for internal surveillance capsules that have been irradiated for many cycles in a reactor that has transitioned from non-low leakage to low leakage fuel management.

3 .1.2.4 Corrections for Competing Reactions Prior to using the measured reaction rates in the dosimetry evaluation procedures, additional

• corrections are made to the 238 U measurements to account for the presence of 235 U impurities in the sensors as well as to correct for the build-in of plutonium isotopes over the course of the irradiation.

These corrections are location and fluence dependent and are derived from the results of the discrete ordinates calculations and, when available, with measurements from paired uranium dosimeters.

In addition to the corrections made for the presence of 235 U and the build-in of plutonium isotopes in the 238 U fission sensors, corrections are also made to both 238U and 237Np sensors to account for gamma-ray induced fission reactions occurring over the course of the irradiation. These photofission corrections are, likewise, location dependent and are based on the plant specific discrete ordinates transport calculations.

3.1.2.5 Reaction Rate Uncertainties The overall uncertainty associated with the measured reaction rates used in the evaluation of exposure parameters includes components due to the basic measurement process, the irradiation history corrections, and the corrections for competing reactions in the fission sensors. A matrix of the uncertainties associated with the reactions applicable to the Palisades dosimetry evaluations is as follows:

1-6

Decay Competing Net Reaction Counting Correction Reactions Uncertainn:

63 Cu (n,a.) 60Co 3% 2% 0% 4%

46Ti (n,p) 46Sc 3% 4% 0% 5%

54Fe (n,p) 54Mn 3% 2% 0% 4%

5 8Ni (n,p) 58Co 3% 4% 0% 5%

238 U (n,f) mes 5% 3% 4% 7%

237Np (n,f) mes 5% 3% 1% 6%

59 Co (n,y) 6°Co 3% 4% 0% 5%

In developing this uncertainty tabulation, the counting component is derived from the expected accuracy using the appropriate ASTM standards. The component due to irradiation history (decay correction term) includes the effects of short vs long product half lives, the product yield in the fission monitors, and target abundance in the sensor material. The uncertainties due to competing reactions were based on the assumption that the error in the calculated correction using the plant specific transport results could be as high as 25% and the resultant uncertainty in the net reaction rate is then 25% of the total correction. For example, a 25% uncertainty in a 4% photofission correction to a measured dosimeter activity results in a net 1% additional uncertainty in the derived reaction rate.

In addition to the use of the ASTM standards in the evaluation of sensor reaction rates, over the course of the last 15 years these procedures have been tested via round robin counting exercises included as a part of the NRC sponsored Light Water Reactor Surveillance Dosimetry Improvement Program (LWR-SD IP) as well as by evaluation of fluence counting standards provided by the National Institute of Science and Technology (NIST). Each of these counting exercises involved evaluation of neutron sensors typical of those used in light water reactor measurement programs.

The results of these studies demonstrated that these procedures do, in fact, produce measured reaction rates within the 1cr uncertainties specified in the above tabulation.

A further consistency check on the measured reaction rates from in-vessel surveillance capsule and reactor cavity dosimetry irradiations is obtained from an examination of the several location and reactor dependent data bases built up over many years of performing reactor dosimetry. Examples of these data bases are provided in WCAP-14044, "Westinghouse Surveillance Capsule Neutron Fluence Re-evaluation", E. P. Lippincott, April 1994. The plant data included in these data bases also lend support to the reaction rate uncertainties specified above.

3 .1.2.6 Dosimetzy Cross-Sections As noted in Section 3.1.1, the dosimetry cross-sections are taken directly from the SNLRML evaluated dosimetry cross-section data base (DLC-178, RSIC Data Library Collection SNLRML, Recommended Dosimetry Cross Section Compendium, July 1994). Cross-section uncertainties in the form of variances and covariances are provided on this data file along with the basic dosimetry 1-7

cross-section data. Detailed covariance matrices for each of the reactions comprising the multiple foil sensor sets used at Palisades are provided in the attachment to this response.

3 .1.2. 7 Calculated Spectrum The uncertainties in the calculated neutron energy spectrum at the location of the individual sensor sets are also input in the form of variances and covariances with the following specifications:

Flux Normalization Uncertainty 30%

Flux Group Uncertainties (E > 0.0055 MeV) 30%

(0.68 eV < E < 0.0055 MeV) 58%

(E < 0.68 eV) 104%

Short Range Correlation (E > 0.0055 MeV) 0.9 (0.68 eV < E < 0.0055 MeV) 0.5 (E < 0.68 eV) 0.5 Flux Group Correlation Range (E > 0.0055 MeV) 6 (0.68 eV < E < 0.0055 MeV) 3 (E< 0.68 eV) 2 It should be noted that the uncertainties listed for the upper energy ranges extend down to the lower energy range. Thus, the 58% group uncertainty in the second range is made up of a 30% uncertainty with a 0.9 short range correlation and a range of 6, and a second part of magnitude 50% with a 0.5 correlation and a range of 3. The covariance matrix associated with the calculated flux spectrum is provided as an attachment to this response.

3.1.2.8 Other Uncertainties Additional uncertainties such as sensor positioning, vessel inner radius, vessel thickness, and water density variations are evaluated based on sensitivity studies using the transport code calculations.

These additional uncertainties are included after the dosimetry evaluations are completed and are considered an uncertainty in relating the MIC bias factor to positions that are removed from the measurement locations; i.e., the pressure vessel wall.

08/14/96 Presentation to Staff Accuracy of Reaction Rate Measurements The accuracy of the reaction rate measurements obtained from surveillance capsule and reactor cavity irradiations is assured by utilizing .laboratory procedures that conform to ASTM National 1-8

Consensus Standards for each of the sensors comprising the multiple foil dosimetry sets. In particular, the following standards are applied for the reactions of interest.

Reaction Standard 63 Cu (n,a) 6°Co ASTM-E-523 46Ti (n,p) 46Sc ASTM-E-526 S4fe (n,p) s4Mn ASTM-E-263 58Ni (n,p) 58Co ASTM-E-264 238 U (n,f) mes ASTM-E-704 237Np (n,f) mes ASTM-E-705 59Co (n,y) 6°Co ASTM-E-481 In all cases, the latest available versions of the applicable standard are used in the dosimetry evaluations.

From these standards, it is noted that the expected uncertainties in the measured disintegration rates can be summarized as follows:

Reaction Precision Bias 63 Cu (n,a) 6°Co 1% 3%

46Ti (n,p) 46Sc 1% 3%

54Fe (n,p) 54Mn 1% 3%

58Ni (n,p) 58Co 1% 3%

238 U (n,f) mes 1% 5%

237Np (n,f) mes 1% 5%

s9co (n,y) 6oco 1% 5%

These uncertainties include the impacts of sample weighing, detector calibration, geometry source/detector geometry corrections, and product nuclide branching ratios.

In determining reaction rates from the measured specific activities, the following additional uncertainties are incurred.

1-9

Reaction Fission Yield Product Half-life Competing Reactions 63 Cu (n,a) 60Co 0.02%

46Ti (n,p) 46 Sc 0.2%

S4fe (n,p) s4Mn 0.2%

5 8Ni (n,p) 58 Co 0.2%

238 U (n,f) mes 1% 0.1% 4%

237Np (n,f) mes 2% 0.1% 1%

59Co (n,y) 6°Co 0.02%

After combining all of these uncertainty components, the sensor reaction rates derived from the counting and data evaluation procedures used for surveillance capsule and cavity dosimetry irradiations typically result in the following net uncertainties associated with the data:

Reaction Reaction Rate Uncertainty 63 Cu (n,a) 6°Co 5%

46Ti (n,p) 46Sc 5%

54Fe (n,p) 54Mn 5%

5 8Ni (n,p) 58Co 5%

238 U.(n,f) mes 10%

237Np (n,f) mes 10%

59Co (n,y) 6°Co 5%

These uncertainty values are quoted at the 1CJ level.

In addition to the use of ASTM National Consensus Standards in the evaluation of sensor reaction rates, over the course of the last 17 years, these procedures have been tested via round robin counting exercises included as a part of the NRC sponsored Light Water Reactor Surveillance Dosimetry Improvement Program (L WR-SDIP) as well as by evaluation of fluence counting standards provided by the National Institute of Science and Technology (NIST). In all, the following five separate counting comparisons were conducted between 1980 and 1997.

1980 Round robin counting of foil sets irradiated at the Thermal Shield Back (TSB) and Pressure Vessel Face (PVF) positions of the PCA simulator.

1981 Round robin counting of additional foil sets included in the first metallurgical simulated surveillance capsule also irradiated in the PCA benchmark mockup.

1-10

These two counting exercises involved direct comparisons with measurements obtained by The Hanford Engineerjng Development Laboratory (HEDL). At the time of these irradiations HEDL was a prime contractor providing measurement services for the PCA benchmark and was cross-calibrated with NIST and the MOL Laboratory in Belgium.

1985 Counting and evaluation of 46Ti(n,p), 54Fe(n,p), and 58Ni(n,p) certified fluence standards supplied by NIST.

Comparisons with fluence standards involve the determination of the reaction rate of each foil, but also of the spectrum averaged cross-section in the NIST 235 U irradiation facility. Thus, the comparisons with the certified fluence test both the measurement process and the energy dependent reaction cross-section used by the vendor.

1992 Counting of NIST foils irradiated in a reactor cavity dosimetry experiment at the Trojan reactor.

This exercise involved duplicate counting of a subset of irradiated foils by both Westinghouse and NIST to assure adequate cross-calibration of the laboratories so that data could be confidently mixed in the overall fluence evaluations performed by NIST and ORNL.

1996 Irradiation of a set of foils used in Westinghouse cavity dosimetry irradiations at the Materials Dosimetry Reference Facility (MDRF) and subsequent comparison with certified results provided by NIST.

Results of the first four inter-comparisons are summarized as follows:

Westinghouse I HEDL Westinghouse I NIST Reaction 1980 1981 1985 1992 Average 63 Cu (n,a.) 60Co 1.041 1.018 0.969 1.009 46Ti (n,p) 46Sc 1.036 1.012 1.030 1.026 s4Fe (n,p) s4Mn 1.006 1.008 1.011 1.056 1.020 58Ni (n,p) 58Co 1.006 0.990 1.028 1.029 1.013 238 U (n,f) mes 1.014 1.014 1.014 237Np (n,f) mes 1.006 1.017 1.012 s9co (n,y) 6oco 1.017 1.017 1.017 Final results of the comparisons from the 1996 irradiations are still pending, but preliminary evaluations support the data comparisons in the preceding tabulation.

1-11

• The comparisons shown in the preceding table demonstrate that the procedures used by Westinghouse in the determination of reaction rates from both in-vessel surveillance capsule irradiations and ex-vessel cavity irradiations have produced accurate and stable results over a period spanning the last 17 years. The cross-comparisons with HEDL and NIST support the typical uncertainties of 5% for *non-fission reactions and 10% for fission reactions that are assigned to Westinghouse reaction rate results.

Further, the certified fluence comparisons performed in 1985, support not only the radiometric counting capability of the Westinghouse Analytical Services Laboratory, but also, demonstrate the accuracy of the 46Ti(n,p), 54Fe(n,p), and 58Ni(n,p) energy dependent reaction cross-sections that are used in the dosimetry evaluations.

08/14/96 Presentation to Staff Accuracy of Reaction Rate Cross-Sections The reaction rate cross-sections used in the neutron fluence evaluations were taken from the RSIC DATA LIBRARY COLLECTION DLC-178 "SNLRML Recommended Dosimetry Cross-Section

• Compendium," July 1994. This data library provides reaction rate cross-sections and associated uncertainties for 66 dosimetry sensors in common use. These cross-sections were drawn from the most recent cross-section evaluations and they have been compared with each other and evaluated with respect to their accuracy and consistency for spectrum unfolding calculations. The library has been empirically tested for use in fission spectra determination as well as in the fluence and energy characterization of 14 MeV neutron sources.

For sensors of interest to Light Water Reactor (LWR) dosimetry applications, the following uncertainties in the fission spectrum averaged cross-sections were provided in DLC 178.

Reaction Uncertain~

63 Cu (n,a) 6°Co 4.08-4.16%

46Ti (n,p) 46 Sc 4.51-4.87%

s4Fe (n,p) s4Mn 3.05-3.11%

58Ni (n,p) 58Co 4.49-4.56%

238 U (n,t) mes 0.54-0.64%

237Np (n,t) mes 10.32-10.97%

s9co (n,y) 6oco 0.79-3.59%

1-12

• Detailed discussions of the contents of the SNLRML library along with the evaluation process for each of the sensors is provided in DLC-178.

The data provided in SNLRML coupled with the certified fluence comparisons discussed earlier .

demonstrate that reaction rates as well as reaction cross-sections used in the neutron fluence evaluations provide adequate accuracy.

RAI 3.4, 3.5; 3.6, and 3.9 (08/14/96) (Submitted September 19, 1996, Attachment 1, pp. 26-30).

3 .4 Recognizing the substantial uncertainty in the cross section covariance data, what is the effect on the FERRET jluence adjustment of taking the covariances to be zero? Are the cross section covariances available for all dosimeter cross sections and, if not, how are these cross sections treated?

3.5 Provide a quantitative basis for the FERRET methodology assumptions concerning the specific form ofthe spectrum con*elation matrix, Pgg' and assumed values ofthe parameters

()and y for application to the Palisades in-vessel and cavity dosimetry? Why doesn't the correlation matrix allow for anti-correlation? What is the sensitivity of the FERRET jluence adjustment to these assumptions?

3.6 Provide an analysis indicating the sensitivity of the FERRET -5% jluence reduction to increasing and decreasing the input uncertainty estimates by a factor of two.

3.9 The FERRET analysis determines the dosimeter jluence using an initialjluence guess based on the DORT calculation. If the jluence determined by FERRET is then used as a more accurate initial jluence guess for a subsequent FERRET calculation, how does the jluence determined by this second FERRET calculation compare to the DORT calculation and the first FERRET calculation. Is the convergence error, indicated by the difference between the two FERRET calculations, small compared to the 5% FERRETjluence adjustment?

These four requests are combined so that the sensitivity analysis of the least squares adjustment procedure results can be shown as a whole. However, each request will be addressed individually as necessary for clarification. Tables 3 .4-1 and 3 .4-2 provide the results of the studies requested above for the in-vessel wall capsule W290-9, irradiated during Cycle 9, and ex-vessel capsule 16° (280°) Cycle 9. It should be noted that changing the least squares adjustment parameters has little effect on the flux but impacts the calculated uncertainty.

3.4 Are the cross section covariances available for all dosimeter cross sections and, ifnot, how are these cross sections treated?

Covariances are available for all dosimeter cross sections from "SNLRML Recommended Dosimetry Cross Section Compendium" Oak Ridge National Laboratory, July 1994.

3.5 Provide a quantitative basis for the FERRET methodology assumptions concerning the specific form ofthe spectrum correlation matrix, Pgg' and assumed values ofthe parameters 1-13

• (}and y for application to the Palisades in-vessel and cavity dosimetry? Why doesn't the correlation matrix allow for anti-correlation?

A detailed covariance matrix is constructed as a sum of its components:

• where each component, M, represents a source of uncertainty that is independent (uncorrelated) from other sources. Each component can then be specified element by element {Miss'} or in terms of fractional uncertainties {Ilg} and a correlation matrix {Pss'}:

Mg*g = Rg Rg* Pg*

In the absence of a detailed covariance matrix, i.e. not every source of uncertainty is specifically known, Equation 3.5-2 may be replaced by:

where Rn (independent of g and g') specifies an overall fractional normalization uncertainty (i.e.,

complete correlation) for the set of values. The fractional uncertainties Rg specify additional random uncertainties for group g that are correlated with a correlation matrix given by:

where:

H= (g-g').

2 r2 The first term in the correlation matrix equation {888 .} specifies purely random uncertainties, while the second term describes short range correlations over a group range y (8 specifies the strength of the latter term). The value of 8 is 1 when g = g' and 0 otherwise. This information was based on the code development ofF. Schmittroth 1*

Anti-correlations are physically undefined as given in Equations 3 .5-2 and 3 .5-3 defining the covariance matrix (a matrix of the absolute magnitude as defined by covariance). However, varying the values of the strength {8} and range {y} within the physical bounds is presented in Tables 3.4-1 and 3.4-2 for the in-vessel wall capsule W290-9 and ex-vessel capsule 16° (280°) Cycle 9, respectively.

1 Schmittroth, F., "FERRET Adjustment Code - Status/Use", Proceedings of the 4th ASTM-EURATOM Symposium on Reactor Dosimetry", NUREG/CP-0029, NRC, Washington D.C., July 1982 .

• 1-14

• 3.9 Is the convergence error, indicated by the difference between the two FERRET calculations, small compared to the 5% FERRETfluence adjustment?

The data presented in Tables 3.4-1and3.4-2 show that the convergence error is very small compared to the uncertainty in the ~djusted flux and to "5% FERRET fluence adjustment".

1-15

Table 3.4-1 In-vessel Capsule W290-9 RAI ~ (E> 1.0 MeV) lcr Fractional Issue Description n/cm 2s Uncertaintt Change Reported2 Adjusted~ (E> 1.0 MeV) 3.123e+10 7%

3.4 X-section covariances= 0 3.081e+10 6% -0.013 3.5 Spectrum Correlation Matrix e = 1, y =doubled 3.183e+10 6% 0.019 e = 1, y =nominal 3.11 le+lO 7% -0.004 e = 1, y = halved 3.136e+10 8% 0.004 e =nominal, y =doubled 3.190e+ 10 6% 0.021 e = nominal, y = halved 3.139e+10 8% 0.005 e = 0, y = doubled 3.223e+10 7% 0.032 e = 0, y = nominal 3.223e+10 7% . 0.032 e = 0, y = halved 3.223e+l0 7% 0.032 3.6 Uncertainty Sensitivity X-section = doubled 3.094e+10 12% -0.009 Dosimetry = doubled X-section = nominal 3.196e+ 10 10% 0.023 Dosimetry = doubled X-section =halved 3.333e+l0 7% 0.067 Dosimetry = doubled X-section =doubled 3.097e+l0 8% -0.008 Dosimetry = nominal X-section = halved 3.227e+10 5% 0.033 Dosimetry = nominal X-section =doubled 3.150e+10 6% 0.009 Dosimetry = halved X-section = nominal 3.137e+10 5% 0.004 Dosimetry = halved X-section =halved 3.188e+10 4% 0.021 Dosimetry = halved 3.9 Input Spectrum Iteration 3.072e+10 7% -0.016

• WCAP-14557, Rev 1 - Table 5.2-3 1-16

Table 3.4-2

~ Ex-vessel Capsule 16' (280') Cycle 9 RAI cj> (E> 1.0 MeV) lcr Fractional Issue Description 2 n/cm s Uncertain!):: Change 3

Reported Adjusted cj> (E> 1.0 MeV) 8.560e+08 8%

3.4 X-section covariances= 0 8.715e+08 7% 0.018 3.5 Spectrum Correlation Matrix e = 1, y =doubled 8.582e+08 6% 0.003 e = 1, y =nominal 8.566e+08 8% 0.001 e = 1, y = halved 8.503e+08 10% -0.007 e = nominal, y = doubled 8.629e+08 7% 0.008 e = nominal, y = halved 8.472e+08 10% -0.010 e = 0, y = doubled 8.082e+08 10% -0.056 e = 0, y = nominal 8.082e+08 10% -0.056 e = 0, y = halved 8.082e+08 10% -0.056 3.6 Uncertainty Sensitivity X-section =doubled 8.671e+08 14% 0.013 Dosimetry = doubled X-section =nominal 8.607e+08 11% 0.005 Dosimetry = doubled X-section =halved 8.655e+08 8% 0.011 Dosimetry= doubled X-section =doubled 8.627e+08 10% 0.008 Dosimetry = nominal X-section = halved 8.502e+08 6% -0.007 Dosimetry = nominal X-section =doubled 8.494e+08 8% -0.008 Dosimetry = halved X-section = nominal 8.452e+08 6% -0.013 Dosimetry = halved X-section =halved 8.338e+08 5% -0.026 Dosimetry = halved 3.9 Input Spectrum Iteration 8.656e+08 8% 0.011

• WCAP-14557, Rev 1-Table6.2-10 1-17

• The four requests from the 08/14/96 RAis (3.4, 3.5, 3.6, and 3.9) addressed input uncertainties to the FERRET least squares evaluation. The parametric studies performed to respond to the RAis evaluated the dosimetry cross-section covariances, the spectrum correlation matrix, the reaction rate measurement and cross-section uncertainties, and the input spectrum.

Another FERRET parametric study was conducted for this most recent RAis which evaluated the effect on the best estimate fluence due to varying the calculated input spectrum and dosimetry uncertainties. Tables 1-2 and 1-3 provide the results of this study for the in-vessel wall capsule W290-9, irradiated during Cycle 9, and ex-vessel capsule 16° (280°) Cycle 9. As noted in the responses to 08/14/96 RAis 3.4, 3.5, 3.6, and 3.9, changing the least squares evaluation parameters has little effect on the best estimate flux but impacts the calculated uncertainty.

Table 1-2 In-vessel Capsule W290-9 Change in Best Estimate Flux Reaction Rate Measurement Uncertainty Half Nominal Double Input Half 0.07% 4.07% 9.20%

Spectrum Nominal -1.06% 0% 3.77%

Uncertainty Double 0.03% -0.89% 0.03%

Best Estimate Flux Uncertainty Reaction Rate Measurement Uncertainty Half Nominal Double Input Half 4% 5% 7%

Spectrum Nominal 5% 6% 10%

Uncertainty Double 5% 8% 12%

1-18

• Table 1-3 Ex-vessel Capsule 16" (280") Cycle 9 Change in Best Estimate Flux Reaction Rate Measurement Uncertainty Half Nominal Double Input Half -3.01% -0.02% 2.61%

Spectrum Nominal -2.01% 0% 1.08%

Uncertainty Double -1.40% 0.64% 1.54%

Best Estimate Flux Uncertainty Reaction Rate Measurement Uncertainty Half Nominal Double Input Half 4% 6% 8%

Spectrum Nominal 5% 7% 11%

Uncertainty Double 7% 10% 14%

• 1-19

Attachment to Response to Item 1 of 07/31/98 RAI ATTACHMENT This attachment provides the requested covariance information used in the Palisades fluence evaluations. The data are given in the FERRET 53 energy group sructure and include both the groupwise standard deviations and the fractional. covariance matrices input to FERRET. In order to conserve space only the lower triangle of the symmetric covariance matrices are provided.

The FERRET group structure is summarized as follows:

Upper Upper Upper Energy Energy Energy Group ~ Group ~ Group IMfil1 1 1.73E+01 19 - 3.88E-01 37 2.75E-04 2 1.49E+01 20 3.02E-01 38 1.67E-04 3 1.35E+01 21 1.83E-01 39 1.01E-04 4 1.16E+01 22 i.11E-01 40 6.14E-05 5 1.00E+01 23 6.74E-02 41 3.73E-05 6 8.61E+OO 24 4.09E-02 42 2.26E-05 7 7.41 E+OO 25 2.55E-02 43 1.37E-05 8 6.07E+OO 26 1.99E-02 44 8.32E-06 9 4.97E+OO 27 1.50E-02 45 5.04E-06 10 3.68E+OO 28 9.12E-03 46 3.06E-06 11 2.87E+OO 29 5.53E-03 47 1.86E-06 12 2.23E+OO 30 3.36E-03 48 1.13E-06 13 1.74E+OO 31 2.84E-03 49 6.83E-07 14 1.35E+OO 32 . 2.40E-03 50 4.14E-07 15 1.11E+OO 33 2.04E-03 51 2.51E-07 16 8.21E-01 34 1.23E-03 52 *1.52E-07 17 6.39E-01 35 7.49E-04 53 9.24E-08 18 4.98E-01 36 4.54E-04

• A-1

~

Cu-63 3.17E-02 (n, a:)

Reaction Cross-Section in FERRET Group Structure 4.22E-02 4.24E-02 3.54E-02 2.66E-02 1.79E-02 9.BSE-03 3 .13E-03* 5.12E-04 3.86E-05 2.83E-06 1.SBE-07 3.94E-10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cross-Section Standard Deviation 7.57E-02 7.64E-02 7.45E-02 9.32E-02 7.52E-02 8.06E-02 9.56E-02 1. 03E-01 1.33E-01 1. 92E-01 2.67E-01 1. OOE+OO 1.00E+OO l.OOE+OO 1.00E+OO 1.00E+OO 1.00E+OO l.OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO 1. OOE+OO 1. OOE+OO l.OOE+OO 1.00E+OO 1.00E+OO 1.00E+OO 1. OOE+OO 1. OOE+OO 1.00E+OO 1.00E+OO 1.00E+OO 1. OOE+OO 1.00E+OO 1.00E+OO 1.00E+OO

1. OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO 1. OOE+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO l.OOE+OO 1.00E+OO Lower Triangle of the 53x53 Covariance Matrix 5.73E-03 4.82E-03 3.76E-03 2.71E-03 1. 36E-03 l.22E-03

1. llE-03 7.70E-04 6. 71E-04 6.86E-04 6.48E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.84E-03 4.SBE-03 3.26E-03 1.64E-03 1.47E-03 l.33E-03 9.27E-04 8.07E-04 8.25E-04 7.BOE-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.SSE-03 4.59E-03 2.lBE-03 l.95E-03 1.77E-03 1. 23E-03 1.07E-03 l. lOE-03 1. 04E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-2

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.69E-03 2.0BE-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.13E-03

1. 96E-03.

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.70E-03 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 3.36E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.33E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.03E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.65E-03 4.87E-03 4.34E-03 3.0lE-03 2.62E-03 2.68E-03 2.54E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.49E-03 6.06E-03 4.04E-03 3.52E-03 3.60E-03 3.40E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO e

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9 .13E-03 6.03E-03 5.17E-03 5.29E-03 5.00E-03 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. 06E-02 7.31E-03 7.34E-03 6.94E-03 O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.76E-02 1. 98E-02 l.61E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO A-3

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.69E-02 3.44E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0. OOE+OO* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.llE-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO e A-4

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. 00.E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 0. OOE+OO- O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO A-5

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-6

O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO. O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO l.OOE+OO A-7

Ti-46 (n,p)

Reaction Cross-Section in FERRET Group Structure 2.19E-01 2.45E-01 2.56E-01 2.48E-01 2.26E-01 l.98E-01 1.46E-Ol 8.80E-02. 3.40E-02 4.14E-03 4.38E-05 l.70E-07 5.SlE-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cross-Section Standard Deviation

1. 46E-Ol l.19E-01 9.00E-02 8.00E-02 8.00E-02 8.00E-02 8.00E-02 8.00E-02 8.00E-02 3.57E-01 6.89E-01 1. OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO

1. OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO

1. OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO

1. OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO

1. OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO Lower Triangle of the 53x53 Covariance Matrix 2.13E-02 l.SSE-02 l.llE-02 8.98E-03 7.77E-03 6.42E-03 4.84E-03 3.24E-03 l.75E-03 3.40E-03 2.69E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. 43E-02 9.52E-03 7.95E-03 7.12E-03 6.09E-03 4.79E-03 3.36E-03 l.92E-03 3.99E-03 3.35E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.lOE-03 6.33E-03 5.90E-03 5.25E-03 4.32E-03 3.19E-03 1. 95E-03 4.34E-03 3.89E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-8

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.27E-01 2.07E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.75E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+.00 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-10

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO. O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-11

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO- O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-12

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO. O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO l.OOE+OO O.OOE+OO 0.00E+OO

.1. OOE+OO O.OOE+OO l.OOE+OO

• A-13

Fe-54 (n,p)

Reaction Cross-Section in FERRET Group Structure 2.29E-01 3.38E-01 4.36E-01 4.73E-01 4.82E-01 4.82E-01 4.78E-01 4. 32E-01* 3.06E-Ol l.85E-01 7.40E-02 2.21E-02 3.42E-03 9.87E-04 l.73E-04 3.65E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cross-Section Standard Deviation 6.69E-02 6.56E-02 5.63E-02 4.36E-02 4.36E-02 3.58E-02 3.74E-02 3.SOE-02 3.68E-02 4.69E-02 4.69E-02 5.llE-02 7.21E-02 7.21E-02 l.20E-Ol l.58E-01 1. 58E-01 l.OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO 1. OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO 1. OOE+OO 1. OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO Lower Triangle of the 53x53 Covariance Matrix 4.47E-03 3.73E-03 3.13E-03 9.44E-04 9.44E-04 6.22E-04 3.17E-04 4.86E-04 4.87E-04 4.64E-04 4.64E-04 5.28E-04 5.78E-04 5.78E-04 8.29E-04 9.60E-04 9.60E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.30E-03 3.65E-03 1.30E-03 l.30E-03 8.03E-04 3.30E-04 5.29E-04 5.26E-04 4.90E-04 4.90E-04 5.52E-04 6.00E-04 6.00E-04 8.37E-04 9.60E-04 9.60E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.17E-03 1. 43E-03 l.43E-03 9.32E-04 4.59E-04 5.52E-04 5.43E-04 5.07E-04 5.07E-04 5.52E-04 5.87E-04 5.87E-04 7.86E-04 8.89E-04 8.89E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-14

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.90E-03 l.90E-03 1. 40E-03 9.30E-04 6.37E-04 6.06E-04 5.70E-04 5.70E-04. 5.53E-04 5.40E-04 5.40E-04 5.99E-04 6.30E-04 6.30E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.90E-03 l.40E-03 9.30E-04 6.37E-04 6.06E-04 5.70E-04 5.70E-04 5.53E-04 5.40E-04 5.40E-04 5.99E-04 6.30E-04 6.30E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 1.28E-03 l.17E-03 8.29E-04 7.56E-04 6.16E-04 6.16E-04 5.99E-04 5.86E-04 5.86E-04 5.88E-04 5.89E-04 5.89E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. 40E-03 l.OlE-03 8.98E-04 6.60E-04 6.60E-04 6.43E-04 6.30E-04 6.30E-04 5.77E-04 5.50E-04 5.50E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. 45E-03 l.34E-03 9.82E-04 9.82E-04 8.80E-04 8.00E-04 8.00E-04 8.04E-04 8.05E-04 8.05E-04 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. 35E-03 1. 33E-03 l.33E-03 l.09E-03 8.91E-04 8.91E-04 7.62E-04 6.94E-04 6.94E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-15

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 2.20E-03 2.20E-03 l.SSE-03 l.lOE-03 l.lOE-03 6.20E-04 3.70E-04 3.70E-04 O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.20E-03 l.SSE-03 l.lOE-03 l.lOE-03 6.20E-04 3.70E-04 3.70E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.61E-03 3.41E-03 3.41E-03 3. 71E-03 3.87E-03 3.87E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.20E-03 5.20E-03 6.12E-03 6.60E-03 6.60E-03 _o. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.20E-03 6.12E-03 6.60E-03 6.60E-03 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. 44E-02 l.87E-02 l.87E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.SOE-02 2.SOE-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.SOE-02 O.OOE+OO O.OOE+OO O.OOE+OO

• A-16

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO. O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-17

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO- O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O:OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO A-18

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO

0. OOE+OO.

O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 1.00E+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO 0.00E+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO l.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 1. OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO 1. OOE+OO

• A-19

Ni-58 (n,p)

Reaction Cross-Section in FERRET Group Structure 2.13E-01 3.67E-01 5.25E-01 5.99E-01 6.24E-01 6.25E-01 6.0SE-01 5. OSE-01. 3.75E-01 2.33E-01 1.16E-01 4.25E-02 1.65E-02 7.17E-03 1. 87E-03 7.20E-04 2.lOE-04 1.88E-36 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO Cross-Section Standard Deviation 1.60E-01 1.SOE-01 1.28E-01 1.12E-01 7.07E-02 6.12E-02 7.07E-02 6.89E-02 6.66E-02 1.03E-01 1.03E-01 9.14E-02 1.41E-01 1. 41E-01 1.45E-01 1.SOE-01 1.00E+OO 1.00E+OO

1. OOE+OO 1.00E+OO 1.00E+OO 1.00E+OO 1. OOE+OO 1.00E+OO 1.00E+OO 1. OOE+OO 1. OOE+OO l.OOE+OO 1. OOE+OO l.OOE+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO

1. OOE+OO 1.00E+OO l.OOE+OO 1. OOE+OO 1. OOE+OO 1. OOE+OO 1.00E+OO 1.00E+OO 1.00E+OO 1.00E+OO 1. OOE+OO

• Lower Triangle of the 53x53 Covariance Matrix 2.SSE-02 O.OOE+OO O.OOE+OO 1.lOE-02 O.OOE+OO O.OOE+OO 3.28E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.25E-02 2.02E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.63E-02 4.03E-03 1.87E-03 1.87E-03 1.87E-03 1.87E-03 1.87E-03 1.87E-03 1.87E-03 8.20E-04 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-20

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.25E-02 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 1.09E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.00E-03 3. 72E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 1.09E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.75E-03 3.78E-03 2.57E-03 2.50E-03 2.50E-03 2.50E-03 1.09E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.00E-03 2.64E-03 2.50E-03 2.50E-03 2.50E-03 1.09E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO 4.74E-03 4.20E-03 2.50E-03 2.50E-03 1.09E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.43E-03 4.76E-03 4.76E-03 2.0SE-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO A-21

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.06E-02 1.06E-02 4.64E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.06E-02 4.64E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.35E-03 1.12E-02 l.12E-02 7.SSE-03 5.62E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.00E-02 2.00E-02 1. 34E-02 1.00E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.00E-02 l.34E-02 l.OOE-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.09E-02 2.48E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.25E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-22

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO A-23

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0 .. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-24

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO l.OOE+OO

• A-25

U-238 (n,f)

Reaction Cross-Section in FERRET Group Structure l.23E+OO 1.13E+OO 9.99E-Ol 9.85E-01 9.95E-Ol 9.91E-01 8.30E-Ol 5. 58E-Ol. 5.46E-01 5.25E-01 5.34E-Ol 5.13E-01 3.41E-Ol 5.66E-02 1. 56E-02 2.56E-03 6.86E-04 2.88E-04 l.73E-04 7.87E-05 5.93E-05 5.60E-05 5.97E-05 7.17E-05 8.54E-05 9.39E-05 9.02E-05 9.03E-05 1. 22E-06 l.OOE-35 l.OOE-35 3.41E-09 3.04E-04 8.78E-04 1. 56E-03 l.48E-05 2.09E-05 5.80E-06 5.90E-05 1. 32E-05 2.37E-05 3.19E-04 2.06E-06 l.16E-04 5.77E-06 5.90E-06 6.96E-06 8.56E-06 l.07E-05 l.46E-05 l.82E-05 2.27E-05 4.47E-05 Cross-Section Standard Deviation 8.00E-02 7.03E-02 5.95E-02 4.65E-02 3.95E-02 3.86E-02 3.75E-02 3.63E-02 3.47E-02 3.30E-02 3.15E-02 3.13E-02 5.30E-02 7.25E-02 9.41E-02 l.18E-Ol 1. 40E-Ol 2.18E-01 3.50E-01 5.48E-Ol 8.12E-Ol 1. OOE+OO 1. OOE+OO 1. OOE+OO

1. OOE+OO 1. OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO 1. OOE+OO

1. OOE+OO 1. OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO 1. OOE+OO

1. OOE+OO 1. OOE+OO l.OOE+OO 1. OOE+OO 1. OOE+OO l.OOE+OO

1. OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO 1. OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO l.OOE+OO 1. OOE+OO Lower Triangle of the 53x53 Covariance Matrix 6.41E-03 5.05E-03 4.22E-03 3.22E-03 2.64E-03 2.46E-03 2.23E-03 1.95E-03 l.60E-03 l.23E-03 9.41E-04 7.27E-04 9.21E-04 9.46E-04 8.66E-04 7.llE-04 5.54E-04 5.52E-04 5.47E-04 3.90E-04 1. BlE-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.94E-03 3.75E-03 2.BBE-03 2.39E-03 2.24E-03 2.0SE-03 1. BlE-03

1. SlE-03 l.19E-03 9.18E-04 7.19E-04 9.25E-04 9.62E-04 8.93E-04 7.46E-04 5.90E-04 5.97E-04 6.00E-04 4.37E-04 2.09E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.54E-03 2.47E-03 2.07E-03

1. 96E-03 l.BlE-03 l.63E-03 1. 38E-03 l. lOE-03 8.65E-04 6.89E-04 9.00E-04 9.SOE-04 8.97E-04 7.63E-04 6.13E-04 6.30E-04 6.44E-04 4.81E-04 2.38E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-26

• O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.16E-03 9.50E-04 O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 1.64E-03

7. 62E-04*

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.58E-03 6.lBE-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.48E-03 8.24E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. 35E-03 8.86E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.16E-03 8.53E-04 7.40E-04 6.07E-04 6.36E-04 6.63E-04 5.lOE-04 2.62E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.56E-03 1. 37E-03 l.30E-03 1. 20E-03

1. 06E-03 8.82E-04 7.21E-04 5.97E:..04 8.12E-04 8.87E-04 8.71E-04 7.73E-04 6.46E-04 6.90E-04 7.33E-04 5.BlE-04 3.lOE-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.49E-03 1. 29E-03 1. 21E-03 1.09E-03 9.29E-04 7.75E-04 6.54E-04 9.07E-04 1. .OlE-03 1.0lE-03 9.15E-04 7.BOE-04 8.50E-04 9.21E-04 7.52E-04 4.17E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO. O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. 41E-03 1.21E-03 1. llE-03 9.72E-04 8.29E-04 7.16E-04 1. 02E-03 1.15E-03 1.18E-03

l. lOE-03 9.57E-04 1.07E-03 l.18E-03 9.99E-04 5.BOE-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 1.32E-03 1.12E-03 1. OOE-03 8.78E-04 7.79E-04 l.13E-03 1.32E-03 1.38E-03 1. 32E-03 l.19E-03 1.36E-03 1. 54E-03 1.35E-03 8.28E-04 O.OOE+OO O.OOE+OO O.OOE+OO o:ooE+oo O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. 21E-03 1. OlE-03 9.15E-04 8.38E-04 1. 26E-03 1.51E-03

1. 64E-03 l.62E-03 1.50E-03 1. 77E-03 2.0BE-03 1.92E-03

1. 25E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO

• A-27

O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.09E-03 9.19E-04 8.73E-04

1. 36E-03 1.68E-03 1. 89E-03 l.95E-03 l.87E-03 2.29E-03 2.79E-03 2.71E-03 1. 90E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 9.90E-04 8.73E-04 l.41E-03 l.79E-03 2.0BE-03 2.22E-03 2.20E-03 2.79E-03 3.SOE-03 3.SBE-03 2.68E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.83E-04 1.47E-03 l.93E-03 2.32E-03 2.56E-03 2.62E-03 3.43E-03 4.46E-03 4.78E-03 3.82E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.BlE-03 3.41E-03 4.23E-03 4.86E-03 5 .13E-03 6.93E-03 9.30E-03 l.OSE-02 8.93E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 5.25E-03 6.04E-03 7.16E-03 7.78E-03 1. OBE-02 l.SOE-02 l.76E-02 l.59E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.86E-03 9.79E-03 l.lOE-02 l.SBE-02 2.26E-02 2.79E-02 2.69E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. 39E-02 1. 46E-02 2.17E-02 3.21E-02 4.19E-02 4.34E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.95E-02 2.70E-02 4.12E-02 5.64E-02

• A-28

• 6.24E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

0. OOE+OO*

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.76E-02 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 6.77E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.73E-02 l.lSE-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.23E-Ol 1. 67E-Ol 2.lOE-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO. O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.0lE-01 3.76E-01 O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO 6.60E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0 .'OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-29

O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO* O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+0.0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

• A-30

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 0. OOE+OO. O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.OOE+OO O.OOE+OO O.OOE+OO O.OOE+'OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.00E+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. OOE+OO O.OOE+OO O.OOE+OO

1. OOE+OO O.OOE+OO 1. OOE+OO

• A-31

Np-237 (n, f)

Reaction Cross-Section in FERRET Group Structure 2.22E+OO 2.13E+OO 2.0SE+OO 2.llE+OO 2.18E+OO 2.24E+OO l.96E+OO i. 49E+oo- l.54E+OO 1. 62E+OO 1. 67E+OO l.67E+OO

1. 60E+OO 1. 50E+OO 1. 37E+OO 1. 07E+OO 6.45E-01 2.83E-01 l.06E-01 4.55E-02 2.30E-02 1. 48E-02 l.lBE-02 l.05E-02 9.75E-03 9.50E-03 9.19E-03 8.78E-03 8.83E-03 9.32E-03 l.04E-02 7.54E-03 l.23E-02 l.46E-02 l.lSE-02 1.89E-02 4.55E-02 2.04E-02 2.48E-03 1. 27E-01 5.36E-02 l.49E-03 3.68E-03 l.04E-02 6.21E-03 1. 34E-03 1. 33E-02 1. 61E-03 l.49E-02 4.33E-03 5.61E-03 7.53E-03 1. 68E-02 Cross-Section Standard Deviation

1. 54E-01 1. 48E-01 1. 42E-01 l.34E-Ol l.27E-01 l.20E-01 1.12E-01 l.03E-01 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 9.90E-02 1. 02E-01 1. lSE-01 l.28E-01 1. 50E-01 l.SOE-01 2.llE-01 2.42E-01 3.13E-01 3.07E-01 3.03E-01 2.97E-Ol 2.89E-01 2.BlE-01 2.76E-01 2.73E-01 2.71E-01 2.66E-01 2.58E-Ol 2.50E-01 2.43E-Ol 2.35E-01 2.28E-01 2.22E-01 2.19E-01 2.16E-01 2.12E-01 2.09E-01 2.06E-01 2.03E-01 2.00E-01 1.97E-01 1. 94E-01 l.90E-01 l.87E-01 1. 84E-01 1.BlE-01 1.00E-01 Lower Triangle of the 53x53 Covariance Matrix 2.36E-02 2.09E-02 1.99E-02 1. 86E-02 1. 72E-02 1. 58E-02

1. 42E-02 1. 24E-02 1. llE-02 l.02E-02 9.39E-03 8.61E-03 7.90E-03 7.32E-03 6. 77E-03 6.27E-03 5.96E-03 5.83E-03 5.67E-03 5.43E-03 5.lBE-03 5.03E-03 4.95E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.19E-02 1.93E-02 1. BlE-02 1. 69E-02 1.56E-02 1. 40E-02 1. 23E-02 1.llE-02 1.03E-02 9.52E-03 8.76E-03 8.0SE-03 7.47E-03 6.91E-03 6.39E-03 6.07E-03 5.93E-03 5.76E-03 5.50E-03 5.23E-03 5.0SE-03 4.96E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.00E-02 1.75E-02 1. 64E-02 1.52E-02 l.38E-02 1.22E-02 1.llE-02 1.04E-02 9.63E-03 8.90E-03 8.21E-03 7.63E-03 7.0SE-03 6.52E-03 6.lSE-03 6.0SE-03 5.87E-03 S.59E-03 S.28E-03 S.09E-03 4.98E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO A-32

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.80E-02 l.57E-02 1. 47E-02 l.35E-02 l.20E-02 l.lOE-02 l.04E-02 9. 70E 9.02E-03 8.36E-03 7.79E-03 7.21E-03 6.66E-03 6.32E-03 6.19E-03 6.0lE-03 5.71E-03 5.36E-03 5.13E-03 5.-00E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. 61E-02 1. 41E-02 1. 30E-02 l. l 7E-02 l.08E-02 l.03E-02 9.70E-03 9.09E-03 8.46E-03 7.92E-03 7.35E-03 6.80E-03 6.45E-03 6.33E-03 6.15E-03 5.83E-03 5.44E-03 5.18E-03 5.03E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.43E-02 1. 24E-02 l.13E-02 l.06E-02 1. OlE-02 9.63E-03 9.09E-03 8.51E-03 8.00E-03 7.46E-03 6.91E-03 6.57E-03 6.46E-03 6.28E-03 5.95E-03 5.53E-03 5.23E-03 5.05E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.25E-02 1. OBE-02 l.02E-02 9.85E-03 9.46E-03 9.00E-03 B.50E-03 B.03E-03 7.53E-03 7.0lE-03 6.68E-03 6.59E-03 6.42E-03 6.09E-03 5.64E-03 5.30E-03 5.09E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.06E-02 9.59E-03 9.40E-03 9.13E-03 B.78E-03 B.37E-03 7.98E-03 7.53E-03 7.05E-03 6.75E-03 6.70E-03 6.55E-03 6.22E-03 5.76E-03 5.39E-03 5.14E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.BOE-03 9.25E-03 9.08E-03 8.83E-03 B.50E-03 B.16E-03 7.76E-03 7.30E-03 7.02E-03 7.00E-03 6.8BE-03 6.54E-03 6.02E-03 S,S6E-03 5.25E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO

• A-33

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.SOE-03 9.26E-03 9.lOE-03 8.86E-03 8.57E-03 8.20E-03 7.76E-03 7.48E-03 7.54E-03 7.44E-03 7.lOE-03 6.48E-03 5.89E-03 5.45E-03 O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.SOE-03 9.26E-03 9.lOE-03 8.88E-03 8.57E-03 8.16E-03 7.92E-03 8.06E-03 8.02E-03 7.70E-03 7.0lE-03 6.29E-03 5.71E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO. O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO 9.SOE-03 9.26E-03 9.12E-03 8.88E-03 8.54E-03 8.35E-03 8.60E-03 8.64E-03 8.39E-03 7.66E-03 6.SOE-03 6.06E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.SOE-03 9.27E-03 9.12E-03 8.86E-03 8.75E-03 9.13E-03 9.28E-03 9.13E-03 8.41E-03 7.44E-03 6.52E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.SOE-03 9.26E-03 9.0SE-03 9.06E-03 9.57E-03 9.84E-03 9.83E-03 9.17E-03 8.13E-03 7.0SE-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.SOE-03 9.25E-03 9.33E-03 9.99E-03 1. 04E-02 1. 06E-02 l.OlE-02 9.02E-03 7.78E-03 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.BOE-03 9.SlE-03 1.03E-02 l.lOE-02 l.14E-02 1.12E-02 1.0lE-02 8.76E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.04E-02 1. 09E-02 l.17E-02 l.25E-02

• A-34

l.26E-02 l.16E-02 1. OlE-02 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO* O.OOE+OO l.31E-02 l.36E-02 l.49E-02 l.55E-02 1. 46E-02 l.28E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO l.64E-02 l.73E-02 l.87E-02 l.82E-02 l.63E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.24E-02 2.37E-02 2.44E-02 2.28E-02 O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.23E-02 3.31E-02 3.34E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.44E-02 4.44E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.87E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.79E-02 7.59E-02 7.31E-02 6.74E-02 5.82E-02 4.BOE-02 4.lOE-02 3.76E-02 3.44E-02 2.82E-02 2.0lE-02 l.36E-02 8.84E-03 5.45E-03 3.21E-03 l.BlE-03 9.89E-04 5.14E-04 2.55E-04 1. 21E-04 5.44E-05 2.34E-05 9.60E-06 3.76E-06 l.40E-06 4.99E-07 1. 69E-07 5.47E-08 1.69E-08 4.00E-15 9.43E-02 7.40E-02 7.00E-02 6.26E-02 5.33E-02 4.67E-02 4.33E-02 4.00E-02 3.35E-02 2.47E-02 1. 74E-02 l. l 7E-02 7.44E-03 4.53E-03 2.65E-03 l.49E-03 8.04E-04 4.13E-04 2.02E-04 9.42E-05 4.19E-05 l.78E-05 7.20E-06 2.78E-06 l.02E-06 3.59E-07 1.20E-07 3.84E-08 1. 28E-14 9.lBE-02 7.09E-02 6.50E-02 5.68E-02 5.05E-02 4.73E-02 4.40E-02

• A-35

3.75E-02 2.84E-02 2.05E-02 1. 41E-02 9.21E-03 5.74E-03 3.45E-03 l.99E-03 l. lOE-03 5.79E-04 2.90E-04 1. 39E-04 6.34E-05 2.76E-05 1.14E-05 4.53E-06 l.71E-06 6.15E-07 2.llE-07 6.91E-08 2.97E-14 8.BlE-02 6.70E-02 6.0SE-02 5.54E-02 5.25E-02 4.95E-02 4.32E-02 3.39E-02 2.54E-02 l.SlE-02 1. 23E-02* 7.95E-03 4.95E-03 2.97E-03 l.70E-03 9.28E-04 4.83E-04 2.40E-04 l.14E-04 5.13E-05 2.21E-05 9.07E-06 3.55E-06 l.33E-06 4.72E-07 l.60E-07 l.OOE-13 8.35E-02 6.35E-02 5.98E-02 5.75E-02 5.51E-02 4.97E-02 4.09E-02 3.20E-02 2.39E-02 1. 71E-02 l.16E-02 7.56E-03 4.75E-03 2.85E-03 1. 63E-03 8.91E-04 4.63E-04 2.30E-04

1. 09E-04 4.92E-05 2.12E-05 8.69E-06 3.40E-06 l.27E-06 4.52E-07 4.56E-13 7.91E-02 6.14E-02 6.0lE-02 5.84E-02 5.44E-02 4.69E-02 3.86E-02 3.02E-02 2.26E-02 1. 61E-02

l. lOE-02 7.25E-03 4.56E-03 2.73E-03 l.56E-03 8.54E-04 4.44E-04 2.20E-04 l.04E-04 4. 71E-05 2.03E-05 8.31E-06 3.25E-06 l.21E-06 l.98E-12 7.62E-02 6.02E-02 5.92E-02 5.62E-02 5.0lE-02 4.25E-02 3.44E-02 2.65E-02 1. 94E-02 1.37E-02 9.35E-03 6.07E-03 3.76E-03 2.22E-03 l.25E-03 6.71E-04 3.43E-04 1. 68E-04 7.BlE-05 3.47E-05 l.47E-05 5.94E-06 2.29E-06 5.13E-12 7.48E-02 5.91E-02 5.67E-02 5.13E-02 4.42E-02 3.63E-02 2.85E-02 2.12E-02 1. 52E-02

1. 05E-02 6.95E-03 4.37E-03 2.62E-Ol 1. 50E-03 8.17E-04 4.25E-04 2.llE-04 9.98E-05 4.50E-05 l.94E-05 7.95E-06

3. llE-06 8.19E-12 7.33E-02 5.70E-02 5.23E-02 4.58E-02 3.82E-02 3.04E-02 2.31E-02 l.68E-02 l.lSE-02 7.91E-03 5.05E-03 3.0SE-03 l.79E-03 9.91E-04 5.24E-04 2.64E-04 l.27E-04 5.82E-05 2.54E-05 1. 06E-05 4.21E-06 1. 30E-11 7.06E-02 5.35E-02 4.84E-02 4.17E-02 3.42E-02 2.68E-02 2.0lE-02 1. 46E-02 l.OlE-02 6.65E-03 4.lBE-03 2.51E-03 l.43E-03 7.82E-04 4.07E-04 2.02E-04 9.55E-05 4.31E-05 l.85E-05 7.60E-06 3.23E-11 6.65E-02 5.04E-02 4.55E-02 3.92E-02 3.21E-02 2.54E-02 l.93E-02 1. 40E-02 9.65E-03 6.36E-03 4.00E-03 2.40E-03 l.37E-03 7.48E-04 3.89E-04 l.93E-04 9.12E-05 4.12E-05 1. 77E-05 1. 22E-10 6.26E-02 4.74E-02 4.28E-02 3.68E-02 3.04E-02 2.43E-02 1. 84E-02 l.34E-02 9.23E-03 6.0SE-03 3.82E-03 2.29E-03 1. 31E-03 7.15E-04 3.72E-04 1. 84E-04 8. 71E-05 3.93E-05 4.38E-10 5.89E-02 4.46E-02 4.02E-02 3.48E-02 2.91E-02 2.32E-02

1. 76E-02 1. 28E-02 8.82E-03 5.SlE-03 3.65E-03 2.19E-03 1.25E-03 6.82E-04 3.55E-04 l.76E-04 8.31E-05 1. 50E-09 5.53E-02 4.lSE-02 3.SOE-02 3.33E-02 2.78E-02 2.21E-02

1. 68E-02 1.22E-02 8.41E-03 5.54E-03 3.48E-03 2.09E-03 l.19E-03 6.51E-04 3.38E-04 1. 68E-04 4.91E-09 5.lSE-02 3.95E-02 3.62E-02 3.17E-02 2.65E-02 2.llE-02 1. 60E-02 1.16E-02 8.02E-03 5.29E-03 3.32E-03 l.99E-03 1.14E-03 6.20E-04 3.22E-04 1. 53E-08 4.93E-02 3.BOE-02 3.49E-02 3.05E-02 2.55E-02 2.03E-02 1. 54E-02 l.12E-02 7. 71E-03 5.0SE-03 3.19E-03 1.91E-03 1. 09E-03 5.95E-04 4.56E-08 4.79E-02 3.69E-02 3.38E-02 2.96E-02 2.47E-02 1. 97E-02 A-36

• l.SOE-02 1.06E-03 2.40E-02 3.00E-03 2.79E-02 4.62E-03 1.0BE-02

1. 29E-07 1.91E-02 1.79E-03 2.33E-02

2. 90E-03*

7.48E-03 4.65E-02

1. 45E-02 3.SlE-07 1.BSE-02 9.06E-07 4.92E-03 3.SBE-02 1.0SE-02 4.SlE-02

1. 41E-02 4.38E-02

3. 09E.- 03 3.28E-02 7.25E-03 3.47E-02 1.02E-02 3.37E-02 1.BSE-03 2.87E-02 4.77E-03 3.19E-02 7.02E-03 3.09E-02 2.70E-02 2.26E-02 1.BOE-02 1.36E-02 9.86E-03 6.BlE-03 4.48E-03 2.23E-06 4.25E-02 3.27E-02 3.00E-02 2.62E-02 2.19E-02 1.74E-02 1. 32E-02 9.SSE-03 6.59E-03 5.25E-06 4.12E-02 3.17E-02 2.90E-02 2.54E-02 2.12E-02 1.69E-02 1.28E-02 9.25E-03 1.lBE-05 3.99E-02 3.07E-02 2.BlE-02 2.46E-02 2.0SE-02 1.63E-02 1. 24E-02 2.52E-05 3.87E-02 2.97E-02 2.73E-02 2.38E-02 1.99E-02 l.SBE-02 5.14E-05 3.75E-02 2.BBE-02 2.64E-02 2.31E-02 1.92E-02 1.00E-04 3.63E-02 2.79E-02 2.56E-02 2.23E-02 1. 86E-04 3.SlE-02 2.70E-02 2.47E-02 3.30E-04 3.40E-02 2.61E-02 5.57E-04 3.29E-02 8.98E-04 1.00E-02 A-37

Co-59 (n,y)

Reaction Cross-Section in FERRET Group Structure 6.79E-04 8.83E-04 7.83E-04 6.48E-04 6.41E-04 7.28E-04 9.40E-04 l .19E-03* l.58E-03 2.llE-03 2.61E-03 3.24E-03 4.22E-03 5.80E-03 6.45E-03 6.63E-03 7.07E-03 7.79E-03 8.77E-03 l.lOE-02 1. 57E-02 l.29E-02 1. 46E-02 2.84E-02 2.94E-02 4.90E-02 5.00E-02 5.44E-02 2.28E-Ol l.31E-01 4.18E-02 9.79E-03 2.03E-02 1. 49E-02 3.56E-02 1. 32E-01 l.38E+OO l.12E+02 3.89E+OO l.84E+OO l.64E+OO l.76E+OO 2.06E+OO 2.51E+OO 3.13E+OO 3.95E+OO 5.02E+OO 6.41E+OO 8.20E+OO l.13E+Ol l.42E+Ol l.77E+Ol 3.50E+Ol Cross-Section Standard Deviation 8.66E-Ol 8.00E-01 7.28E-01 6.41E-01 5.53E-Ol 4.66E-01 3.64E-01 2.97E-01 2.88E-Ol 2.78E-01 2.70E-Ol 2.61E-01 2.52E-01 2.44E-01 2.35E-Ol 2.26E-01 2.17E-Ol 2.08E-Ol l.99E-01 l.86E-01 l.68E-Ol l.51E-Ol l.43E-Ol l.37E-01 l.32E-01 l.28E-01 l.22E-Ol l.15E-01 l.08E-Ol l.04E-01 l.02E-01 9.92E-02 9.46E-02 8.76E-02 8.07E-02 7.37E-02 6.68E-02 6.00E-02 5.87E-02 5.75E-02 5.63E-02 5.51E-02 5.39E-02 5.26E-02 5.14E-02 5.02E-02 4.90E-02 4.78E-02 4.65E-02 4.53E-02 4.41E-02 4.29E-02 3. llE-02 Lower Triangle of the 53x53 Covariance Matrix 7.50E-01 5.53E-01 4.99E-Ol 4.31E-01 3.63E-Ol 2.95E-01 2.19E-01 l.65E-01 l.43E-Ol l.19E-Ol 9.73E-02 7.79E-02 6.08E-02 4.76E-02 3.54E-02 2.48E-02 1. 75E-02 l.20E-02 8.04E-03 4.19E-03 l.60E-03 5.50E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 6.41E-01 4.65E-01 4.04E-01 3.42E-01 2.80E-01 2.09E-Ol l.60E-01 l.40E-01 l.17E-01 9. 72E-02 7.86E-02 6.20E-02 4.91E-02 3.69E-02 2.62E-02 l.86E-02 1. 29E-02 8.75E-03 4.64E-03 l.81E-03 6.37E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.30E-01 3. 71E-Ol 3.17E-01 2.61E-Ol 1. 97E-01 1. 52E-01 1. 34E-Ol l.14E-Ol 9.58E-02 7.84E-02 6.26E-02 5.00E-02 3.81E-02 2.74E-02 1. 97E-02

1. 39E-02 9.50E-03 5.13E-03 2.05E-03 7.38E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO

• A-38

O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO O.OOE+OO 4.lOE-01 2.82E-01 2.35E-01 1.79E-01 1.39E-01 1.25E-01

1. OBE-01 9.21E-02* 7.65E-02 6.20E-02 5.02E-02 3.87E-02 2.83E-02 2.07E-02 1. 48E-02 1. 03E-02 5.65E-03 2.33E-03 8.63E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.06E-01 2.0SE-01 1.SBE-01 1.25E-01 1.14E-01 9.96E-02 8.61E-02 7.26E-02 5.97E-02 4.90E-02 3.83E-02 2.BSE-02 2. llE-02 l.53E-02 1.0BE-02 6.07E-03 2.SBE-03 9.BlE-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO 2.17E-01 1.35E-01 1.0BE-01 9.96E-02 8.88E-02 7.79E-02 6.66E-02 5.56E-02 4.62E-02 3.67E-02 2.77E-02 2.08E-02 1.53E-02 l.09E-02 6.30E-03 2.75E-03 1.08E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1. 33E-01 8.59E-02 8.08E-02 7.33E-02 6.54E-02 5.69E-02 4.83E-02 4.07E-02 3.29E-02 2.53E-02 1. 94E-02 1. 45E-02 l.OSE-02 6.21E-03 2.BlE-03 l.14E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.BlE-02 6.76E-02 6.27E-02 5.70E-02 5.06E-02 4.37E-02 3.75E-02 3.09E-02 2.43E-02 l.90E-02 l.44E-02 1.07E-02 6.SOE-03 3.0SE-03 1.29E-03 O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 8.30E-02 6.32E-02 5.89E-02 5.35E-02 4.74E-02 4.16E-02 3.SlE-02 2.83E-02 2.26E-02 1.76E-02 1. 34E-02 8.45E-03 4.16E-03 1.84E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO A-39

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.75E-02 5.93E-02 5.53E-02 5.03E-02 4.52E-02 3.92E-02 3.25E-02 2.67E-02 2.14E-02

1. 67E-02 1.09E-02 5.69E-03 2.65E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0. OOE+OO* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.27E-02 5.56E-02 5.18E-02 4.75E-02 4.22E-02 3.60E-02 3.03E-02 2.48E-02 1. 98E- 02 1. 35E-02 7.36E-03 3.60E-03 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.BOE-02 5.19E-02 4.87E-02 4.43E-02 3.88E-02 3.34E-02 2.SlE-02 2.30E-02 1.62E-02 9.28E-03 4.77E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.35E-02 4.87E-02 4.54E-02 4.08E-02 3.60E-02 3.lOE-02 2.60E-02 1.90E-02 1.14E-02 6.16E-03 O.OOE+OO 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.95E-02 4.54E-02 4.17E-02 3.77E-02 3.31E-02 2.84E-02 2.lSE-02 l.35E-02 7.SSE-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.53E-02 4.lSE-02 3.87E-02 3.48E-02 3.06E-02 2.40E-02 1. SSE-02 9.32E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.09E-02 3.86E-02 3.57E-02 3.22E-02 2.63E-02 1. 82E-02 1.14E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.70E-02 3.56E-02 3.29E-02 2.78E-02 A-40

• 2.02E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.32E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

0. OOE+OO*

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.32E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.27E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.87E-02 2.19E-02 1.SOE-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.96E-02 2.88E-02 2.31E-02 1.67E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.45E-02 2.38E-02 l.85E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.83E-02 1.93E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.27E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.0SE-02

1. 53E-02 1. 41E-02 1.30E-02 1. 14E-02 9.08E-03 6.90E-03 5.58E-03 4.98E-03 4.42E-03 3.42E-03 2.22E-03 1.37E-03 8.00E-04 4.41E-04 2.31E-04 1.25E-04 6.49E-05 3.21E-05 1.SlE-05 6.78E-06 2.91E-06 1.19E-06 4.62E-07 1. 71E-07 6.06E-08 2.04E-08 6.58E-09 2.02E-09 5.89E-10 3.58E-16 1.86E-02 1. 42E-02 1. 35E-02 1.21E-02 1.02E-02 8.08E-03 6.74E-03 6. llE-03 5.50E-03 4.38E-03 2.99E-03 1. 93E-03 1.18E-03 6.80E-04 3.72E-04 2.12E-04 1. lSE-04 5.94E-05 2.93E-05 1.38E-05 6.17E-06 2.64E-06 1.07E-06 4.17E-07 1.SSE-07 5.46E-08 1. 84E-08 5.89E-09 1.80E-09 1.70E-15 1.73E-02 1.34E-02 1. 24E-02 1.07E-02 8.82E-03 7.53E-03 6.90E-03 6.28E-03 5.12E-03 3.61E-03 2.41E-03 1.52E-03 9.lOE-04 5.15E-04 3.03E-04 1.70E-04 9.09E-05 4.64E-05 2.26E-05 1.05E-05 4.63E-06 1. 95E-06 7.84E-07 3.00E-07 1.lOE-07 3.82E-08 1.27E-08 4.0lE-09 5.25E-15 1.63E-02 1.23E-02 1.lOE-02 9.25E-03 8.03E-03 7.42E-03 6.81E-03

• A-41

5.64E-03 4.0BE-03 2.79E-03 1. BlE-03 l. llE-03 6.43E-04 3.BBE-04 2.23E-04 1. 22E-04 6.41E-05 3.19E-05 l.52E-05 6.89E-06 2.98E-06 l.23E-06 4.82E-07 l.BOE-07 6.44E-08 2.19E-08 7.llE-09 1. lBE-14 l.50E-02 l.lOE-02 9.67E-03 8.60E-03 8.04E-03 7.48E-03 6.35E-03 4.76E-03 3.38E-03 2.27E-03 1. 45E-03* 8.70E-04 5.44E-04 3.25E-04 1.85E-04 l.OOE-04 5.19E-05 2.56E-05 1.20E-05 5.40E-06 2.31E-06 9.41E-07 3.66E-07 l.35E-07 4.78E-08 l.61E-08 3.82E-14 1.33E-02 9.79E-03 8.99E-03 8.53E-03 8.06E-03 7.07E-03 5.55E-03 4.13E-03 2.91E-03 1. 94E-03 l.22E-03 8.Q4E-04 5.03E-04 3.00E-04 l.71E-04 9.26E-05 4.79E-05 2.36E-05 l.llE-05 4.97E-06 2.12E-06 8.65E-07 3.36E-07 1.24E-07 4.39E-08 l.64E-13 l.lBE-02 8.92E-03 8.61E-03 8.26E-03 7.47E-03 6.15E-03 4.BOE-03 3.55E-03 2.48E-03 1.64E-03 l.13E-03 7.40E-04 4.63E-04 2.76E-04 1.57E-04 8.50E-05 4.39E-05 2.17E-05 l.02E-05 4.56E-06 l.95E-06 7.92E-07 3.07E-07 1.14E-07 6.68E-13 l.OBE-02 8.41E-03 8.16E-03 7.54E-03 6.40E-03 5.16E-03 3.93E-03 2.84E-03 l.94E-03 l.37E-03 9.30E-04 6.00E-04 3.69E-04 2.17E-04 1.21E-04 6.46E-05 3.29E-05 1.59E-05 7.36E-06 3.24E-06 l.36E-06 5.46E-07 2.0BE-07 1. 66E-12 l.03E-02 8.04E-03 7.50E-03 6.48E-03 5.30E-03 4.llE-03 3.0lE-03 2.0SE-03 l.50E-03 1.03E-03 6.78E-04 4.24E-04 2.52E-04 1. 43E-04 7.77E-05 4.0lE-05 l.98E-05 9.28E-06 4.15E-06 l.77E-06 7.21E-07 2.BOE-07 2.59E-12 9.85E-03 7.43E-03 6.51E-03 5.41E-03 4.26E-03 3.17E-03 2.23E-03 1. 64E-03 l.14E-03 7.61E-04 4.83E-04 2.92E-04 1. 69E-04 9.29E-05 4.BBE-05 2.44E-05 1.16E-05 5.29E-06 2.29E-06 9.47E-07 3.73E-07 4.02E-12 8.95E-03 6.48E-03 5.55E-03 4.51E-03 3.46E-03 2.52E-03 l.90E-03 1.37E-03 9.42E-04 6.17E-04 3.86E-04 2.30E-04 1.31E-04 7.07E-05 3.65E-05 l.BOE-05 8.43E-06 3.77E-06 l.61E-06 6.53E-07 9.52E-12 7.68E-03 5.52E-03 4.70E-03 3.78E-03 2.BBE-03 2.28E-03 1. 73E-03 1. 24E-03 8.54E-04 5.59E-04 3.49E-04 2.0BE-04 1. lBE-04 6.39E-05 3.30E-05 l.62E-05 7.60E-06 3.40E-06 1.45E-06 3.32E-11 6.51E-03 4.65E-03 3. 92E-03 3.13E-03 2.60E-03 2.06E-03 1.56E-03 l.12E-03 7.69E-04 5.03E-04 3.14E-04 1.87E-04 1. 06E-04 5.73E-05 2.96E-05 1. 45E-05 6.BlE-06 3.04E-06 l. lOE-10 5.43E-03 3.84E-03 3.22E-03 2.BOE-03 2.33E-03* 1. 84E-03 1.39E-03 l.OOE-03 6.87E-04 4.49E-04 2.BOE-04 1. 67E-04 9.45E-05 5.llE-05 2.63E-05 l.29E-05 6.05E-06 3.45E-10 4.46E-03 3.13E-03 2.85E-03 2.48E-03 2.06E-03 l.63E-03

1. 23E-03 8.86E-04 6.07E-04 3.97E-04 2.48E-04 1. 47E-04 8.34E-05 4.50E-05 2.32E-05 l.14E-05 l.02E-09 3.60E-03 2.75E-03 2.51E-03 2.18E-03 1.SlE-03 1. 43E-03 l.OSE-03 7.77E-04 5.33E-04 3.48E-04 2.17E-04 1.29E-04 7.29E-05 3.94E-05 2.03E-05 2.86E-09 3.45E-03 2.64E-03 2.41E-03 2.09E-03 1.74E-03 1.37E-03 l.03E-03 7.43E-04 5.09E-04 3.33E-04 2.07E-04 l.23E-04 6.95E-05 3.75E-05 8.34E-09 3.31E-03 2.53E-03 2.31E-03 2.00E-03 1.66E-03 1.31E-03

• A-42

• 9.89E-04 6.62E-05 1.59E-03 1.88E-04

1. 83E-03 2.88E-04 7.lOE-04 2.32E-08

1. 25E-03 1.llE-04 1.52E-03

1. 79E-04.

4.86E-04 3.17E-03 9.44E-04 6.lSE-08 1.20E-03 1.SSE-07 3.17E-04 2.42E-03 6.78E-04 3.03E-03 9.0lE-04 2.90E-03

1. 97E-04 2.21E-03 4.64E-04 2.32E-03 6.46E-04 l.17E-04 l.92E-03 3.02E-04 2.llE-03 4.42E-04 2.22E-03 2.02E-03 1.75E-03 1. 45E-03 1.14E-03 8.58E-04 6.lSE-04 4.20E-04 2.74E-04 3.75E-07 2.77E-03 2.12E-03 1.92E-03 1.67E-03 1.38E-03 1.09E-03 8.17E-04 S.85E-04 3.99E-04 8.61E-07 2.64E-03 2.02E-03 1. 83E-03 1.59E-03 1.31E-03 1. 03E-03 7.77E-04 S.56E-04 1.89E-06 2.52E-03 1.92E-03 1.75E-03 1.SlE-03 1.25E-03 9.83E-04 7.37E-04 3.94E-06 2.40E-03 1.83E-03 1. 66E-03 1.44E-03 l.19E-03 9.32E-04 7.84E-06 2.28E-03 1.74E-03 1.58E-03 1.36E-03 1.12E-03 1.49E-OS 2.17E-03 1.65E-03 1.49E-03 1. 29E-03 2.70E-05 2.0SE-03 I I

1.56E-03 1. 42E-03 4.65E-05 1.95E-03 1.48E-03 7.65E-05 I 1.84E-03 1. 20E-04 9.70E-04 -1 I

I

• A-43

• 2. Dosimeter Discrepancies. The staffnoted that the high and low energy dosimeter readings imply a different calculational bias; the high energy dosimeters indicate an MIC of approximately 1.0 while the low energy dosimeters indicate an MIC of approximately 0.83.

However, the staff cannot identify a physical reason for these differences. Please identify and discuss the physical basis for the difference between the bias inferredfrom the high and low energy dosimeters.

The reason for the difference in the bias between high and low energy dosimetry most likely comes from the calculations. There probably is no physical basis. The most likely source of this difference is the accuracy of the calculational cross-sections and the source spectrum. The high energy neutrons in a calculation basically represent the uncollided flux at the locations of interest. These neutrons have undergone very few interactions which provides less opportunity for even small errors in the cross-section data base to have an impact on this portion of the calculation. This is a simpler calculation than what is necessary to accurately calculate the neutron flux at lower energies. At lower energies the neutrons have experienced significantly more interactions and errors in the cross-sections will be more evident. This is taken to the extreme when you try to calculate the flux at thermal energies. It is not surprising that a calculation will exhibit.a different level of accuracy when you compare the results of high and low energy fluxes.

Although the cross-section database has been improved, it still contains uncertainty. As previously presented, the difference between the high and low energy fluxes has been observed in other calculations, including the bench marking calculations used to evaluate the DORT calculational methodology. These differences are of the same magnitude as those seen at Palisades, however they are not necessarily 0.83 and 1.00. These biases can be shifted. This shift is most likely a response to the accuracy of the source spectrum and modeling of the problem.

The observed differences in the response of the high threshold reactions from the Palisades plant specific data base are consistent with observations from extensive measurements taken from other pressurized water reactors; and is most probably caused by uncertainties in the high energy portion of the fission spectrum used to compute the core neutron source for input to the analysis.

Information on this topic has been supplied in response to previous RAI's. For completeness, that prior information will be repeated here.

The following discussion was provided in response to the RAI's generated at the 02/26/97 technical meeting between the NRC staff and Consumers Energy (Submitted June 26, 1997, Attachment 1, pp.

14-20) .

• 2-1

Issue 2: Where Does the Observed Spectrum Bias Come From?

An examination of [M]/[C] ratios for each of the foil reactions comprising the multiple foil sensor sets used by Westinghouse shows that the observed ratios for individual reactions differ from the overall average [M]/[C] ratio for all reactions by approximately+/- 8%. This observation is illustrated by the data comparisons shown in Table 2-1. For ease of comparison, the data provided in Table 2-1 have been normalized to an unweighted average of 1.00 for the six foil reactions. The normalized data allows for comparisons among data sets to observe similar spectral variations. The Palisades data is presented in Table 2-2.

This variation in Palisades' normalized [M]/[C] ratios for individual reaction rates are consistent with the 8% standard deviation associated with the overall data base average, but, nevertheless, indicates that the ratio of measurement to calculation varies somewhat with energy. That is, the measured data indicate that, in addition to an observed bias in th.e overall magnitude of the calculations, small variations in the calculated vs. Measured energy distribution also exist; i.e.

spectral variations.

Spectral variations in [M]/[C] ratios similar to those observed in the Westinghouse data base have

• also been reported elsewhere. The following references contain data that indicate that spectral mismatches between calculation and experiment have been observed in a fairly wide variety of applications:

1- Williams, M. L., et. al., "Transport Calculations of Neutron Transmission Through Steel Using ENDF/B-V, Revised ENDF/B-V, and ENDF/B-VI Iron Evaluations," Ann. Nucl. Energy, Vol. 18, No. 10, pp. 549-565, (1991).

2- Sajo, E. et.al., "Comparison of Measured and Calculated Transmission Through Steel for a Cf-252 Source," Ann. Nucl. Energy, Vol. 20, No. 9, pp.

585-604, (1993).

3- Sajo, E., et. al., "Pressure Vessel Neutron Spectrum Analysis of the Czech LRO/VVER-440 Benchmark Experiment," Proceedings of the ANS 1996 Topical Meeting on Radiation Protection and Shielding, pp. 181-188, N.

Falmouth, Massachusetts, (April 1996).

2-2

4- Bevilaqua, A., et. al., "Special Dosimetry at Saint Laurent B 1 MOX-Loaded Unit," Proceedings of the Eighth ASTM-Euratom Symposium on Reactor Dosimetry, pp. 132-139, Vail, Colorado, September 1993.

5- Remec, I. and Kam, F. B. K., "H. B. Robinson-2 Pressure Vessel Benchmark," NUREG/CR-6453, to be published.

In References I, 2, and 3 listed above, detailed comparisons of calculated and measured energy spectra are provided for several evaluations involving deep penetration in steel. In all cases, the differences betWeen calculation and measurement varied with neutron energy. In Reference 2, the following summary conclusion was noted:

"The results obtained in this study appear to indicate that the ENDF/B-VI cross-sections will not entirely resolve the spectrum discrepancies observed in the energy interval above 1.0 MeV."

"The discrepancies could indicate that further refinement is needed in the iron cross-section and/or the Cf-252 fission spectrum" The data comparisons provided in References 4 and 5 listed above are characteristic of pressurized water reactor systems similar to those comprising the Westinghouse dosimetry data base and are provided in Tables 2-3 and 2-4, respectively.

The comparisons of Reference 4 are based on a collaborative set of measurements and calculations performed by Commissariat a l'Energie Atomique and Electricite' de France for the french reactor at Saint Laurent and include data from both in-vessel surveillance capsule and ex-vessel dosimetry sets.

The data comparisons from Reference 5 are based on measurements and calculations at both in-vessel and ex-vessel locations performed in support of the NRC sponsored Light Water Reactor Surveillance Dosimetry Improvement Program (LWR-PVSDIP). The data from Reference 5 is cited as a suitable benchmark in DG-1053, "Calculational and Dosimetry Methods for Determining Pressure Vessel Fluence."

A comparison of normalized [M]/[C] comparisons from References 4 and 5 with those observed in the Westinghouse dosimetry data base is provided in Table 2-5 .

• 2-3

From Table 2-5, it is evident that the spectral variations observed in the Westinghouse dosimetry data base are also evident in both the St Laurent and H. B. Robinson comparisons. It may also be noted that the St. Laurent and H.B. Robinson comparisons fall within 1 standard deviation of the data base average values.

A comparison of the overall Westinghouse data base with the Palisades plant specific normalized

[M]/[C] data is also illustrative. This comparison is provided in Table 2-6.

The comparisons shown in Table 2-6 show that, like St. Laurent and H. B. Robinson, the Palisades plant specific dosimetry data base exhibits similar trends (Fe and Ni ratios lower than other reactions) and is statistically compatible with the overall Westinghouse dosimetry data base.

In attempting to determine the cause of the observed discrepancies in the calculated and measured normalized neutron energy distributions, it is important to recall that the calculations involve assumptions regarding the energy spectrum of the neutron source as well as assumptions related to -

processing basic cross-section data from the ENDF/B-VI data files to the multi-group structures characteristic of the transport calculations.

In terms of the source spectrum, two factors can combine to produce uncertainties that would vary with neutron energy. The first of those is the relative lack of knowledge of the high energy end of the fission spectrum for the individual isotopes that are fissioning in a light water reactor core; and, the second, is the uncertainty in the mix of uranium and plutonium isotopes that make up the total power production for a given fuel cycle. The combination of these two factors along with the fact that the mix of fissioning isotopes varies both with position and time leads to a net effect on the calculation that may produce energy dependent biases.

In addition to these energy dependent uncertainties in the neutron source term, remammg deficiencies in the ENDF/B-VI cross-sections themselves produce effects that could cause energy dependent biases that are a function of penetration.

The most probable cause of the observed mismatch in calculated and best estimate spectra is a combination of uncertainties in these source term and cross-section processing assumptions that enter into the transport calculation along with uncertainties in the transport cross-sections. These observed spectral effects can be duplicated analytically by performing sensitivity studies to demonstrate that the [M]/[C] observations are consistent with the uncertainties in each of these parameters. However, it is not possible to separate out each of the individual effects that act in concert to produce a net effect, observed spectral bias, manifested in the observations in the

• 2-4

• normalized [M]/[C] ratios. Nevertheless, the comparisons of measurement with calculation by themselves provide an excellent indication of the net effect of uncertainties in all of these variables.

In regard to these comparisons, it should be noted that the observed spectral differences are not large and are easily accounted for in the uncertainty estimates associated with the spectrally weighted best estimate evaluations. The least squares adjustment approach accounts for these spectral differences by combining the individual measurements and their uncertainties with the transport calculated spectrum and its uncertainties to arrive at a Best Estimate of the true spectrum at the measurement locations. Thus, the observed spectral mismatch is accounted for in the overall uncertainty derived for the Best Estimate fluence .

• 2-5

Table 2-1

[M]/[C] Comparisons from the Westinghouse Dosimetry Data Base Foil Reaction Absolute [M]/[C] Ratio Normalized [M]/[C] Ratio 63 Cu(n,a )6°C~ 1.023 +/- 0.068 1.054 +/- 0.070 46Ti(n,p)46Sc 0.976_+/- 0.058 1.005 +/- 0.060 S4Fe(n,p)s4Mn 0.916 +/- 0.061 0.943 +/- 0.063 5

8Ni(n,p) 58 Co 0.903 +/- 0.062 0.930 +/- 0.063 235 U(n,f)FP 0.982_+/- 0.088 1.011+/-0.091 237Np(n,f)FP 1.021+/-0.116 1.051+/-0.119 Average 0.971+/-0.056 1.000 +/- 0.080 Table 2-2

[M]/[C] Comparisons from the Palisades Data Base Foil Reaction Absolute [M]/[C] Ratio Normalized [M]/[C] Ratio 63 Cu(n,a)6°Co 0.922 +/- 0.046 1.049 +/- 0.052 46Ti(n,p )46 Sc 0.942 +/- 0.049 1.073 +/- 0.056 s4Fe(n,p)s4Mn 0.836 +/- 0.033 0.952 +/- 0.038 0.959 +/- 0.030 5 58 8Ni(n,p) Co 0.843 +/- 0.026 0.964 +/- 0.090 235 U(n,f)FP 0.847_+/- 0.079 23 7Np(n,f)FP 0.880 +/-0.101 1.002 +/- 0.115 Average 0.879 +/- 0.056 1.000 +/- 0.070

• 2-6

Table 2-3

[M]/[C] Comparisons from the St. Laurent Data Base Foil Reaction Absolute [M]/[C] Ratio Normalized [M]/[C] Ratio 63 Cu( n,a )6°Co 1.000 1.024 46 Ti(n,p )46 Sc 54Fe(n,p)54Mn 0.936 0.958 58Ni(n,p)58Co 0.907 0.929 235 U(n,f)FP 1.010 1.034 237Np(n,f)FP 1.031 1.055 Average 0.977 1.000 Table 2-4

[M]/[C] Comparisons from the H. B. Robinson 2 Data Base Foil Reaction Absolute [M]/[C] Ratio Normalized [M]/[C] Ratio 63 Cu(n,a )6°Co 1.076 0.993 46Ti(n,p)46Sc 1.124 1.037 s4Fe(n,p)s4Mn 1.042 0.961 58Ni(n,p) 58Co 1.005 0.928 235 U(n,f)FP 1.157 1.068 23 7Np(n,f)FP 1.099 1.014 Average 1.084 1.000

• 2-7

• Table 2-5 Comparison of Normalized [M]/[C] Ratios from the Westinghouse Dosimetry Data Base with Independent Evaluations from other Pressurized Water Reactors

[M]/[C] [M]/[C] [M]/[C]

Reaction Data Base St. Laurent H. B. Robinson 63 Cu(n,a)6°Co 1.054 +/- 0.070 1.024 0.993 46Ti(n,p)46Sc 1.005 +/- 0.060 1.037 54fe(n,p)54Mn 0.943 +/- 0.063 0.958 0.961 58Ni(n,p)ssco 0.930 +/- 0.063 0.929 0.928 235 U(n,f)FP 1.011 +/- 0.090 1.034 1.068 23 7Np(n,f)FP 1.051+/-0.119 1.055 1.014 Average 1.000 +/- 0.080 1.000 1.000 Table 2-6 Comparisons ofNonnalized [M]/[C] Ratios from the Westinghouse Dosimetry Data Base with Plant Specific Evaluations Perfonned for Palisades

[M]/[C] [M]/[C]

Reaction Data Base Palisades 63 Cu(n,a)6°Co 1.054 +/- 0.070 1.049 +/- 0.052 46Ti(n,p)46Sc 1.005 +/- 0.060 1.073 +/- 0.056 54Fe(n,p)s4Mn 0.943 +/- 0.063 0.952 +/- 0.038 58Ni(n,p)58Co 0.930 +/- 0.063 0.959 +/- 0.030 235 U(n,f)FP 1.011_+/- 0.091 0.964 +/- 0.090 237Np(n,f)FP 1.051+/-0.119 1.002 +/- 0.115 Average 1.000 +/- 0.080 1.000 +/- 0.070

• 2-8

In addition to the previously submitted data, sensitivity studies have been performed to relate individual foil responses at in-vessel and ex-vessel locations to the energy distribution of the neutron source in the reactor core. The results of these studies, based on the use of adjoint discrete ordinates transport calculations, are provided in Tables 2.1 and 2.2 for the in-vessel wall capsule location as well as for the 16 degree reactor cavity measurement location. In Tables 2.1 and 2.2, the energy dependent response of each foil reaction as well as of <l>(E > 1.0 MeV) is related to the energy of the neutron source in the reactor core. Data are provided on both a groupwise and a cumulative response basis for both locations. For convenience, the response data have been binned into seven broad energy groups above 1.0 MeV. Also, the short half-life reactions in Ti and Ni have not been included in the tabulations. The Ti response is very similar to Cu and the Ni response is close to that of iron.

The results shown in Tables 2.1 and 2.2 provide two important conclusions. First, the high threshold reactions are loosely correlated with the flux above 1.0 MeV at both in-vessel and ex-vessel locations. For example, for Cu(n,a) approximately 90% of the response at both the in-vessel and ex-vessel measurement locations is due to neutrons born in the core at energies greater than 6 MeV.

For <l>(E > 1.0 MeV), however, roughly 25% of the response is due to source neutrons above the 6 MeV value. Foil reactions with lower thresholds such as U-238(n,f) and Np-237(n,f) more closely mirror the response of <!>(E > 1.0 MeV).

The second conclusion that follows from the observations drawn from Tables 2.1 and 2.2 is that the uncertainties in the high energy tail of the fission spectrum can account for the observed differences in the relative reaction rate measurements .

• 2-9

• Table 2.1 Reaction Response Matrix at the In-Vessel Wall Capsule Location Relative Group Response Weighting Lower Upper Energy Energy Cavity Response Flux MeV MeV Cu63(n.a) Fe54(n.p) U238(n.f) Np237(n.f) [E > 1.0) 1.22E+01 1.73E+01 6.85E-02 1.36E-02 1.OSE-02 6.87E-03 6.93E-03 8.61E+OO 1.22E+01 3.60E-01 1.18E-01 8.33E-02 6.04E-02 6.13E-02 6.07E+OO 8.61E+OO 4.62E-01 3.70E-01 2.68E-01 2.21E-01 2.30E-01 3.68E+OO 6.07E+OO 1.09E-01 4.26E-01 4.16E-01 4.16E-01 4.32E-01 2.73E+OO 3.68E+OO 5.88E-04 5.90E-02 1.43E-01 1.71E-01 1.64E-01 2.23E+OO 2.73E+OO 2.04E-05 1I15E-02 5.71E-02 7.82E-02 7.09E-02 1.00E+OO 2.23E+OO 8.99E-07 1.83E-03 2.13E-02 4.62E-02 3.43E-02 Total 1.00E+OO 1.OOE+OO 1.00E+OO 9.99E-01 1.00E+OO

• Lower Energy Upper Energy Cumulative Response Weighting Cavity Response Flux MeV MeV Cu63(n.a) Fe54(n.p) U238(n.f) Np237(n.f) [E > 1.0) 1.22E+01 1.73E+01 6.85E-02 1.36E-02 1.OSE-02 6.87E-03 6.93E-03 8.61E+OO 1.22E+01 4.28E-01 1.32E-01 9.38E-02 6.73E-02 6.83E-02 6.07E+OO 8.61E+OO 8.90E-01 5.01E-01 3.62E-01 2.88E-01 2.98E-01 3.68E+OO 6.07E+OO 9.99E-01 9.28E-01 7.78E-01 7.04E-01 7.31E-01 2.73E+OO 3.68E+OO 1.00E+OO 9.87E-01 9.22E-01 8.75E-01 8.95E-01 2.23E+OO 2.73E+OO 1.00E+OO 9.98E-01 9.79E-01 9.53E-01 9.66E-01 1.00E+OO 2.23E+OO 1.00E+OO 1.00E+OO 1.00E+OO 9.99E-01 1.00E+OO 2-10

Table 2.2 Reaction Response Matrix at the 16 Degree Ex-Vessel Capsule Location Relative Group Response Weighting Lower Upper Energy Energy Cavity Response Flux MeV MeV Cu63(n.a) Fe54(n.p) U238(n.fl Np237(n.fl [E > 1.0) 1.22E+01 1.73E+01 9.88E-02 2.42E-02 1.50E-02 9.13E-03 1.14E-02 8.61E+OO 1.22E+01 4.36E-01 1.73E-01 1.06E-01 7.31 E-02 8.79E-02 6.07E+OO 8.61E+OO 3.98E-01 4.0BE-01 2.92E-01 2.48E-01 2.78E-01 3.68E+OO 6.07E+OO 6.68E-02 3.45E-01 3.85E-01 4.09E-01 4.12E-01 2.73E+OO 3.68E+OO 2.47E-04 3.99E-02 1.24E-01 1.51 E-01 1.35E-01 2.23E+OO 2.73E+OO 9.86E-06 8.56E-03 5.0BE-02 6.84E-02 5.59E-02 1.00E+OO 2.23E+OO 4.49E-07 1.34E-03 2.76E-02 3.90E-02 1.95E-02 Total 1.00E+OO 1.00E+OO 1.00E+OO 9.98E-01 1.00E+OO Cumulative Response Weighting Lower Upper Energy Energy Cavity Response Flux MeV MeV Cu63(n.a) Fe54(n.p) U238(n,f) Np237(n,f) [E > 1.0) 1.22E+01 1.73E+01 9.88E-02 2.42E-02 1.50E-02 9.13E-03 1.14E-02 8.61E+OO 1.22E+01 5.34E-01 1.97E-01 1.21E-01 8.22E-02 9.93E-02 6.07E+OO 8.61E+OO 9.33E-01 6.05E-01 4.13E-01 3.30E-01 3.77E-01 3.68E+OO 6.07E+OO 1.00E+OO 9.50E-01 7.98E-01 7.40E-01 7.89E-01 2.73E+OO 3.68E+OO 1.00E+OO 9.90E-01 9.21E-01 8.90E-01 9.25E-01 2.23E+OO 2.73E+OO 1.00E+OO 9.99E-01 9.72E-01 9.59E-01 9.BOE-01 1.00E+OO 2.23E+OO 1.00E+OO 1.00E+OO 1.00E+OO 9.98E-01 1.00E+OO

• 2-11

3. Position Uncertainty. The Consumers Energy/Westinghouse Palisades "best-estimate" jluence is based entirely on the dosimeter measurements. Because of the extremely strong jluence attenuation, thejluence measurement is sensitive to the position of the dosimeters relative to the few peripheral fuel assemblies that dominate the dosimeter response.

The current Palisades dosimetry measurements (before adjustments) have been corrected twice for geometrical causes. In view ofthese corrections and the position sensitivity of the measurements, the proposed relatively small (< 5%) dosimetry position uncertainty does

-not appear credible. In order to support the use of these measurement uncertainty values, provide a detailedjustification for the following measurements: (1) accelerated capsule, (2) in-vessel capsules, and (3) cavity measurements. To the extent possible, this justification should be based on the Palisades-specific as-built geometry data and should account for the effect of radial, axial, and azimuthal displacements.

It is correct that the use of measurements is strongly affected by the accuracy of the measurement locations. It is also correct that Palisades has updated this information in part, twice. These changes were made to improve the accuracy of these dosimetry locations. Changes were made, because it was evident that we had not established them well enough. If there is a concern about the accuracy of the positions used in the calculations, it would be useful for our response if we knew specifically which measurement locations we have not provided sufficient justification for. The fact that we have improved them is not in and of itself reason to doubt them now.

The best estimate fluence for the Palisades reactor vessel is not based solely on the measurements.

The approach used in the FERRET code performs a log-normal least squares adjustment of the measured data, dosimetry cross-sections, and calculated spectrum to produce the most consistent set using a least squares methodology. The code calculates an output covariance matrix relating the uncertainties in all parameters.

The FERRET code uses a log-normal least squares technique to obtain the best solution to the equations:

where: R; = A set of measured reaction rates for i sensors.

ai8 = Multigroup reaction cross-sections for i reactions and g neutron groups.

<J>8 = Calculated multigroup neutron spectrum for g groups at the measurement location.

3-1

• The number of simultaneous equations solved in the adjustment procedure is dependent on the number of sensors contained in the dosimeter set. Input values supplied to FERRET include these parameters and a covariance matrix relating the uncertainties in each of these parameters.

In the FERRET calculations, multigroup neutron fluxes, reaction cross-sections, and covariance data are treated in a 53 group energy scheme. The calculated neutron spectrum is provided in the multigroup structure used in the transport computations, in this case 47 groups. The dosimetry cross-sections are supplied in 620 groups in the SNLRML library. The least squares adjustment algorithms discussed in ASTM Standard E 944 are solved in FERRET to produce best estimate exposure results with associated uncertainties at the measurement location. Thus, the Palisades best estimate fluence is derived from all available surveillance capsule and reactor cavity dosimetry data, which includes the measurements and calculations.

The position uncertainty of the in-vessel and ex-vessel has been addressed in detail in the response to RAI 3.10 dated 08/14/96 (Submitted September 9, 1996, Attachment 1, pp. 14-24). The response is provided again on page 3-3.

Combustion Engineering drawing 2966-E-2871 provides a diametrical tolerance of 0.015 inches on a flux monitor housing hole of 0.136 inches. Likewise, Combustion Engineering drawing 2966-SJ-1571 provides a diametrical tolerance of 0.250 inches at the top support and 0.375 inches at the bottom support of the capsule holder relative to the radial position of the wall or accelerated capsule.

In view of the design tolerances, a dosim~try position sensitivity analysis was performed for a wall capsule position to evaluate the potential for an improperly positioned capsule. Table 3-1 shows the required misalignment of the wall capsule for each reaction such that the calculated response equals the measured response. The W290-9 capsule irradiated during Cycle 9 was used for this example.

Table 3-1 Radial and Azimuthal Capsule Displacements for a Calculated Response Equal to the Measured Response at Capsule W290-9 Reaction Radial Disnlacement (cm) Azimuthal Disnlacement 63 Cu (n,a.) 60Co +0.2 +0.6° 54 Fe (n,p) 54Mn +1.6 +4.6° 58

• 8Ni (n,p) Co 5

+1.3 +3.7° 238 137 U (n,f) Cs +1.2 +3.2° 237Np (n,f) 137Cs +1.6 +3.7°

• 3-2

The comparison shows that for each reaction the capsule must be moved in a radial direction away from the core towards the reactor vessel or azimuthally a large arc length. For all of the dosimetry reactions except the 63 Cu response, the responses show the required capsule displacement exceeds the design tolerance. In fact, the 54Fe and 23 7Np require a radial displacement placing the capsule physically within the reactor pressure vessel wall, an impossibility without coincident increase in the diameter of the pressure vessel. Similar large displacements would be required to match the accelerated capsule calculations and measurements.

RAI 3.10 (08/14/96) The reliability of the M!Cjluence bias and the FERRET adjustment procedure depends on reasonable agreement between the measured and calculated reaction rates. However, the measured reaction rates are sensitive to the capsule location and the position of the dosimeters inside the capsule, and the as-built positions of the dosimeters (relative to the core) typically include a substantial degree of uncertainty.

1) Provide an estimate of the uncertainty in the dosimeter locations and the resulting uncertainty in the measured reaction rate.

2) Describe how this uncertainty is included in the FERRET analysis.

3) How does this uncertainty compare with the uncertainty in the calculated bias?

As noted in Section 8.1 of WCAP-14557, Revision 1, the best estimate neutron fluence at the Palisades reactor pressure vessel wall is determined from the following relationship:

Best.Est. = K calc where:

<l>eestEst. = The best estimate fast neutron exposure at the location of interest.

K The plant specific measurement/calculation (MIC) bias factor derived from all available surveillance capsule and reactor cavity dosimetry data.

<l>ca1c. The absolute calculated fast neutron exposure at the location of interest.

The bias factor K is determined from a comparison of the results of the least squares adjustment evaluation of all available dosimetry sets with the corresponding analytical predictions at the nominal location of the multiple foil sensor sets. The uncertainty associated with the least squares adjustment results includes a combination of the uncertainties in the measured reaction rates, dosimetry cross-sections, and the calculated neutron spectrum at the nominal location of the dosimetry. The least squares adjustment does not include any component due to positional uncertainty of the dosimetry. Therefore, this additional component is not reflected in the uncertainty

• 3-3

associated with the bias factor, K. Note, from Table 7.1-1 of WCAP-14557, Revision 1, that the uncertainty in the bias factor was estimated to be approximately 8% [(0.067/0.831)* 100].

As noted in Section 8.2 ofWCAP-14557, Revision 1, the overall uncertainty in the best estimate fast neutron exposure of the* pressure vessel wall includes, in addition to the uncertainty in the bias factor, K, components to account for the relative locations of the measurement points and the pressure vessel wall, the potential variation in the dimensions of the reactor internals, and the potential variations of water density within the reactor. The magnitude of these additional uncertainty components is determined from analytical sensitivity studies carried out for the Palisades reactor geometry. In addition, an added uncertainty of 5% is included to account for minor components of the overall uncertainty that are not specifically addressed in either the measurement to calculation comparisons or in the analytical sensitivity studies. Note, from Section 8.2 ofWCAP-14557, Revision 1, that combining these added uncertainty components with the uncertainty in the bias factor obtained from the least squares adjustment MIC data base results in a net uncertainty of 14.5% in the best estimate projections of the fast neutron (E > 1.0 Me V) exposure of the Palisades reactor pressure vessel.

The following discussion pertains to the location and positional uncertainty associated with the reactor cavity and internal surveillance capsule multiple foil sensor sets.

Reactor Cavity Sensor Locations The multiple foil sensor sets irradiated in the Palisades reactor cavity during fuel cycles 8 through 11 were suspended from an aluminum support bar that was originally intended to be positioned at a nominal radius of 108 inches relative to the core centerline. The azimuthal positioning of the support chains supporting the aluminum bar was determined relative to reactor coordinates stamped on the reactor vessel head at the o*, 90°, 180°, and 270° cardinal axes and to seal ring bolt holes equally spaced in the reactor vessel seal ledge on a 213-11/16 inch bolt circle.

During a walkdown of the initial installation, it was noted that the aluminum support bar was displaced azimuthally due to the passage of a support chain located at 330° over an angle iron located in the reactor cavity. This displacement also resulted in a radial skew of the support bar with the 270° end of the bar moving closer to the reactor pressure vessel. At that time, an estimate of the azimuthal displacement was made using a plumb line dropped at 300° as a reference point. The bar was initially estimated to have been translated azimuthally by approximately 5*. Consistency checks, using measured and calculated azimuthal neutron flux gradients, indicated that the azimuthal shift was actually 6° .

• 3-4

• During the dosimetry installation prior to the onset of Cycle 10, a more detailed set of measurements were made to determine the as-built radial location of the dosimetry bar in the reactor cavity relative to the outside surface of the mirror insulation on the reactor vessel. The distances measured were from the surface of the vessel insulation to the center of the U-tubes on the dosimetry support bar.

These as-built locations are depicted in Figure 3 .10-1. Also shown on Figure 3 .10-1 are bands representing a potential+/- 3 inch displacement of the dosimetry sets in both the azimuthal and radial directions. Note that for a nominal radius of 108 inches, a translation of+/- 3 inches corresponds to an angular displacement of+/- l .6°.

Although the uncertainty in sensor set positioning is estimated to be +/- 2 inches based on the measurements obtained after installation of the dosimetry support bar, comparisons are provided here for a range of+/- 3 inches in order to better illustrate the behavior of the neutron field in the cavity. In performing these comparisons, it was assumed that translation of the sensor sets could take place in any direction relative to the nominal position. All comparisons provided herein are based on gradient information extracted from the Cycle 9 transport calculation.

An examination of the neutron flux and reaction rate gradients within the reactor cavity indicate that variations in the azimuthal direction are less than the variations in the radial direction. Therefore, the largest impact of the uncertainty in dosimetry location can be determined by an evaluation of the radial gradient data at each azimuthal location containing dosimetry. Gradient data describing the radial variation of~ (E > 1.0 MeV) at the first octant equivalent (FOE) 6°, 16°, 24°, 26°, 36°, and 39° dosimeter locations are provided in Figures 3 .10-2 through 3 .10-7. The gradient information shown on Figures 3 .10-2 through 3 .10-7 is provided in terms of fractional change in calculated response as a function of distance from the nominal sensor set position. Over the range of interest, the gradient data for all fast neutron reaction rates are similar to those observed for ~ (E > 1.0 Me V).

An examination of Figures 3 .10-2 through 3 .10-7 shows that within the 3 inch range from nominal position the fractional change in calculated flux ranges from+/- 0.5% for the 39° azimuth to+/- 5% at the 16° location. Therefore, the maximum bias that could be introduced into the MIC comparisons due to mis-positioning of the cavity dosimetry sensor sets would be expected to be no greater than 5% with an average uncertainty for all cavity sensor sets substantially less than the 5% value.

Internal Capsule Locations Multiple foil sensor sets irradiated in the internal surveillance capsules are positioned laterally at a constant radius from the core center. The lateral gradients across the capsule are small; and as is the case with the cavity dosimetry the maximum impact of positioning uncertainties occurs due to radial rather than azimuthal gradients. However, _unlike the reactor cavity where positioning uncertainties 3-5

result in a translation in air, the positioning uncertainties for the internal capsules result in a translation through either a water or steel medium.

In assessing this component of the uncertainty for the Palisades reactor, dosimeter positioning was assumed to be+/- 0.25 inches and+/- 0.125 inches for the wall and accelerated capsules, respectively.

These dimensions were taken from the allowable tolerance specified in the design drawings for the Palisades reactor.

Based on parametric studies of the variations of capsule positioning within the reactor environment, the following impacts were developed for the in-vessel dosimetry sets.

Dosimeter Position (acc.) 11.0%/cm 3.5% uncertainty Dosimeter position (wall) 6.0%/cm 3 .8% uncertainty It should be noted that these uncertainties, while representing a maximum based on tolerance limits, were treated as 1cr values in the overall uncertainty associated with the neutron exposure of the pressure vessel wall .

• 3-6

Figure 3.10-1 Location Of Reactor Cavity Multiple Foil Sensor Sets 350 340 - Bioshield Wall 330 -

320 --

310 El 300 --

~

<I.I

a=

290

+

~

i::i=: 280 -

270 -

260 -

250 -

- ri + ++

Vessel Insulation

+

240

- Pressure Vessel 230 I I I I

' I I I i I I I I I I I I I I I I I I I I I I I 0 10 20 30 40 50 60 70 Azimuthal Angle (deg)

• 3-7

Figure 3.10-2 Fractional Change As A Function Of Radial Position 6 Degree Azimuthal Traverse

<j> (E > 1.0 MeV) 0.10 -.----------------------------~

.Sil

~

= 0.05 u

~

.s~

ell

= 0.00

-==

u

.9=

~

cu -0.05

~ ""'

-0.lQ I I

-4 -3 -2 -1 0 2 3 4 Distance From Nominal Radius (in)

• 3-8

• Figure 3.10-3 Fractional Change As A Function Of Radial Position 16 Degree Azimuthal Traverse

<j> (E > 1.0 MeV) 0.10 -..----------------------------~

cu 0.05 i:z:::

u

~

.s~

tl.()

=

cu

..=

0.00 u

....=

~

cu -0.05

~ "'

-0.10 _,__ _ _ _ _ _ _ I - - - - - - - - - - - - - - - - - - - - - - ' !

-4 -3 -2 -1 0 2 3 4 Distance From Nominal Radius (in)

• 3-9

Figure 3.10-4 Fractional Change As A Function Of Radial Position 24 Degree Azimuthal Traverse

<j> (E > 1.0 MeV) 0.10 - - - . - - - - - - - - - - - - - - . . , , . . - - - - - - - - - - - - - - - - - - .

.s Cll 0.05

~

u

~

• =~

1:).1)

=

Cll

..c:

0.00 u

-a

...CJ=

.s E

i:..

-0.05

-0.10 +----.,-----,---,-I-....,...--..,..!- - - . . , . I---,----,....----..,...-....,--..,.-~I

-4 -3 -2 -1. 0 2 3 4 Distance From Nominal Radius (in)

• 3-10

Figure 3.10-5 Fractional Change As A Function Of Radial Position 26 Degree Azimuthal Traverse

<j> (E > 1.0 MeV) 0.10 ---.----------------------------~

.s.... 0.05 -

~

i:z::

u

~

.5

'I.I

=ii

=

~

0.00

-=u ca

.s....=

CJ

~

-0.05

~ ""

-0.10 I I I I I

-4 -3 -2 -1 0 2 3 4 Distance From Nominal Radius (in) 3-11

• Figure 3.10-6 Fractional Change As A Function Of Radial Position 36 Degree Azimuthal Traverse

<j> (E > 1.0 MeV)

Q

':C 0.05

~ =

u

~

.5 Q,)

~

=

.c=

0.00 u

=

Q

':C

(.I

~

=

-0.05

-4 -3 -2 -1 0 2 3 4 Distance From Nominal Radius (in) 3-12

Figure 3.10-7 Fractional Change As A Function Of Radial Position 39 Degree Azimuthal Traverse

<j> (E > 1.0 MeV)

-~

....cu 0.05

=i:::

u

~

.5 Q,j CJ) 0.00

=

cu

-=u

....=

.9

(.I cu -0.05

~ ""

-4 -3 -2 -1 0 2 3 4 Distance From Nominal Radius (in) 3-13

4. Cavity Dosimetry. In view of the difference between the cavity and in-vessel neutron spectrum, identify and discuss the physical mechanism that justifies the use of the cavity measurement to calculation (MIC) comparisons to reduce the I. 0 Me V < E < 3. 0 Me Vin-vessel spectrum._ Specifically, the number of in-vessel 1.0 MeV < E < 3.0 MeVneutrons is determined by the complex slowing down process that takes place at the steel/water interface at the inner wall of the vessel while the neutrons detected by the cavity dosimetry (especially the Cu-63, Ti-46, Fe-54, and Ni-58 dosimeters) are independent of the process.

In fact the cavity neutrons undergo the entirely different slowing down process resulting from the attenuation through the 8.25 inch thick steel vessel. Therefore, justify the use of cavity M/Cs to adjust the I. 0 < E < 3. 0 Me Vin-vessel jluence.

The methodology used in the Palisades fluence evaluations is intended as a Best Estimate, rather than a bounding, or conservative, fiuence determination. In the methodology, calculations and plant specific measurements are combined to derive a Best Estimate. In general, several approaches may be used to provide this exposure evaluation for the reactor pressure vessel.

Once the measurements and calculations are compared, one course of action is to merely use the_

measurements as a test of the calculated result. The calculation then would be considered adequate if it reproduced the measurements within an acceptable tolerance. This method, while the simplest in checking methods using both benchmark and plant specific data, does not produce a Best Estimate result and the uncertainty in the result will be that evaluated for the calculation alone.

The second method is to use the results of the plant specific analytical/dosimetry comparisons to re-normalize the calculations. Use of this approach will normally produce the best results at, or nearby, the locations where the dosimetry is placed. Translations to other locations can be guided by the results of benchmark comparisons and sensitivity analyses performed in support of the qualification of the calculational methodology. Use of this approach, combining both measurement and calculation, will come closer to the Best Estimate exposure than the method outlined in the preceding paragraph.

The most rigorous method for Best Estimate fluence determination is to include plant specific calculations and measurements and their uncertainties with benchmark measurements and uncertainties in a general least squares procedure such as that incorporated in the LEPRICON methodology. In the LEPRICON procedure, benchmark experiments are first incorporated into a data base of integral dosimetry measurements of high quality. These are measurements which 1) have been performed in simple geometries amenable to accurate descriptions for calculational purposes, 2) have large sensitivities to only a few differential parameters, and 3) involve integral quantities and parameters which are highly correlated with many of the parameters used in the 4-1

analysis of the more complex geometries characteristic of light water reactors. The benefit of simultaneously combining the benchmark results with the plant specific data into a more self consistent data base comes about because of the correlations induced by data sharing sensitivities .

to common parameters.

In the evaluations performed for Palisades, the second approach outlined above was used to re-normalize the discrete ordinates calculations based on [BE]/[C] ratios of cj>(E > 1.0 MeV) obtained from least squares evaluations of both in-vessel and ex-vessel dosimetry. The use of this approach is less rigorous than the full least squares adjustment as represented by LEPRI CON and depends on the ability of the transport calculation to accurately reflect the relative behavior of the neutron field between the measurement locations and the vessel inner wall. In particular, for the ex-vessel comparisons the calculation must accurately reflect the attenuation through the thick steel wall.

For the transport methodology employed in the Palisades calculations, the ability to accurately reflect the attenuation through the pressure vessel wall has been tested against both the PCA benchmark and the H.B. Robinson benchmark The pressure vessel simulator benchmark comparisons used in the qualification of the neutron transport methodology are based, in part, on the analysis of the PCA 12/13 experimental configuration. The 12/13 configuration was chosen for the methods evaluation due to the similarity of this particular mockup to the thermal shield- downcomer- pressure vessel designs that are typical of most pressurized water reactors. Of particular note in regard to the areas of similarity are the 12 cm water gap on the core side of the thermal shield, the 13 cm water gap between the thermal shield and the pressure vessel simulator, the 6 cm thick thermal shield, the 22.5 cm thick low alloy steel pressure vessel, and the simulated reactor cavity (void box) positioned behind the pressure vessel mockup.

From the viewpoint of fast neutron attenuation, the 12/13 experimental configuration results in a reduction factor for cj>(E > 1.0 MeV) of approximately 1000 between the reactor core and the inner surface of the pressure vessel; and a corresponding reduction factor of about 30 from the inner surface to the outer surface of the pressure vessel wall. These similarities in the geometry and attenuation properties of the PCA mockup and L WR plant configurations provide additional confidence that judgments made regarding measurement/calculation comparisons in the simulator environment can be related to the subsequent analyses performed for operating Light Water Reactors .

• 4-2

During the PCA experiments, measurements were obtained at several locations within the mockup to provide traverse data extending from the reactor core outward through the pressure vessel simulator and on into the void box.

In addition to the direct comparisons with benchmark measurements, a series of adjoint calculations have been performed to determine the sensitivity of the measurements in the reactor cavity to the energy distribution of the neutron source in the reactor core, i.e., the fission spectrum, as well as to the energy distribution of neutrons at the inner wall of the pressure vessel.

Results of the three-dimensional calculations using the TORT discrete ordinates transport code are provided in Table 4.1. The three-dimensional calculations were required to adequately treat axial leakage effects in the small PCA geometry. Also provided in Table 4.1 are the results of a least squares adjustment of the data supplied at each measurement location. An examination of Table 4.1 shows that, when axial leakage is calculated accurately, the transport calculation provides a good representation of the attenuation of Q>(E > 1.0 MeV) through the thick iron pressure vessel simulator.

This data suggests that using a relative attenuation obtained from a plant specific transport calculation along with least squares evaluated data from the reactor cavity measurement locations provides an adequate indication of cp(E > 1.0 MeV) at the inner surface of the simulator block.

This conclusion is further supported by a comparison of in-vessel and ex-vessel calculation to measurement comparisons obtained from the evaluation of the H.B. Robinson benchmark.

In Table 4.2, a comparison of the measured and calculated reaction rates at both the internal surveillance capsule and the reactor cavity locations at H. B. Robinson are provided. The comparisons indicate good agreement at both locations with a slight trend toward overprediction by the calculation. The consistency of the agreement at the cavity and internal capsule locations indicates that the attenuation through the vessel wall is being calculated well by the ENDF/B-VI cross-sections. This observation matches that observed with the three-dimensional calculations performed for the PCA.

In Table 4.3, a comparison of the ratio of reaction rates at the surveillance capsule location to that at the cavity location is shown for each measured reaction. Data are provided for both calculation and measurement.

In Table 4.4, calculated exposure parameters in terms of cp(E > 1.0 MeV) and dpa are provided along with the results of the least squares adjustment for both the internal capsule and the reactor cavity locations. Again, the trend toward overprediction by the calculation is evident. The results of the 4-3

least squares evaluations show consistency with the reaction rate comparisons and the calculated and best estimate slopes are likewise in good agreement.

Table 4.1 Comparisons Of Measured And Calculated Data From The PCA Benchmark Evaluations TORT Calculations Neutron Flux (E > 1.0 MeV)

Best Location Estimate %Unc. DORT TORT BE/DORT BE/TORT A1 3.87e-06 4 3.76e-06 3.83e-06 1.03 1.01 A2 4.24e-07 4 4.18e-07 4.33e-07 1.01 0.98 A3 1.37e-07 4 - 1.38e-07 1.44e-07 0.99 0.95 A4 4.58e-08 4 4.54e-08 4.78e-08 1.01 0.96 AS 2.23e-08 4 2.13e-08 2.24e-08 1.05 1.00 -

A6 9.84e-09 5 9.15e-09 9.71e-09 1.08 1.01 A7 2.79e-09 5 2.16e-09 2.62e-09 1.29 1.07 Table4.2 Comparison of Measured and Calculated Reaction Rates H.B. Robinson - Cycle 9 Benchmark 20° Surveillance Capsule 0° Reactor Cavity Reaction Calculated Measured M/C Calculated Measured M/C 63 6 Cu(n,a) °Co 4.00e-17 3.98e-17 1.00 4.13e-19 4.01e-19 0.97 46 Ti(n,p) 46Sc 6.35e..,16 6.49e-16 1.02 5.92e-18 6.17e-18 1.04 54 Fe(n,p) 54 Mn 4.01e-15 3.83e-15 0.96 3.78e-17 3.59e-17 0.95 58 Ni(n,p) 58Co 5.43e-15 4.88e-15 0.90 5.63e-17 5.29e-17 0.94 238 U(n,f)FP 1.79e-14 1.80e-14 1.01 2.54e-16 2.72e-16 1.07 237 Np(n,f)FP 1.24e-13 1.20e-13 0.97 5.23e-15 Average 0.97 0.99

• 4-4

Table 4.3 Comparison of Measured and Calculated Surveillance Capsule/Reactor Cavity Reaction Rates H.B. Robinson - Cycle 9 Benchmark Westinghouse Calculation Measurement Reaction Cagsule Cavity Ratio Cagsule Cavity Ratio 63Cu(n,a)6°Co 4.00e-17 4.13e-19 96.9 3.98e-17 4.01e-19 99.3 46Ti(n,p) 46Sc 6.35e-16 5.92e-18 107. 6.49e-16 6.17e-18 105.

54 Fe(n,p) 54Mn 4.01e-15 3.78e-17 106. 3.83e-15 3.59e-17 107.

58 Ni(n,p)58Co 5.43e-15 5.63e-17 96.6 4.88e-15 5.29e-17 92.2 23BLJ(n,f)FP 1.79e-14 2.54e-16 70.5 1.80e-14 2.72e-16 66.2 237 Np(n,f)FP 1.24e-13 5.23e-15 23.7 1.20e-13 Table 4.4 Summary of Least Squares Evaluations H.B. Robinson - Cycle 9 Benchmark Calculated Best Estimate  % Uncertainty BE/C 20° Surveillance Capsule

<l>(E > 1.0 MeV) 4.89e+10 4.58e+10 7 0.94 dpa/sec 7.75e-11 7.36e-11 9 0.95 Avg. Foil M/C 0.97 0° Reactor Cavity

<l>(E > 1.0 MeV) 9.78e+08 9.54e+08 10 0.98 dpa/sec 4.16e-12 4.11e-12 20 0.99 Avg. Foil M/C 0.99 Surveillance Capsule/Cavity Ratio

<!>(E > 1.0 MeV) 50.0 48.0 0.96 dpa/sec 18.6 17.9 0.96 The results of these benchmarking studies highlighted in Tables 4.1 through 4.4 show that measurements taken in the reactor cavity can be correlated with the fluence at the vessel inner wall with acceptable uncertainties. These comparisons indicate that the relative slope through the vessel wall is predicted by the plant specific transport calculations to within approximately 3-4%. These trends shown in Tables 4.1 through 4.4 are also observed in the Palisades plant specific data base when in-vessel and ex-vessel measurements are compared. It is, therefore, concluded that

• 4-5

measurements from the Palisades reactor cavity can be included in the Best Estimate fluence evaluation for the vessel wall.

As noted in the preceding paragraph, the procedure used in the Palisades evaluation introduces a 3-4% uncertainty due to the use of the calculated attenuation. This uncertainty component could be improved with the application of a more rigourous least squares evaluation methodology as represented by LEPRICON .

• 4-6

• 5. Guide E944-96. "Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, "E-944 states that "Adjustment methods provide a means for combining the results of neutron transport calculations with neutron dosimetry measurements in_ order to obtain optimal estimates ofneutron damage exposure parameters with assigned uncertainties. The inclusion of measurements reduces the uncertainties for these parameter values and provides a test for consistency between measurements and calculations and between different measurements. "This does not however imply that the standards for measurements and calculations of the input data can be lowered; the results of any adjustment procedure can be only as reliable as are the input data" (emphasis added).

In view of the energy spectrum dependent MIC results, how was the data reliability, compatibility, and statistical significance for the adjustment operation established In the approach used to determine the Best Estimate exposure of the Palisades reactor pressure vessel, the least squares adjustment approach is used to evaluate calculations and measurements at the dosimetry locations at in-vessel and ex-vessel locations, The input to these evaluations includes the calculated neutron spectrum, measured sensor reaction rates, and dosimetry reaction cross-sections. As noted in the above question, ASTM standard E944 requires that each of these input variables should be determined using the best available techniques. As discussed in responses 1, 2, and 6 of the current RAI as well as in responses to previous RAl's, each of these input variables was determined on a plant specific basis using the latest procedures as outlined in applicable ASTM procedures. The data has been shown to be repeatable and consistent with observations from other reactors. In performing the Palisades least squares adjustment evaluations, no data incompatibilities have been noted that cannot be attributed to uncertainties associated with the various input variables .

• 5-1

• 6. Fluence Methodology. The proposed Palisades adjustment of 17% in the vessel jluence has been called a calculational bias. This implies that jluence measurements in similar plant settings that have been analyzed with the same methodology should exhibit the same trend of substantial underprediction with respect to the calculation.

However, this is not the case with the Westinghouse/Palisades method. For the 21 plants analyzed by Westinghouse (and presented in previous meetings) identify the physical phenomena that cause them to exhibit different behavior than Palisades.

Significant effort has been expended improving the accuracy of the DORT computer code. This code, when given accurate information, will produce a predictably accurate answer. However, the calculation of the fluence at a particular reactor is a complicated process that is dependent on a significant number of inputs that are not precisely known. The calculation's uncertainty is determined by defining the limits of what is known. The uncertainty attributed to the DORT computer code in the Palisades calculated fluence is essentially zero. The uncertainty in Palisades' calculated fluence comes from the quality of the source distribution, geometric input, compositional inputs and the cross-section database. Of these uncertainty sources, only the cross-section data base uncertainties are common among different plants. Therefore, it is not surprising that the result of a DORT calculation would differ in accuracy from plant to plant even though the same code is being used.

The data on Westinghouse calculated fluence for different plants shows a scatter that is actually less than what would be expected assuming that all the plants have calculational uncertainties of approximately 15%. Yet, the Staff has repeatedly questioned how there could be so much scatter.

The questions Consumers has received in this area imply that all the calculations should have roughly the same bias with a very small scatter. This assumes that all the plants would suffer from some common bias that when removed would result in a very small uncertainty. This is not the case.

The only significant bias that plants can share is a bias caused by the cross-sectional data base and even this bias would be affected by geometrical differences between plants. In addition, Consumers doubts that any plant can quantify the inputs to the DORT calculational methodology to the point that their uncertainty would be truly less than 10%.

The data related to Westinghouse analyzed plants as presented by Palisades show that there may be some common bias of 6% and if this bias were removed that the uncertainties of these calculations would run at slightly less than 10%. This, in and of itself, speaks very well of Westinghouse's consistency and competence in this area. Westinghouse's calculational uncertainty is generally around 14%. Using this estimate, it should be expected that one out of every 20 plant's 6-1

fluence calculation would have a bias factor of greater than 28% and one out of every 3 plants would have a bias factor of greater than 14%. When viewed against this estimate, Westinghouse has done a better job in their calculation than would be expected. Yet, the staff continues to question the

'wide' scatter in the data. It is very difficult for Consumers to explain why the scatter is so large, when it is already smaller than it should be when referencing the accepted uncertainty values.

When BE/C comparisons for an individual plant such as Palisades are contrasted with an overall industry data base, it is important to keep in mind the various factors that may cause a bias to exist between calculation and measurement. There are indeed a number of factors related to the general methodology that may cause a bias that would generally apply to all calculation/measurement comparisons. This is an example of the trend suggested in this question. However, there are additional components of the calculational uncertainty that may also vary from plant to plant. These include both physical and operational variables. When these additional factors are considered, it is indeed possible for BE/C comparisons to exhibit different behavior for different plants.

This issue was discussed extensively in response to RAI's generated at the 02/26/97 technical meeting between the NRC staff and Consumers Energy as well as at several other .technical meetings. The prior RAJ response is also provided here in order to illustrate the relationship of the Palisades plant specific data base to the overall 21 plant data set described in previous discussions between the staff and Consumers Energy (Submitted June 26, 1997, Attachment 1, pp. 21-3 7).

Issue 3: Why is the spread on Palisades MIC comparisons tighter than at other plants?

The standard deviations associated with the Palisades [MIC] comparisons are acceptable, but, in general, are no better or worse than those observed at other operating reactors.

The standard deviations associated with the [MIC] ratios developed from the Palisades plant specific dosimetry data base are both reasonable and consistent with those observed in industry wide comparisons. In Table 3-1 absolute [MIC] ratios obtained from the Palisades irradiations are compared with an industry wide data base compiled by Westinghouse from irradiations at 21 domestic reactors and also with a Siemens-KWU data base reported to consist of [MIC] ratios from 20 German light water reactors. The Palisades, Westinghouse, and Siemens-KWU data bases all contain comparisons at both in-vessel and ex-vessel locations.

An examination of Table 3-1 indicates that the standard deviations in non-fission reaction rates range from 4% - 7% and for fission reaction rates from 9% - 12%. Variations of this magnitude are consistent with the associated uncertainties in the measurement process and are not unexpected.

Also from Table 3-1, it can be seen that the corresponding standard deviations in the Palisades data 6-2

base range from 4% - 5% and 9% - 12% for non-fission and fission reaction rates respectively. In some cases the Palisades data have a smaller standard deviation than the data base as a whole. Since the data base spans many plants and the Palisades data are from a single plant, this trend should be expected.

More detailed summaries of the absolute [M]/[C] ratios for the individual sensors that comprise the multiple foil sets used in both in-vessel and ex-vessel irradiations are provided in Tables 3-2 through 3-7 for the 63 Cu (n,a), 46Ti (n,p), 54Fe (n,p), 58Ni (n,p), 238U (n,f), and 237Np (n,f), reactions respectively. These data are illustrated graphically in Figures 3-1 through 3-5, except for 46 Ti (n,p) due to the limited data.

From the data listed in Tables 3-2 through 3-7, the percent standard deviation associated with the Palisades foil measurements can be compared with the range of percent standard deviations observed in the 21 plant data base. These comparisons are summarized in Table 3-8.

From the comparisons listed in Table 3-8, it is clear that the statistical behavior of the Palisades plant specific [M]/[C] ratios is consistent with observations from the 21 plant data base for all foil reactions. Again, as noted earlier the standard deviations of the Palisades plant specific foil data fall close to the data base average for all reactions .

• 6-3

Table 3-1

• Comparison of Palisades Absolute [M]/[C] Ratios with Corresponding Ratios from Westinghouse and Siemens-KWU Industry Wide Data Bases

[M]/[C]b [M]/[CY [M]/[C]d Reaction Westinghouse Siemens-KWU Palisades 63 Cu (n,a) 6°Co 1.02 +/- 7% 0.92+/- 5%

46Ti (n,p) 46 Sc 0.98 +/- 6% 0.94+/- 5%

54Fe (n,p) 54Mn 0.92+/- 7% 0.92+/- 6% 0.84+/-4%

58Ni (n,p) 58 Co 0.90+/- 7% 0.84+/-4%

238 U (n,f) FP 0.98+/-9% 0.85 +/-9%

93Nb (n,n') 93mNb 0.96+/-6%

23 7Np (n,f) FP 1.02 +/- 11% 0.88 +/- 12%

Average 0.97+/-6% 0.94+/-6% 0.88 +/- 5%

NOTES:

[a] - Siemens-KWU data were taken from:

Polke, E., "Siemens-KWU Experience in Evaluating Fluence Detectors Inside and Outside the RPV in German Light Water Reactor Plants," Proceedings of the Ninth ASTM-Euratom Symposium on Reactor Dosimetry, Prague, Czechoslovakia, September 1996.

[b] - The Westinghouse data base consists of MIC comparisons from 158 multiple foil sensor sets irradiated at 21 operating reactors. The data base represents both in-vessel and ex-vessel comparisons.

[cJ - The Siemens-KWU data base consists of MIC comparisons from in-vessel and ex-vessel irradiations at 20 operating reactors. The total number of data points were not reported.

[d] - The Palisades data base consists of MIC comparisons from 17 multiple foil sensor sets irradiated at both in-vessel and ex-vessel locations .

• 6-4

Table 3-2 Summary of [M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 63 Cu (n,a.) 6°Co Average Standard  % Standard Number of Reactor [M]/[C] Ratio Deviation Deviation Points 3 0.890 0.076 8.5 18 Palisades 0.922 0.046 5.0 17 5 0.943 0.082 8.7 19 8 0.962 0.008 0.8 4 11 0.984 0.041 4.1 3 10 0.986 0.039 4.0 4 7 0.987 0.048 4.8 4 14 0.989 0.044 4.4 4 12 0.998 0.057 5.8 4 1 1.019 0.107 10.5 20 15 1.024 0.032 3.1 3 19 1.035 0.036 3.5 4 2 1.035 0.056 5.4 20 18 1.051 0.012 1.2 6 4 1.053 0.088 8.4 12 16 1.053 0.022 2.1 4 19 1.074 0.004 0.4 2 13 1.096 0.037 3.4 2 20 1.100 0.026 2.4 2 21 1.117 0.010 0.9 3 17 1.177 0.080 6.8 3 Average 1.023 0.068 6.7 158

• 6-5

Table 3-3 Summary of [M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 46Ti (n,p) 46Sc Average Standard  % Standard Number of Reactor [M]/[C] Ratio Deviation Deviation 3 0.899 0.057 6.3 16 Palisades 0.942 0.049 5.2 16 5 0.946 0.039 4.1 12 1 0.992 0.092 9.3 8 4 1.023 0.084 8.2 16 2 1.056 0.040 3.8 17 Average 0.976 0.058 5.9 85

• 6-6

• Table 3-4 Summary of [M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 54 Fe (n,p) 54Mn Average Standard  % Standard Number of Reactor rMllrCl Ratio Deviation Deviation Points 3 0.804 0.058 7.3 18 Palisades 0.836 0.033 3.9 17 14 0.845 0.069 8.1 4 18 0.869 0.037 4.2 6 15 0.874 0.027 3.1 3 1 0.877 0.085 9.7 20 7 0.882 0.058 6.5 4 11 0.894 0.041 4.5 3 5 0.899 0.063 7.0 19 12 0.908 0.133 14.6 4 8 0.915 0.028 . 3.1 4 19 0.926 0.078 8.5 2 2 0.927 0.035 3.8 19 13 0.929 0.006 0.6 2 16 0.938 0.042 4.5 3 21 0.938 0.054 5.7 3 20 0.947 0.032 3.4 2 10 0.968 0.013 1.3 4 9 0.984 0.045 4.5 4 4 1.004 0.110 11.0 12 17 1.075 0.101 9.4 3 Average 0.916 0.061 6.6 156

• 6-7

Table 3-5 Summary of [M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 5

8Ni (n,p) 58 Co Average Standard  % Standard Number of Reactor [M]/[C] Ratio Deviation Deviation Points 14 0.821 0.037 4.5 4 3 0.838 0.079 9.5 12 Palisades 0.843 0.026 3.1 16 1 0.846 0.096 11.3 19 18 0.866 0.018 2.1 6 15 0.867 0.006 0.7 3 12 0.869 0.093 10.8 4 11 0.883 0.046 5.2 3 5 0.887 0.059 6.6 19 9 0.891 0.083 9.4 4

• 19 20 13 10 2

0.897 0.899 0.906 0.907 0.920 0.040 0.029 0.006 0.054 0.031 4.5 3.2 0.6 5.9 3.4 2

2 2

4 19 7 0.922 0.080 8.7 3 8 0.922 0.045 4.8 4 16 0.938 0.032 3.4 3 21 0.939 0.049 5.2 3 4 1.022 0.174 17.0 12 17 1.092 0.079 7.2 3 Average 0.903 0.062 6.8 147 6-8

Table 3-6 Summary of [M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 238 U (n,f) FP Average Standard  % Standard Number of Reactor [M]/[C] Ratio Deviation Deviation Points Palisades 0.847 0.079 9.3 15 12 0.850 0.073 8.6 4 0.859 0.101 11.8 20 15 0.874 0.115 13.1 2 17 0.876 0.128 14.6 3 "2_, 0.924 0.105 11.4 19 0.934 0.088 9.4 20 11 0.949 0.025 2.7 2 3 0.957 0.079 8.3 18 14 0.967 0.143 14.8 4 9 1.000 0.057 5.7 4 7 1.001 0.118 11.7 4 4 1.013 0.121 11.9 12 8 1.013 0.080 7.9 4 16 . 1.032 0.086 8.4 2 13 1.062 0.045 4.2 2 19 1.082 0.165 15.2 2 21 1.082 0.039 3.6 3 20 1.098 0.003 0.3 2 18 1.098 0.030 2.7 6 10 1.102 0.085 7.7 4 Average 0.982 0.088 9.0 152

• 6-9

• Table 3-7 Summary of [M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 23 7Np (n,f) FP Average Standard  % Standard Number of Reactor [M]/[C] Ratio Deviation Deviation Points 12 0.831 0.024 2.9 3 14 0.870 0.111 12.8 4 Palisades 0.880 0.101 11.5 14 13 0.907 0.053 5.9 2 15 0.929 0.036 3.9 2 5 0.929 0.170 18.3 14 0.956 0.139 14.5 18 2 0.971 0.094 9.6 20 3 0.990 0.116 11.7 16 21 0.992 0.023 2.3 3 18 1.021 0.049 4.8 6 11 1.023 0.112 10.9 3 16 1.057 0.227 21.5 2 17 1.070 0.125 11.7 3 19 1.076 0.177 16.5 2 7 1.096 0.123 11.2 4 20 1.107 0.052 4.7 2 8 1.130 0.104 9.2 4 10 1.147 0.200 17.5 3 4 1.148 0.157 13.7 10 9 1.316 0.044 3.3 3 Average 1.021 0.116 11.3 138

• 6-10

• Table 3-8 Comparison of Standard Deviations in the Palisades Plant Specific Measurements with the Range of Standard Deviations from Plants Comprising the Data Base Data Base Average Data Base Range Palisades Reaction  % Standard Deviation  % Standard Deviation  % Standard Deviation 63 Cu (n,a.) 6°Co 7% 0.4% - 10.5% 5%

46Ti (n,p) 46 Sc 6% 3.8% - 9.3% 5%

54Fe (n,p) s4Mn 7% 0.6% - 14.6% 4%

58Ni (n,p) 58 Co 7% 0.6% - 17.0% 4%

238 U (n,f) FP 9% 0.3% - 15.2% 9%

23 7Np (n,f) FP 11% 2.9% - 21.5% 12%

Average 6% 5%

• 6-11

Figure 3-1

[M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 63 60 Cu (n,a) Co 1.40

_ Data Base Average

---

+/-!CJ 1.30

- - - - - - - - - - - - -!:- - - - - ~- - -.-~-!

1.20 1.10

-~

=:

I i: -

u

~

1.00 -

___T___ -l --~---- -- -- ----- --------------------

0.90 0.80 0.70 -

Palisades ID = 6 0.60 -+-1---,--.,-!-,---,-----,--,-I---,-..,.1-.,...--,----,-1-.,--------,----,.--,-----,---,1--'

0 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 Plant ID Cu-63.atb

• 6-12

Figure 3-2

[M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 54 Fe (n,p) 54Mn 1.40

_Data Base Average

---

+/-la 1.30 1.20 1.10

.Sl

~

~

---

~--~-----

u

~

1.00

--~--------~--

0.90

---

~----- --~-- ----------- - -----

0.80 0.70

- Palisades ID = 6 0.60 I I I I I I I 0 2 3 4 5 6 7 8 9 10 II 12 13 14 15 16 17 18 19 20 21 22 Plant ID Fe-54.atb

• 6-13

• Figure 3-3

[M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 58 Ni (n,p) 58 Co 1.40 - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,

_Data Base Average

---

+/- lcr 1.30 -

1.20 -

I .1u 1.00 I

0.90 -

---

---- ---f- ---- ----- -- ----~--~--------! ________

0.80 0.70 0.60

- Palisades ID =6

-',~..,....----..-----,.-----.,.---.,...--,1-.,.-1--...,------,I---,---~

0 2 3 4 5 6 7 8 9 IO 11 12 13 14 15 16 17 18 19 20 21 22 Plant ID Ni-58.atb

• 6-14

Figure 3-4

[M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base 238 U (n,f) FP 1.40 - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .

_Data Base Average

---

+/-la 1.30 1.20 -

1.10 -

1.00 -

---

T------- ~- -----I--------I-- ___ J__ -~-1

- --~- _____________ I I_____ -- ----- -----------

0.90 1-- -- -

0.80 0.70 0.60 Palisades ID =6

--'----..,...------,.-1--,1--.-1-,.-I----,-----.,-----..,...-,-1---,------..,...--,,.--...,..1_ ___.

0 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 Plant ID U-238.atb

• 6-15

Figure 3-5

[M]/[C] Ratios from In-Vessel/Ex-Vessel Data Base z31Np (n,t) FP 1.40

_Data Base Average 1.30

---

+/- la I

1.20

---

--------- __J_____ -- -------------- -- ------

.s....

==

1.10 1.00 1 I

~ 0.90

-- -- ----- --r-----------------~-~-- --~-- --------- ------

0.80 0.70 Palisades ID = 6 0.60 -'---,--,----,-I- --,1,....-....,.1-..,.1-.,---1,....-....,.1-.,-1-.,..I- , - I- - , - - - . . , . I-.,..I---,----..,.I--~

0 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 Plant ID Ni>-237.atb 6-16

Issue 4* What are the causes of the [BE]/[C] bias exhibited at Palisades?_

The individual effects causing the overall bias observed at Palisades are to a large extent unknown.

The plant has made extensive efforts to quantify and remove the known biases from the calculations.

One additional known source of bias is the fouling of flow venturi in the steam generator feed system. Testing has been performed using an ultrasonic flow measurement device which has demonstrated that the plant has been running at 98% of its rated thermal power. This bias will be evaluated for application in the future. This directly effects the [BE]/[C] bias. Other possible sources of bias include, the calculation of pin powers in low powered peripheral assemblies, as-built core barrel and shroud thicknesses compared to nominal values, coolant temperatures in the bypass region and peripheral fuel assemblies, and undiscovered errors in the cross-sections used in the transport analyses.

In addition there are several differences in the design of Palisades that may contribute to the bias.

These differences include, narrow and wide water gaps between fuel assemblies, lower inlet temperature, capsules mounted on the inside diameter of the vessel instead of the outside diameter of the thermal shield, and the lack of a thermal shield in the Palisades design. Errors in the cross-section data base may be exaggerated at Palisades due to the lack of a thermal shield and the location of the in-vessel dosimetry.

Since the identification and quantification of these individual effects is extremely difficult, the use of the plant specific measurements represents the only practical means to quantify the net overall bias in the calculation. Benchmarking the calculational methodology to known benchmark problems does not identify or quantify variations or errors in the input to plant specific calculations. The accuracy of the input is limited by the availability and quality of the plant specific documentation.

Table 4-1 represents an estimate of possible biases existing within the calculation of the Palisades reactor vessel fluence. These estimates are based on sensitivity studies done to calculate the calculational uncertainty and engineering judgment.

6-17

Table 4-1 Summary of Potential Sources of Calculational Bias Potential Bias Source Possible Magnitude Fouling of the Feed Water Flow Venturi +1%to+3%

Peripheral Assembly Pin Powers +/-8%

Core Support Barrel Thickness (+1116) +2%

Core Shroud Thickness (+l/16 inch) +2%

Material Compositions & Densities +/-4%

Bypass Temperature 0%to+5%

Exterior Core Temperature 0% to +3%

Transport Cross Sections +/-8%

Neutron Source (Pu vs. U) +/-3%

6-18

• 7. Fluence Methodology. The proposed Westinghouse/Palisades vessel fluence is based on an assumed DORT calculated overprediction of the E < 3. 0 Me V fluence of approximately 17% and an essentially correct DORT prediction of the E > 3. 0 Me V fluence. Please identifa the flaws in the Palisades fluence calculation by providing an explanation of this overprediction including: (1) the identification of the physical mechanism or approximation responsible for the overprediction (e.g.,

group structure, cross sections, fission spectrum, etc.), (2) a discussion of the responsible mechanism describing the phenomena and the source of error, and (3) a revised DORT calculation correcting the E < 3.0 MeV overprediction.

In our response to request 6, we have discussed areas that are likely to be the cause of the bias. This information was originally submitted June 26, 1997. An attempt was also made in our September 19, 1996 submittal to identify the source of the bias. These attempts have proven inadequate. Unfortunately, we are unable to provide more specific information to explain the spectral bias without re-testing and benchmarking the cross-sections and performing basic research on the high energy fission spectra ofU and Pu.

As discussed at the December 7, 1998 meeting, we will actively begin to implement improvements to the calculations as they are developed. It is our intent to provide a revised fluence methodology to the NRC by July 1, 2000.

7-1