View source for 3F1102-11, Submittal of Non-Proprietary Information Proposed License Amendment Request 270, Revision 0 Power Uprate to 2568 Mwt.

{{Adams
| number = ML023380681
| issue date = 11/25/2002
| title = Submittal of Non-Proprietary Information Proposed License Amendment Request #270, Revision 0 Power Uprate to 2568 Mwt.
| author name = Young D
| author affiliation = Florida Power Corp
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000302
| license number = DPR-072
| contact person = 
| case reference number = 3F1102-11, TAC MB5289
| document type = Letter type:
| page count = 37
| project = TAC:MB5289
| stage = Request
}}

=Text=
{{#Wiki_filter:Florida         Power A Progress Energy Company Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.90 November 25, 2002 3F1102-11 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

==Subject:==
Crystal River Unit 3 - Submittal of Non-Proprietary Information Re: Proposed License Amendment Request #270, Revision 0, "Power Uprate to 2568 MWt" (TAC No.
MB5289)

==References:==
: 1. FPC to NRC letter, dated June 5, 2002, Crystal River Unit 3 - License Amendment Request #270, Revision 0, "Power Uprate to 2568 MWt"
: 2. FPC to NRC letter, dated September 30, 2002, Crystal River Unit 3 - Response to Request for Additional Information Re: Proposed License Amendment Request
                       #270, Revision 0, "Power Uprate to 2568 MWt" (TAC No. MB5289)

==Dear Sir:==

By letter dated June 5, 2002, Florida Power Corporation (FPC) submitted License Amendment Request #270, Revision 0, "Power Uprate to 2568 MWt." In response to an NRC request for additional information dated September 30, 2002, FPC provided proprietary Framatome ANP document, FRA-ANP 51-5015662-01, "FIV Development, Qualification and Clarification for TMI".
The attachment to this letter provides the non-proprietary version of Framatome ANP document, FRA-ANP 51-5015662-01. Also being provided for NRC review is the non-proprietary version of Framatome ANP document, 86-5022636-00, "CR-3 PT Fluence Analysis Report - Cycles 7-10".
This letter makes no new regulatory commitments.
If you have any questions regarding this submittal, please contact Mr. Sid Powell, Supervisor, Licensing and Regulatory Programs at (352) 563-4883.
Sincerely, Dale E. Young Vice President Crystal River Nuclear Plant DEY/pei Attachments:
A. Non-Proprietary Information - FRA-ANP 51-5015662-01, "FIV Development, Qualification and Clarification for TMI" B. Non-Proprietary Information - FRA-ANP 86-5022636-00, "CR-3 PT Fluence Analysis Report
            - Cycles 7-10" xc:        Regional Administrator, Region II                                                                        A/ &#xfd; Senior Resident Inspector NRR Project Manager 15760 West Power Line Street
* Crystal River, Florida 34428-6708 * (352) 795-6486

U.S. Nuclear Regulatory Commission 3F1102-11                                                                                  Page 2 of 2 STATE OF FLORIDA COUNTY OF CITRUS Dale E. Young states that he is the Vice President, Crystal River Nuclear Plant for Progress Energy; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.
Z;
                                                                                   , 671 Dale E. Young            /
Vice President Crystal River Nuclear Plant The foregoing document was acknowledged before me this 25-/ day of                 A/overn beA 2002, by Dale E. Young.
(Print, type, or stamp Commissioned Name of Notary Public)
Personally                 Produced Known     _    _    -OR-   Identification

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT A License Amendment Request #270, Revision 0, Power Uprate to 2568 MWt FRA-ANP 51-5015662-01, "FIV Development, Qualification and Clarification for TMI" NON-PROPRIETARY

20440-9 (2/2002) f A                                                  ENGINEERING INFORMATION RECORD FRAMATOME ANP Document Identifier 51 -      5022444- 00 Title    FIV Development, Qualification and Clarification for TMI (Non-Proprietary Version of 51-5015662-01)
PREPARED BY:                                                 REVIEWED BY:
N;me           JA Burgess Jr                               Name          RR Schaefer Signature                                 Date-'--Z Signature                                      Date Technical Manager Statement: Initia Is Reviewer is Independent.
Remarks:
During a meeting with the NRC and TMI, a number of questions were presented with respect to the development of the Framatome ANP Flow Induced Vibration (FIV) methods for application to the OTSG. The historical, experimental, and analytical basis for the FIV methodologies is presented herein.
This document is the non-proprietary version of the proprietary document [51-5015662-01 or Reference 12]. In order for this document to meet the non-proprietary criteria, certain blocks of information were with-held based on the following criteria.
a) Information reveals cost or price information, commercial strategies, production capabilities, or budget levels of FANP, its customers or suppliers.
b) The information reveals data or material concerning FANP research or development plans or programs of present or potential competitive advantages to FANP.
c) The use of the information by a competitor would decrease his expenditures, in time or resources, in designing, producing or marketing a similar product.
d) The information consists of test data or other similar data concerning a process, method or component, the application of which results in a competitive advantage to FANP.
e) The information reveals special aspects of a process method, component or the like, the exclusive use of which results in an advantage to FANP.
f) The information contains ideas for which patent protection may be sought.
I t.: 10

A FRAMATOME ANP                               Non-Proprietary     51-5022444-00 Record of Revisions Revision       Section       Description                               Date 00         All            Original Issue                           11/2002 FIV Development, Qualification and Clarification for TMI Non-Proprietary Version of 51-5015662-01                         Page 2 of 10

A FR A MATO ME A NP                              Non-Proprietary                                  51-5022444-00 1.0    PURPOSE The purpose of this document is to present the methodologies used to evaluate the Flow Induced Vibration (FIV) concerns of the OTSG tube bundle. This document will present both the techniques used to determine the OTSG secondary side thermal hydraulic conditions as well as their application to the structural FIV analysis. The qualification and accuracy of the thermal hydraulic and structural computer codes used in these evaluations are discussed. Lastly, recent test results of the cable stabilizer damping properties in regard to the fixed boundary conditions at the tubesheets and tube support plates, which result from an over-pressurized swollen tube, are presented.

==2.0     BACKGROUND==
OF ORIGINAL OTSG TUBE FIV DESIGN CONSIDERATIONS In the initial developmental stages of the OTSG design, which occurred during the late 1960's, Babcock & Wilcox performed numerous tests to assess the heat transfer characteristics and structural integrity of the OTSG shell and tube bundle. The mockup of the OTSG design was similar in length and other pertinent design considerations to that which was constructed for commercial operation with the exception of the number of tubes. The OTSG mockup was limited to 37 tubes. The OTSGs in service today have nearly 15,500 tubes.
The stability of the OTSG tube bundle was examined through qualitative test data and the experience on stability that were available when the design was first conceived. To provide the necessary confidence in the stability of the OTSG tube bundle, Babcock & Wilcox conducted an extensive research and development program to ensure that the OTSG tube would be fluid-elastically stable.
The objectives of this program were to:
(1) Determine experimentally the stability characteristics of the OTSG tube at design conditions; (2) Study experimentally the effect of various operating and physical parameters on the stability characteristics of the OTSG tube; (3) Develop an analytical tool by which the stability limits of the OTSG tube can be predicted.
A large amount of literature on the subject of fluid-elastic instability was reviewed and evaluated which provided an understanding of the phenomenon and led to an analysis code by which the stability limits of the OTSG tube bundle could be assessed. This code was also used to evaluate tube support plate configurations based on the instability ranges of the tube bundle. The capability of the analytical model used to evaluate the stability of the OTSG tube bundle was compared with the test results and other boiler designs currently in operation and found to predict the instability of a tube bundle with reasonable assurance.
Since the stability of the OTSG tube is directly related to the natural frequency of the tube, vibration testing was performed with a 0.625 inch OD Inconel tube 625.375 inches long, with a wall thickness of 0.035 inch. The tube was fixed at the ends to simulate the effect of the tubesheet and was supported between the ends by supports similar to those in the manufactured OTSG. The objective of testing performed with this mockup was to determine the possibility of buckling, vibration, and wear.
FIV Development, Qualification and Clarification for TMI Non-Proprietary Version of 51-5015662-01                                                          Page 3 of 10

A FR A MATO ME A N P                              Non-Proprietary                                    51-5022444-00 Vibration pluck testing of tubes on the actual fabricated commercial OTSG was performed in order to demonstrate that the production unit's vibratory response is in agreement with the sample tube test discussed above. The tubes tested in the production unit were found to have an average natural frequency of 47 Hz. This compared closely with the predicted value of 45 Hz.
The damping ratio was a second item considered in this program. In the single tube test, the average percent of critical damping was[           )b. 'tn the production unit test, the average percentage of damping was aboutl I ., 4 In conclusion, the pluck testing performed on the production unit demonstrated that the single tube laboratory testing as previously determined was representative of actual condition in the as-built OTSG units.
3.0   METHODOLOGIES FOR DETERMINATION OF THERMAL HYDRAULIC INPUTS FOR FIV ANALYSIS Flow loads on OTSG tubes were originally based on tests on a scale model boiler described in Section 2.0. The velocity and density distributions in the top span were based on the following assumptions:
        "* The steam density is[        ]lbm/ft3 and is uniform over the top span and over the entire cross section of the OTSG.
        "   The axial velocity distribution follows the[                          .' tubes.
: t. Thus, T,,c the actual cross flow velocity for each   tube was[
1.b, d The secondary side mean velocity flow conditions, that were determined from testing, varied from tube-to-tube over the cross sectiop of the OTSG. The maximum peak factor (ratio) from the mean velocity in each tube was[ 3aq *C "orthe TMI VTSGs. The highest flow load occurred at[
                               "1,at which the mean cross flow velocity wasE            fs. The highest predicted mean cross flow velocity for tubes['
3 'lI/sec.
Framatome ANP now uses a modified version of EPRI's "PORTHOS" computer code to predict detailed thermal-hydraulic performance of the OTSG. "PORTHOS" is a three-dimensional computational fluid dynamics computer code that models the tube bundle between the lower and upper tubesheet secondary faces. This modified version of "PORTHOS" has been adapted for OTSGs and its accuracy has been documented in Reference [7]. The OTSG thermal hydraulic model includes the aspirator port, tube support plates, peripheral gap between the tube support plates and the shroud, open tube inspection lane, and steam annulus. The current version does not include the feedwater downcomer, but does include the effects of steam-condensation heating of the feedwater. Applications of this code have included calculations of:
(1) cross flow velocities and dynamic pressures in the upper span to support power uprates and definition of tube stabilization criteria, (2) moisture distributions in the upper span and at the upper tube sheet to establish localized and overall tube plugging limits, and FIV Development, Qualification and Clarification for TMI Non-Proprietary Version of 51-5015662-01                                                            Page 4 of 10

A F RA MATO ME A N P                             Non-Proprietary                                  51-5022444-00 (3) mixed mean steam temperatures to support overall tube plugging limits.
The OTSG tubes are spaced on a triangular pitch. Thus, the tube orientation provides what appears to be a staggered alignment in some directions and an in-line alignment in others. The PORTHOS computer code models this effect using several parameters to account for the "porosity" of a steam generator tube bundle in its formulation. The volumetric porosity is used in the computation of cell pressures and the directional porosity values are used to compute gap velocities between the tubes.
The directional porosity values are input for the axial, radial, and azimuthal directions.
It is believed that the hydraulic resistance of the tube bundle does not have a significant azimuthal dependence and the azimuthal variation in radial velocities is small. Thus, in PORTHOS modeling, the smaller of the two porosity values are input for both the radial and azimuthal porosity. This maximizes the velocities and is therefore, conservative. Framatome ANP is unaware of any test data that would confirm or refute this azimuthal variation of radial velocities.
The accuracy of the PORTHOS thermal hydraulic code and methods have been verified and thus its use in safety-related calculations is justified through favorable comparisons with model scale testing and plant data, References [9 through 11]. These comparisons include:
        "   Two different tests on 19 and 37 Tube Model Boiler tubes defining axial primary, tube, and secondary temperature distributions over the axial length as well as secondary pressure distributions
        "* Babcock-Atlantique Tube Bundle Cross Flow Velocity Distributions (with and without internal AFW headers)
        "* Plant Mixed Mean Steam Temperatures for 2568 Mwt nominal, 2772 Mwt nominal, 2568 Mwt with high peripheral plugging, and 2568 Mwt with three-tube wide inspection lane.
Many of these comparisons are presented in Reference [7] along with the comparison with plant mixed mean steam temperatures. Therefore, the use of PORTHOS to predict the OTSG secondary side conditions in the top span is justified for use as inputs into subsequent structural and FIV calculations.
Since PORTHOS lacked a turbulence model, corrections are made to accurately model the lower span of the OTSG. This short coming in PORTHOS limited the ability of the model to represent effects of fluid entrainment by the flow of streams jetting through the downcomer orifice which would be required to accurately predict the formation of any recirculation eddies.
Modifications to the PORTHOS coding have been made for the purpose of adding capability to model the orifice plate openings, lower downcomer, and baffle ports in the inlet region of the OTSG.
PORTHOS models of the Chalk River (See Section 5.0) and ARC SG model configurations have been made and results compared with test data. PORTHOS results for velocity distributions over the SG inlet region at the tube bundle outer radius are considered reasonable. A conservative method is used to extrapolate velocity distributions at the outer radius to other radial locations within the lower bundle.
FIV Development, Qualification and Clarification for TMI Non-Proprietary Version of 51-5015662-01                                                          Page 5 of W3

A FR A MATO ME A NP                               Non-Proprietary                                  51-5022444-00 4.0    FIV ANALYSIS METHODOLOGIES The general guidelines and methods employed by Framatome ANP for FIV analysis of heat exchanger tube banks are given in References [2 through 4]. For a virgin tube model, a single tube is modeled using finite element techniques provided by the Framatome ANP computer code "CASS". The tube is fixed at the secondary faces of the upper and lower tubesheet and pinned at all tube support plate locations. The effective mass of the tube, including the primary and secondary fluid, is considered in the modal analysis.
Once the frequencies and mode shapes of the tube have been determined, the Fluid-elastic Stability Margin (FSM) of the tube is evaluated with the Framatome ANP computer code "PCSTAB2". When a tube bundle is subjected to cross-flow with increasing velocity, it will come to a point at which the responses of the tubes suddenly increase without bound, until tube-to-tube impacting or other non linear effects limit the tube motions. This phenomenon is known as fluid-elastic instability. The "PCSTAB2" computer code determines the margin against this instability of the tube from inputs such as;
         "*  The mode shape eigenvalues from the modal analysis,
         "*  Connors' constant,
         "*  Damping values,
         "*  Cross flow gap velocities,
         "*  The linear mass densities of the tube, including non-structural and added masses
         "*  Secondary side densities.
The computed Fluid-elastic Stability Margin (FSM) is the ratio of the critical velocity of the tube bundle (or the velocity at which the tube bundle is predicted to become unstable) to the equivalent mode shape weighted pitch velocity. An FSM greater than 1.0 implies that the tube is stable while and FSM less than 1.0 implies that the tube bundle is unstable. The minimum acceptable FSM for design is 1.0.
The stress from random vibration of turbulent cross flow is determined with the Framatome ANP computer code "PCRANDWIN". These vibrations are small in amplitude and always occur below the critical velocity and away from the vortex lock-in region. These small amplitude vibrations always exist and are caused by the turbulent eddies in the flow. The "PCRANDWIN" computer code determines these stresses using the coherence integral method and from inputs such as;
         "* The dynamic pressure ( 2pV 2),
         "* Damping ratio due to small vibration,
         "* A table to introduce the frequency dependence of the random lift coefficient and the correlation lengths The vibration amplitudes due to vortex shedding are only computed for tubes located at the periphery of the bundle, as it is believed that the required vortices will not develop intra bundle. This response is also determined with the Framatome ANP computer code "'PCRANDWIN". When vortex lock-in does occur, the forcing function becomes fully correlated over the span of the tube. Thus, vortex induced vibration is determined by assigning a very large correlation length to the tube spans. The inputs for this analysis are similai to those provided for the turbulent buffeting vibration.
FIV Development, Qualification and Clarification for TMI Non-Proprietary Version of 51-5015662-01                                                          Page 6 of 10

A FRAMATO ME AN P                                   Non-Proprietary                                   51-5022444-00 5.0    VERIFICATION OF FIV METHODOLOGIES The Chalk River Nuclear Laboratory performed a stability test on a full scale model that consisted of the lower three spans of the B&W 177 Fuel Assembly OTSG. The actual span lengths, support plate thickness and tube-to-tube support plate clearances were properly simulated in this test. Results of ,
these tests show that the tube bundle[
lb/sec [Reference 5].
An analytical model of the Chalk River test tube was created to evaluate the FIV techniques and methodologies performed by Framatome
                                      ,h           ANP [Reference
                                                           ,eeec      6]. The anaytca 6]      analytical mo   Ispr models       i predicted an FSM of[ ]when using a Cornors' constant of[ Itn         3, axial damping value oft I ani a perpendicular damping value of[ J'o-"     the test above. Therefore, the overall analytical model predicted the instability threshold to within approximately[ 1.6 Framatome ANP has consistently used a Connors' constant off Ifor single phaqe lows in the bottom and top spans. An axial damping value oA              and] a perpendicular value of[ 3 are employed in the FIV analysis of OTSG tubes. The[            'hxaxialdamping is used to account for the frictional losses occurring between the tube and tube support plates as the tube slides vertically through the support plate. The contradiction in the constants employed in Framatome ANP FIV analysis and those determined from the Chalk River test can be in part eradicated through the relation of damping and the Connors' constant. The Fluid-elastic Stability Margin of a tube is proportional to the following parameters; The combination of these two input parameters is believed to be realistic and not overly cons erv~ative by industry experts in the field of FIV. 1 closely corresponds to the Connors' constant of[ I apA[
damping oft[               6,4         3 16 sumed in the calculation to correlate with the Chalk River test results. When P4= land &#xfd;=j j inputs are used, the fluid-elastic stability margin predicted for the Chalk River test setup is[ 3, %'hat    is, with an accuracy of about&#xfd; 3
* The uncertainties in calculating the FSM come from; (1) uncertainty in the fluid-dynamic input; (2) uncertainty in the damping ratio; (3) uncertainty in the stability constant.
Framatome ANP addresses (1) by using two different sets of input from two different sources, including the input from the "PORTIlOS" computational fluid dynamics code and the older estimates that were actually extrapolated from a scale model test at the time the OTSGs were being designed.
When all other input parameters are the same, the FSM values computed with these two different sets of fluid dynamic inputs are comparable, with the "PORTHOS" input giving results that are believed to be more accurate due to its more detailed modeling capability. Itenps,(2) and (3) are addressed together by using a conservative estimate of damping ratio of[J"or looyely supported multi-span tube together with a conservative value for the stability constant[ ".
FIV Development, Qualification and Clarification for TMI Non-Proprietary Version of 51-5015662-01                                                              Page 7 of 10

A FRA MATO ME A NP                                Non-Proprietary                                  51-5022444-00 A test conducted at Babcock Atlarntioue over 25 years ago showed that the stability constant for the ,
OTSG tube bundle was aboutt Jwhfile most of the industry data show stability constants overt .
An in-air test of the full size OTSG conducted 25 years ago showed that even with moderate vibration amplitude well below the half tube-tube gap clearance, damping ratios mostly exceed[ )i*eceni           test in the lab using a one span beam with real OTSG support showed a damping ratio close to&#xfd; jeven for vibration amplitudes in the 0.01 inclrnge. Therefore. Framatome ANP believes the computed FSM for the OTSG tube is within[ J accuracy.
Finally, we compare the final result with field experience. No OTSG tube in the designed condition has ever failed because of fluid-elastic instability. The latest incident regarding the severed tube at TMI verifies the technique. When testing was performed on an OTSG tube expanded against the support plate, the damping ratio significantly decreased. With this reduced damping ratio as input, the analysis showed that indeed tube 66-130 would be at the threshold of instability.
6.0    FIV DAMPING VALUES Recent testing of the OTSG cable stabilizer to determine the additional damping the cable provides to the tube/cable system is presented in Reference [8] and summarized in Table 6.1. This testing was performed to determine the additional damping produced by the OTSG cable stabilizer in an over pressurized tube where the tube becomes locked into the tubesheets and tube support plates due to swelling of the tube. Several configurations are tested and the results for each system are summarized below.
Framatome ANP has traditionally usedl ] normal structural damping associated with non-linearity of the tube to TSP clearance. The test resujts shown in Table 6J. show that the non-linearity of the tube to TSP clearance provides aboutf j *)amping. About [ o thi      t    damping is lost as a result of a swelled tube. When the tube pressurized, approximatelyl T acfaitional damping is created. Since a pressurized tube would tend restrain the tube more, it was concluded[
bahittonal damping. This trend was also prevalent in the virgin tube and stabilized tube tests.
The viscous damping effect of secondary side fluids surrounding the tube that are in single phase is small, especially at temperatures of 550F, and is not typically considered in FIV analysis. However, 2% additional damping can be accounted for in the lower spans of the OTSG tube bundle where the secondary side fluid is in the two-phase mixture region.
FIV Development, Qualification and Clarification for TMI Non-Proprietary Version of 51-5015662-01                                                          Page 8 of 10

A FRAMATOME ANP                                  Non-Proprietary                                   51-5022444-00 Tab 1e 6.1: OTSG Cable Stabilizer Damping Results [Reference 8]
Support Test Case Swelled Tube Pressure Environment Stabilizer TS Sever                    Arrangement     Damping (yes/no)        (ksi)    (air/water)    (yes/no)      (yes/no)                      (avg)
Baseline          no            0.0          air           no           no           (TS-TS)               ""1 I             nio           0.0          air           110          no        (I S-D-B-TS) 2             yes           0.0          air           no           no        (TS-D-B-TS) 3             yes           0.0          air          yes          yes        (TS-D-B-TS) 4             no            0.0          air           no           no        (TS-B-B-TS) 5             yes           0.0          air           1o           no        (TS-B-B-TS) 6             yes           0.0          air          yes           no        (TS-B-B-TS) 7            yes            0.0          air          yes          yes      (Sever-B-B-TS) 8             no            0.0          air           no           no         (TS-B-B-B) 9              no            0.0        water           110          no         (TS-B-B-B) 10            yes            8.0        water           no           no         (TS-B-B-B)
II            yes            5.0        water           no           11o        (TS-B-B-B) 12            yes           0.0         water           no           no         (TS-B-B-B) 13            yes           0.0          air          yes            no         (TS-B-B-B) 14            yes           0.0         water         yes            no         (TS-B-B-B) 15            yes           8.0         water         yes            no         (TS-B-B-B) 16            yes           0.0          air          yes           yes       (Sever-B-B-B) L           -J Notes: TS - Tubesheet Bore D - Drilled Hole B - Broached Hole Summary of Damping Results:
Damping of tube (Fixed-Fixed)  = r Average damping of virgin tube in air =
Average damping of virgin tube in water =
Average damping of expanded tube w/o Pressure =
Average damping of expanded tube w/ Pressure =
Average damping of expanded tube & stabilizer w/o Pressure =
Average damping of expanded tube & stabilizer w/ Pressure =
Average damping of swelled tube & stabilizer, with sever at TS, w/o Pressure = L           J FIV Development, Qualification and Clarification for TMI Non-Proprietary Version of 51-5015662-01                                                           Page 9 of 10

A FRAMATOME ANP                             Non-Proprietary                                51-5022444-00

==7.0 REFERENCES==
: 1)                                                    "Once-Through Steam Generator Research and Development Report", dated April 1971.
: 2)    Ben Brenneman "Random Vibrations Due to Small-Scale Turbulence With Coherence Integral Method", ASME Journal of Vibration, Acoustic, Stress, and Reliability in Design, Volume 109, April 1987.
: 3)    M. K. Au-Yang, "Flow-Induced Vibrations of Power and Process Plant Components," ASME Press, 2001. Chapters 7 and 9.
: 4)    ASME Section III, Appendix N-1300 Series Non-mandatory Code on FIV Analysis of Tube Banks, 1998 Edition.
: 5)    Once-Through Steam Generator (OTSG) Fluid-elastic Instability StudyL 3 b"d b1 4
: 6)                                              3, "Flow-Induced Vibration Analysis of TMI OTSG Tubes due to Power Uprate", dated June 1997.
: 7)    Moore, R.W. "Adaptation of PORTHOS to the Once-Through Steam Generator", Presented at an American Power Conference.                   b6.
: 8)    E                                        ] , "OTSG Cable Stabilizer Damping Test Results",
dated November 2001.                        6jA,
: 9)    1                                        3 ,"PORTHOS for OTSG Application", dated January 1996.                                       ,
: 10)                                              "","OTSG Top Span Conditions - PORTHOS", dated April 1996.                                bA
: 11)  I"3                                         , "OTSG Local Tube Plugging Limits", dated November 1998.                             6,A
: 12)  U      m    1-I                               , FIV Development, Qualification and Clarification for TMI", dated 12/2001.
FIV Development, Qualification and Clarification for TMI Non-Proprietary Version of 51-5015662-01                                                 Page 10!of *10

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT B License Amendment Request #270, Revision 0, Power Uprate to 2568 MWt Non-Proprietary Information - FRA-ANP 86-5022636-00, "CR-3 PT Fluence Analysis Report - Cycles 7-10" NON-PROPRIETARY

20)697-6'(2/2002)
A                                                               CALCULATION.

==SUMMARY==
SHEET &#xfd;(CSS)
Document Idcntifjt '86 &#xfd;-,5022_636 -_00 Title      *Ck-3 PT FLU EN CEMAALYS IS REPORT -'CYCLES 7-10 PREPARED BY:                                                           REVIEWED BY:
METHOD:~        DETAILED CHECK'L      INDEPENDENT CALCULATION NAMIE      JAMES WM NEWMAN. R.                                        NAME      'J. Nj3YARD SIGNATURE.-/t)                                                        SIGNATURE        \L         X '
DATE         '11/22102    TITLE i1_4
                                                                               ~ENGINEER1I
                                                                                                    -4 DAT7E     [       aj TITLE       tn_&GNEER 1Ill COST jCENTER        .411016 REF.
PAGE(S)        12-13 IM STATEMENT:
REVIEWVER INDEPENDENCE          _,.t1ow PURFPSE AND '8UMMARYOF RESULTS:
Th&#xfd;is aoduiierit summ'arizes the re's'UUlt      &#xfd;fromt~CR-3PT F166hcbAhtily&#xfd;Is fdricy~Ies 7-10. Fast Fjlbence Values (or 15, 32,
,and 48 EFY werf 'c6mfr'U 'dfor th'e fl'ol~vd~ldi~aU66n
      & Pressure Vessel In- 1de'SuifS66 Maiximbm- L66atkn_
0     WF-8 and WF-1 8 Longitudinal W~elds (upper shell) a -SA-1 580 Longitudfniil Weld (lowemrshell)
Sk 1769 Circumferential Weld (max location)
        *W-F-70 Circbimferential WelI d (max location),
* Levier Plate MaximurfiLbC66-tioIY
          ' Upper Plate Ma~iiimur Lbc~li6r lTH    FOLLOi Nd COMPOUTE&#xfd;R CODjES HAVE BEEN USED IN THIIS DOCU-MEN'T;                THE D'OCUMENTCONTAINS ASSUMPTIONS THAT MUST BE VER IFIED PRIORTO USE ON SAFETY.
RELATEDWORKpj C.ODENVERSibNiREv                               CODENERSIQN!REV
____________            ___________                                D       YES                        No Page       IL of _,23'

CR-3 PT FIu~nciArnalysis Report,-Cycles 7-40                  Cailc. #!; 86-5022636-00
                                                                              ,hge2 of 23 IRCbrn    of Rm~sion Rcvis~ion Number                                 esriptio 00                                     bOiiginai Issuc Framaiome ANP                                                          Fr~iratorn ANPNon-Proprietary

CR-3"PT fluence Analysis Report, Cycles 74-0                                                                       Cale. #: 86-5022636-00 Page 3 of23 Tableo* Contents 1.0   Intr~duction ........................................                              :
2.0   Fluence Resutltsf ................................................................. 5 3.b   Dosimetry Actvity .....                  ..                ...               ...... ......... ...        .,            ... ,....              10
.4.0   Refereh~e&#xfd;..     -, ................. ...........          .........    ... ..............       ....................
                                                                                                       ....                       ..           .... 12 AppendixA   -'Mcthodalogy         ......... ..    .   ..........            ............................                       .. ............
                                                                                                                                   .                1 Framatome ANP                                                                                                                 FNon-Proprietary

CR-3 PT Fluence Analysis Report, Cycles 40                                           Calec. P: 86-5022636-00
                                                                                                        ~Page 4-of 23 1.0        INTRhODUCTION Over the last fifteen years FrarnatomeANP (PAIP),has developed a cnakulafi6nal based flu~rfde'h~dlyes~is ithodolo~gy,' that caSib ii~&dieiai nciUditcly predict-the fasf necution fluence in the rea~ctor v,&#xfd;ssel using surveillance capsule, 86simctry or cavlity d(Iosunetry(or both) to verify the fluence predfictions.-      This methodology :Whs de~ielo 1 5d through&#xfd; ii -full-sicale b~nchxriark ex&#xfd;&#xfd;0riffeicftifrit:* -vs 'i~rf~riiid ut ihcl aV-i'i-iBcsselU nit I rcnctior-t and the rnihod'ology is
.Aescribe8 in .deitalt in ,Appendix A. The restilts of-the-benc'hmark-,xperilinnt 4emonstrated that
-4he accur~qy-bf afluence qnaly~is th6t: t              flosTeTAI4,P        cn'thod~l56Pi     l&#xfd;d~be:',hbiased and Iiave-dprec~isi'ori well within the'U.S Nuelearliegul~tory buide i.190 ini iof2O, TelY                                           III eir                          foeylc 7-%
The-TN? mthodology was used           etoclculate'the neutron fluencce7xpbr~rcyls7
: 8. cy~cle 9 arid cyble 10,of the Cry)stW River`,3 niclc'ar        fcacto Ir.`The methfodology. Was iziso~s    used to cstiinate fluences on thie inner surface of threaco vcslwell as at spcci -ficd wel-d locations on the 'vessel surface- The fast neutr6n ;fiuenc6'(13>1 MeV) ait ca~li 1&ttri na                     ~aulaad ,in
.Uc66rkidncice Nwith'the ufe4uirifment&#xfd; of Uf.S.%6uedar Regul1atory Guide 1.1 -90" The cnergly-:dependent flux on the ylq9adcycle 1,0 ,capsulcs;'wasu~sed W'~detehimine the -dalculated, activity of ecich dosini~tex_. -NWi'ir6n, ti~ihspori c6lctationfs fin'             ':tw6;diiin"'n geomctry, wecre Uised to obtain energy dcpendent "flx distr ibutions throughout t~he core. Reactor conditions-were representative of an ayeragd over the bycleJ- iriito                          eid       ~     s 9and 10 -%e'rc tre~ated inravidu~ll, 'since thcre' waisir do-simetei capsule fdf' each c-ycl'e.               G'Cometiic
 ,detail was.sdlected to, excplicitly represent' ihe d&simeter holdermTnd the reactor vessel. Amore detailed, discussion 'of the calculational proebdure is given, in Appendix A. The calc~dated ncdtivities ,*eer,-djttstcd for l iownm biases ,(piotoflissior, &#xfd;bho~-h&#xfd;alf~ifc, 1J-235 JImpurity, and non saturation), and compared to measured activities directly. It is noted that these measurements are not usted in any wayto determilne the magnitude bf th6 flux, or the fluecriei. The Meiasu'rements are Frarnatorne, AiTNo-roretr                                                                         Non-Proprietary

'.CR-3'PT Fluence Analysis Report, Cycles 7-10                               &#xfd;Cak. #: 86-5022636-00 Page 5 of 23 used only t6 show.that the calculitionaf results are reasonable, and to shom;r that therestlts for the
  ,CR-3',ostmeters are consistent with the FANP,benchtiark databasc of hiertfiuriti6s.
J2.0     FLUENCFE RESULTS
          -Thrce irfrdiation periods we&r& hdal*t"'iM sprtbf the CR-. PTMil ence annalysiA, one for
  &y6le4 7-, pone &#xfd;focycle 9, and one foi cycle 16;0 ',les    7 and 8 operated for a total irradiafion pernfo of 1033.8 EFPD, cycle 9 for 557.2 EFPD and cycle 10 for 592.8 EFPD.,
          "Th- ihcid6fit fast fluchne(E>&#xfd;1;O MNW ) w-as calculated on ihe inn-er surface otf the reactor ressel, The layout ofthe reactor vessel ti sshown in igure 2-1L Framatome ANP                                                                         "Non-'Proprietar,

CR-3 PrtFlunce Ana'lysis Report, Cycles 7 10,                       Calo. -#: 86.5O22636-OO Piage 6 o423 tAir S ac
          -rM $111eld
                                                                                       .CPsule
                                        ~~Jj ~~t77~       ~          50.282 217.4 d!imensions in cm cirawinu NOT to scale Figure 2-1., CR-3        omtyO rve Framatome ANP                                                               Frnniatme on-Prdpri-iary ANP

p CR-3 iPT Iluerice Analys~is RePqrtq~vles 7.10,                                        ab    :8-5022636-00 Page 7, or23 T-lux estimnates were znade for ,several points on-the .inner surfacE f the xeac - -r vessel.
these estimates are of p~aticiilaz~i i 6rta- 66 in -6e-termin-ng_ Nleffc ofnurnfu eo h 0opertics , f'the v~sseI .Surffice ind welds. "The po -ints of intercst,, and'thfa calculated flu)'-b'y cycle; we shown;in Tle2-1, Table. Lj*3D Synthesized l~uxes Cycle__Length__Cycles                  7anil               grcld9                     'CIC    10O
_______________   -1033.'S                                     557.2                        592.8 (EPS                 .9320M7.               4.8l42E37                    5,121 SET.
Tlux'Location                         -E>1].O            MeV Flux (n/crnV/S Inside Surface Max. Flux                 6.17309                  6.495U                      '7.162E9 1S AA 769 Peak Flux                  ;5.524E-9                '5.93 1E9                    16.250B9 VF-70 Peak Fl ux                   6.919E9                 :E-1159119                   *6.90SE9
    'NU-SAVF- 18 Peak Fluwx                 '5.762E-9                .5.86SE9                     .6.602F.9 SA- 1580 Peak Flux                   :5.5239                  '53 13E9                      6.232139 Lower Plate Mak 11lux                  ;6,,169E9                '6,303E9                     &#xfd;7.1I62E9 Upper PlateIa~xFlux                    '6.173E9,                 6.495E-9                    -i7,084139 Fluences -for -the vessel 'cati als6,bC_ _xtr-a_ olaiWd 1o ldngr iirnc periods in order to
  ,estin'a6 teotal fli-eiic-s o'n the poinits of inkre-st. This extrapolation is performed by assuming that
  .the average 'fluence on t16 -vess'I for- the'extrapolated time i&#xfd; at 'eqiiili1briumi at the cycle 10 flunc. Tisassmpi~ is~ceptbl        iroviddthtch subsequent cycte-shows an equal or dec'linin'g' maxim-rum fluence on the vessel surface. E'nd' of lite fluences are determined by taking the cumulative fluence and then extrapolating forward. -The cumulative fltcicfce values for CR-3 through cycle 10 are A6bown in Table 2-2, nloinj,with the extrapolated ROL Iluence at 15, 32, anud 48 'EFOY&#xfd; 'The end of life (15, 32, or -4'8'EFPX) Tfluences,'are calculatdd u~ing the folloNing, formula-F-ramatome ANT1                                                                               Non-Proprietary o-rpitr

dmv zwol=wd.
of 1,lScH:jjojaquinu[iqojpqj I  owo :)Iok:Djoj xuU. oq&#xfd; st 010 101 ojog6jq pu,3,.itlllu zouanU OT st, (OI0Oa),V(A-Jq SV&#xfd;9'u'ffl oj!Ippud oql ju olmij6-D uo- &#xfd; 6LD
                                                                 -o n         si ("16:1)j ziaqsk (W"',) *,010+ (ooo at)&, (&#xfd;oq)s, EZJO aa3ed oc&#xfd;qozzog-qg    -.4 -31BD:                 o I-L                   it!;,(IUUV oauzq j,,l E--do

77=
CR-3,PT Flu'dnce Analysis Report, Cycles 7-10                                          Ctaic. II:8G-5022G16O00 Thlge 9,of 23 Table 2-2.,, Cumiulative F.iibife Esffihiiii's
                        ]   Increniental lwiu~efd(b/cm)______                                               u0if y         he      (Warbm)  ______           ____
Cylelux                                                   ~1                     IS3FPY         32-13F7PY,      48SEEPY
   '(I3FPD).            1033.8             -557.2,        592.8       _________________
(EFT.PS)          8-9320137    -4.814213-7          5.1218137     _____1_____
(E.FP Y):            2.83               1526           1.623         :5.876..-        11.8711                                 is               32
                                                                                                                                                   -__________     48 Flux          1       Incremental~
Loca tin                 Iceetl1Iec                nc  2 wii~v fi~side, Srae            5.'S14E17 ,3.127][317             3.6tgil      -id6:o06h1318       32130 9Ei3I1      7.5544E1         *39768613g          6ao296rtli   1.14411 SA-1769 Peak Fuctice 4.9341317        12.856r.17      3.2011317      1.790013M8        2.880n1ig-           .989~             S0~8         7.7038
                                                                                                                                            '707131 10011 1'-0'&#xfd;          '1 WP-70 Peak           5.37611-17       -2.9ii513V1     3.5316H17      L!)200131l8'      '1107~1hiSi.       7.2832-E9 WF-8/WF i - 1 8c 5.147113-17           -2.9251817       J.382E1:1      1.9400ElS8;       2.197541118           M 945lr-39, 3.82691318 3.06311:i8-7.734211- 19
                                                                                                                                           -7.399118 i.14121319 10111
                                                                                                                                                                            '1 Peak Fluence
                                                                                                                                                                            .1 Ptklune   5.51O 1          3.0341517       3.19E17       1,*2001         3.8~2012S1319        7.5744E9`          .9437413-18&#xfd;   7.964E8         L24 1
LoUper Plate         5.51413 17,       1127417        3.6681317     1.9300MI18         3,212EO18         '7&#xfd;7i.5-544   -) 3971T            .9937             .1677Y1sn I
Max Fluence Framninorne ANP`                                                                               1*cn-PoFi~etary 9'
j

CR-3 PT Fluence AnaIy3ls sReport, Cyc--P        _les 7-10                            C61c.-#: 86;.5022636-06 Pagel10 of 23 3.-0       DOSIMEITR&#xfd;Y ACTIVITY The ratio (if the spedileed aetiyities to the nie'asured s'~ii      '~'is(OM~),is presentcd
 ,irvTablc 3-1 fot Zycles,9,and 16.' In this ta'ble,Athe target avcragcd CM- represents-the average of all the
 ,indhividual target doshrniters and the overall averagc is the averagc C/IM for the entire cnp'sulc.
TAlc-3-1.- &#xfd;CIINratios I-DosTypcj            'Dosimeter-
______13_____I
_______                   '111                               _____________',AVG (bbare)                                                                                                    Y11YPE     J Fe (b)                  F              1.9411E+00       1.897E+00          -1.023E3+00 Fe (b)                  G             'l.941E+00       1.92]E+f00          !l.0I0E+00 FeL)                     3             .1.9411;+00)     1.930L-+00'          1:00o61+00 Te(b)                  AA              1;941E+00        1.9 11E+00    I     1.016E,+00                  -1.021.E+00 Fe                   1 H              1941 E+00        1.897L-400'         4.023E-+00 Te                 -AB              1.941 E+00      :L887E+00-           'I029E-+00 PC                  AC             1:.94113+00      1:944E+f00            1.053E3+00 Te                     I                       1        92713+00
                                                                 .9130             1.007E3+00          _________
tNi                 AM               3.618C3+00,      3.382E3+00          -1.070E3+00
         'Ni                 -AN              3.61814-+00     3.371E+00            -1.073F-+00                 :013O
         -NM                 AO               3.6181.+00,     3.449E3+00            1.0491:+00 Ni                  AT             3.618E+00        3.4144E+00           &#xfd;1.05113+00 cu                   G              15.997E3-B       6.034E3-03          '9.939E-01I Cu                  -11            -,5.'997E3-03    .5.975E-03          -1004F3-+00                   9.99513-01
         &#xfd;Cu                    j             5.997E3-03       5.9S3E-w3            1;002E3+00 Cu                    .1            5.997E3-03       6.008E--03         .9.982E-01           __________
U-238             B341.J238            '7.178E-03      '6.945F--03         71.034E3+00                   1'.034E+00 Nrb                   A             :'5.682&301      -4.85213-0            1.171E3+00
         'Nb                   B             'S.6S2E-01l      '4.8241301            1.178E-+00                  1,189E3+00 Nb                    C              5.682E3.01       4.617E3-01           1.231E-+00 Nb             ~D               5.68213-01      -4.834E3-01          -1.175E-+0 0          ________
________0
_        ___OVERALL                                      'AVERAGE                         1,02913+00
______7_                                                                          sans    'Nbh&N&#xfd;i237
'Framatome ANP                                                                                 Non-'Proprictar.y

CR-3 PT Flucnce Asialysis R6jl&#xfd;rt, Cycle- j-7-b Cale. ~;86-5022636-00 Iag I of 23
                                                                'C3c1c 10
-DOSIM                        noite(s) j         c                                     I           CIA I                             -NI                             I(CIIN)   AVG BYT)"P 1'               I                   ---.-'-             -I                       I                            I____
c                                                                  173l7E+00f            '1.1~72131,00 F                                    2.'035E+00                   iL77213+00 2.0)35]E+f0                 1.76713+00              -1.15213+00 B$                                   2.035E+00 D)                                                                         1        7F-f,    .                        1.168E3+00 2.035E3400                  1.701E-400              .1.196E+ LOO
                'B      __________       2.035E+00                   ].-F 1733E-+00                 174i .,00 2.035E3+00                  1.7551f00                 .1 1013+00A 2.035E+00'                       hJ~1.I- I            .2f    E00I~
                                                  .1 E+00 ,l                                 1           n
                       -p                                               .                     L~iuL-t-7 1,;136E.+0 L14213+00 3 .2-59E-00 A                                                                 -f-.842E+00U            13147E+001 Q.QL ib-Ui r%________---~.-.                             6.27-0              603E-3F~f               1 .ULiUI AO5E-j.A                 1,.099E+f0,0 bii2lIi-03 6.2E0               6OOSEl3W~                1 10          0, U-2,                                   7.9101E-03                  7.682E3-03              1.03013+-00                1.0 12 E+00 U-2I-                                 7.910&303                   -7,957E-03              9.941 E-0)1 NBI6.25513-01                                           5.742E-01               1.08913+0                  1.0881+00 NIB-2                                   6.25513-01                  5.75613-01              1-08713+00             _______
                                                                                    -ONTALLAVEAGE1.105E3+00 F        SailS    'Np23 & Nb Frumatome ANP                                                                                     )on-Proprieta'ry Frumaome NP

CR-3 PT IHuence Analysis R~port&#xfd;Qycles 7-10                                Calc. 8:6-502263-6-06 Page 12 of 23 4.b     REFERENCE8, T        Worsbafam, J.R., -ei al.,   "Fhieic   'and Unce'rtainty Methodologies," 'BA W-2241P-A,&#xfd; Revision 1, Frama-tomc ANP;~Lynch'hurg, Vfirginia, April 1999.
&#xfd;2       U3.S. Nuclear- Regulatory ComtnissioriRegulatory 'Guide 1.'190, "Cakculational and
       -.Dosimefiy Meth&1sifdr Detcr-uniiniig Pressure Vessel N~eutron Fjuence,.;March 2001I.
3'       Rutherford, 'm. -A. N. 7%C. iassan, 'et. a]., Eds. "DORT, TvWo DinfenSional Disc~rej&
Ordinnites Transport C-dd,." BVN,&#xfd;f&#xfd;-TMy-107, Fi nt'otme Tccono1ogies, Inc;,iLyncnurg; Virg~inia, May 1995.
4        Hassler, L. A., &#xfd;and N. M. Hlassan, ttSORREL, 'DOT Input, Generatidji C~d6 Usci's MIanual," NPD-TIvI-427, Rc~isiofi 10, Fnma'oni'c 'AM', Lyn~hburg. -Virginia, May
        -2001-.
SInersllID.T.;t. t, BUGLE-3,              rodu~ti6n -and Testing of the VITAMIN-6Fn Group' a6d i1ic'BUGLE-!3B o-ad GjroupNcutron!Iphoton Cross-Section libraries Derived fro ENF/BVi         ucla    Dt       ORNL-DLC-175, *Radiation Safcty Information",
       'C0,mput-,tinal Center, Oak Rid&'Nlati6nAl-1         or~tor&#xfd;, 0 k-Ridge, Tenniessee, -April 1994.
6       Hassler, L&#xfd; A. and N. M. Ilassan. -"GTP .User's Manual 'for B&W Version, g~ioup
        ,r4anizcd 'Cross Section ]nputTPgram." NPGDM-1,456, Rvso                    1 rmtm
       .ANI', Lynchburg, Virginia;,Augs I94 7       Worsbarn, J. R.       "BUGLE-93 R6&#xfd;pqise Fuinctions," .FTG Document -N~tiribr 32-J 1232719-00, Re-V"ision 0, FiamatorneANP. Lynchbur'g, Virginia; June 1995.L 8U.S, Nuclear Regulatory Comriiission, "Rtadiation Emrbritticment of Rdactor Vessel Materials," Regulatory Guide_ 1.99, Revi&#xfd;iofi 2, May I 998 Framat6rric ANP                                                                   INon-Pr-opfietary

                                                                                               -7 77-77 CR-3 PT Fluence Analysis Re&#xfd;Pbrt, &#xfd;Cyclcs 7-10 Calc. T~r:
86-502263 6-00 Pige 13 of,23 9    Lowe, A.L.'t.j., "flflegratcd Reactor Vessel Material -Shrvcillancc rgm,'B 1543A, Rc'4sion 2, frafhatorjdANp, Lynchburg. Virginia, May195 Framnatome ANP                                                               1Non-Proprietary

INI&#xfd;_, I'll. I I          -    7-77-77r&#xfd; 7- ",- -','_I`
CR-3TTfluence Analysis Report, &#xfd;Cycles 7-10                                            Calc. #:, S6-$02263&#xfd;-00
                                                                                                   -Page 14 of 23
                                    ~APrFNjx A":ML'TIIODOLOG.V The prim~ary' tool used in the deterniindtion or the fl n                 d ?t       f Ce     sx~~
r to Th
 ,&#xfd;ucill~ance capsule dos'iiii~ters is the h6-dimbri.~n'slOl discrete ordinates transport code DOWT
     -ThcCR-J3 PT analysis covers irradiation from cycle 7jthrough cycle 10, and includesc&apsules irradia ted in cycles 9and 10. The poWcr Aistribufn in'h orird~on, cycles were s)mriiti-cboth in 0 an'd . That is,,the axial power Abapc is roughly the same 'fbr'any adhgle and, conversely, that the azimuthal. pow%,er Mliaji is the~s-i~o '.~any height. This- meais -that the iiehon -flx -t'     me point(R, 0,Z) can be considered lobe a separibic function of (R, 0) anid (
'2). Ihercfore, the cycle 7-10 irradiations 66n' be' nioddlc~d Vsinig the- stafidard FAN? synties'is procedui-es. t
     .Tigurc A-i depicts the analytical procedure that is us~*d to deterimine th&'flucnk&#xfd; acctuilulai~d'
&#xfd;os'er ech irradiation period. As sb6%Wiin'Ihc Iigiire, the-analysis is div-ided into seven tasks- (1)
&fcriartion of thie neutron sourTce, (2) development ofthieIDORT-geometry Tnrideis, (3) calculation of thle macroscop-ic material cross'sectidns, (4) synthesis of the idsulti, and (5-7) VstiniAjion of the calculalkidral &#xfd;biai, tIhe   l1ctldational imnccrtairiiy,,an'd,-fc final -huence. Each -ofi'these -tasks is discussed 'ingreaier detail in ihe foll owing sections.
     'GeheratioulofO Nhe     'ctr-6n.Sou-rce The tUmc-aVriiged                    ndeiir p~~'~ .y-&p~hdcnEineutron sour'ccs for cycles 7-10 were calculated using the SORREL4 code. 'The effects of burnup, on the -spatial distribution of the neutron source wvere accounted for-by~talculating the cycle --average "fission. &#xfd;pectrurn _fir 661h.
fissile is6t6p-c on an iisseinrIhy-!by-isscrnbly basis, and'by determining the cycl&#xfd;-avcrage specific neutron emission Tate. This data was then used with the normalized time weighted average pin-'
Framnatome ANP                                                                                 Non-Proprietany o-rpity

                                                   -    ---        r~flr
  &#xfd;CR- I PTTfluence Analysis Repor~t, C~yeles 7-10                              Calc.t: S6-5022636-bO Page 15 of 23 by'-pin "elative p6wer dcnsit&#xfd; (RD),distribution to determine the space.&#xfd;d~ndentrgy-dependdnt neutron source. The azimuthailly aVerqged) time averaed a.4;aI power 'sha~pc in'fhe peripheral.
assemblies was used with the --fis]ion~soe- runi of the peripher&#xfd;l assemblies AIo determine the iieutr6ni'sburce fro ilhe nxialbflORt run. Thcse two neutron soufce'disfiibutionis were input to 1i)Rt-as, indicated in Figure: A-1. 'Threi scparat& sources _(7-, ;r9 and 10) were developed in porder to acctount. foi thie two dim~iycf     psc thtwr raiated in cycle~s 9 arid 10.
Development of the Gcomictrka1 NMoaels Tble system geoqmetry models; for Ih6 hiid-plane (R, ,0) DORT -%eie dev eloped using standard FANP in'te-rvi, size and 'configuration gtiidelines., The RO model -,for'the Scycks 7.78, 9 hnd 10 analysis exteindeds radially fr~i~Thd cc it~i.cif the core to the outer surface of-the pressure vessel,
,and az-1muthally ,from the major atxis to 45: "iThe. axial model extends frhn&#xfd; be6Wv the active core tegibn td' iihoe .the rctivL &#xfd;oiric'fegidn. Thec geometrical models either met or exceeded -all guiidahnce' criteria concerning iiinterval size &ht~are provided in Reg Guide-l.,190.2 - Ii`,,all cases, cold 81mensions were used. Thne &#xfd;eoriietiy'&#xfd;hod~h werd inpu'in      tfc.teDORT code as'indicatcd in Figure A-1. Th(dse mo~dels; will be uised,'in all subsequent pressure-temperature curve analyses that'niay be performed by WOA-for CR_-3 C-Mlculatio'1of 1MIacioscopiclMatcrial Cross Sections In-d6cordance      ih    e Guide 1.1902 th& , 3UGLE-935 crosis section library was used. The GIlP code 6 'Was     Used   to -calculate the macroscopic energy-dependent cross- sections for all materials used in the ana~lysis -&#xfd; from 'he core '9pUt'through the cavity and inf6 the'6 Cn~rete and from coie plate 't1core &#xfd;Iate. Th& FNDF/B-VJ do'simetcr-reaction cross sect!Ions -were used to Tramatome AI&#xfd;T'                                                                        FramtomeANP'Non-Pfoprietary

CR-3 PT Fluence Analysis Report, CYClcs 7-10                             Caic. #: 86-5022 -636-00 Pag-e`16,of 23
_generate' -the response ~unce~ions that wert-,usea to calculate the .DORT-calculated ",saturated'
           'Figure A-1. fluence Analysis Metldo~loogy for CR-3 .PTT- Wnce Analysis Framatome ANPNn-rretr                                                             Non-PToprietary

tR-3    riP Fluence Analysis Report, Cycles 7-10                                Cat. #: U86-5022&#xfd;636O00 Page 17 of'23 DORT Aniilvses The c'r6ss seetios, ~geometry, and appropriate source were combined to crcate a,set ofDORT models (RO and RZ) for the cycles 7-8 ,-9;nd 10.innly~cs. Each R0 fORT riin utilized a cross
'section Legbndie :expahsion a thiree- (P,);,rty-eig'ht        -directions (Se), vith the ;appropriate
 'boifidairyconditions. The RZ .models ued Aucross tsctin 'Legendr expatision of ihidre (P3 ),
forty-ight,.directions (So), Niith the a ~joii~iie b6undar 'condiions., A theta-weighted flux 6xtrapolati'n-m6dcl was used, and Al other requirements"of Reg Guide 1.1902 that relate t6 the
 ,various DORT parameters were eithernmet or4ce-d d for all DORT rtins.
:Svnihesijed ThreebTnicitsional Results The DORT, aial2'ses produce two'sets                          fiwo-dimensional tiux  distributions, one for a vertical
 ,cylinder and one 'for the radial plane for each set of-dosimety. The vertieil cylinder, which Wrill be referrd to as the RZ plahe,,is derified us the 'l*6-e-bUonded      -bov-e and 'below the active core rcgion and -radially by the center of the -core the outside surfaee of the reactor.pressure vessel.
Tihe' horizontal plan!e: referrdd to as -the RO,pIdnedi defined 'as the-'plIn'& iunded radially by ihe center-of the core and theoutside surface of the pressure vessel, and tazimuthally by the major axis and'.the ,djaccnt 45<'-i-dius. The veesel fkLt,',*hicVer, V*iiesighificantly -in all three cyiindrical-coordinate directions (R      ,      Tis hZ).means that if a point of interest is outside &#xfd;the boundaries of botli the R-Z DORT and the R-0 DORT, the true flux cannot be determined from either DORT run. 'Under the assumption that the three-dimensional ,flux-is a sepiriable fuihction,'
both tN,6-diniensiona'l data sets \-,-ere i'ath~ma'tically &#xfd;ornbined to estimate the flux at all three dimensional points (R, 0, Z) of interest. The synthesis procedure outlined in Reg Guide 1.90W is identicdl to the basis used for the FANP flUX-synihhesis process.
Framatome ANP                                                                            Non-Proprietairy

2 T77"
 'CR-3 PT Fluence Analysis 'Report, Cycles 7-10
                                                                                        -Cale, -f: 86-5022-636-00 Page IS of 23
  ,Calcbla'ted Activiti.es a-ndMeasured IActivities,
      .The "calculated a~i~iivtie~s for cacli d-simeter- type '""v 'or'each irr~di ati6n period %Nci'e d~termiilned using the Collow-ing cquation:
                                                     "R,'x       x     S
                    'Cd                 .. calculated sp~ccitk activity for dostiriii-ter- "d"'inptiof'
                                              'product isdt'ope per uram ottartget .Igotopc three dinkiesi6fial flux&#xfd; fd+ dos tr~&"d" it piositon Yd, tor
                   'RF                       'dosi Meter responseh   'fution   tor dosi'meter "d"'and energy b1as correction factors for dosirheter 'V'"
N1,SF             .        non-saturnelon correction factor,(NSF).
'For ih~~two             separate sets ofact'ivitics.-%ill be calculated,"one-for th& dosinictry of cycle
,&#xfd;D, and one for the dosimqery ofCydIe 10.
'he bias correction factors (Be,) in tbe specific activity &#xfd;alqUlafion fibove are listed in Table A-I.
TAble A-0-1. Bias Correction F~actors DosimeterTypc,                       I                              ias
                     'Activation                       IShort                     h~alfLire Fissionisio Framatorne ANT                                                                                 lon-Pr-Oprictaz-y Framaome NP

CR-3 PT Fluence Analysis Report, Cycles 7-10                                    CaIc. #: 86-5022636-00 page 19 of23
      -A photofissionfactor-was applied-o correct for the fa& that sonie of the " Cs atomspresent in the dosime~tr were pr6dti6ed by (yi)ieacti6ng and 'were not nccounteId for in DORT mialysis.
 ,The short half life and impuiity factors were inignificaiht and theiefore iviie fr6i app&#xfd;lid.,
CJ, P  Ratios.
The folloNing explanations will de*fne the meanings of the terms "mesurcenrnts" (MI) and "calculations" (C) as-used in this analsis:1 Measurements:'- The .ir.mciits-meaning' o the'tem "mc....                as used by FANP:is the medsurement &f the Mhysicial 1quantity of the dosimeter (specific :4ctivity) that responded to the neutron fluence, not to the`"measired fluence.- For the`example of an iron dosimeter, a- refcrefice 4to thd meedsurements means the specific activity or 54Mn in         which Ai/g, is the prodctic isotope of the dlosimeter re*eti6oi:
U~+ 'n . 5 4+
np
              ,, *Calculations: The calculationalethodology produces two primary results- ihe calctiulated dosimieter aciivities anl thie neutron flux at all points of interest. -The' meaning of the tern "calculations" asused by FANP is the calculated dosimeter.
activity. The cidaulatcd .adtivities ate determined'in such a wy that they are directly comparable to -ihe measurement values, but without recourse to the measurements. 'That is the calculated values 'are deternified by the DORT
                 'calculafi6riiund n-.directly ornpra ble io the measurement values. ENDF/B-VI
                 ,based dosimeter reaction cross sections? and 'response functions w-ere 'used in Framatome ANP                                                                             Non-Proprictary

CR-3 ITnuence Analysis Report, Cycles 7-1-0                                               # 8ac 6-5022636-,00 Page 20 of 23 determnining the calculated values for each individual dosimcter: In&#xfd; siirnrrdy,-it
                      'should be -stressed', ftht ',jh6 Uaculition i~ahcs in the :FANP ,approach2 are independent of the'measurejnien't values.
Uncertaifity,
     'TheCR Cycles 7-10 fluence id6 ios                   _,re bsed on the methodology described in the TANP "'Fiueric&,'an~d Uncertainty MethodolIo~ilj' .!opical-report, B3AW-22_41P.-A2'                Thc iirne
,avcragcd fu'xes,, and thereby the fluerid~throug~hout theicact&r .nd w~ss~~l, rc ccufaied with the DORT.,discrete ordinateSI ciinpci.&#xfd;cia&. using, three-dimensional synthesis methods.Th liasic thoyfor, 'syihesis is descjibedin' "Section 3.0 of 'the topfiyal ifnd tli5 _ORT 'fhree dimrensibnal ~sytthcsi&sect;, results are the basd'r6rthe    t    flu~nkc predictions -using the FANP&#xfd;_ ,'1Smi Thec- unceitainties-.in -the Clft-3 flhuencc Values bavc'be~n evaluated to          ti&that
                                                                                             -- the~greater than 1.0 MeV calculated iftienc6valdiis,-i& 6-              te (viih -nodliscernlible bias) and have a mecan standard deviatiion that is consistent ,witii fbheANP --benchmark- database, of tincertaintics.
Conisenc 'etwenthe fluence uncertainties- in theu~dat~d 'cilculati-n-s for CR-3 cycles 10
;ind th~ose- ffi -the FANM bcnchrrnrk '.databa~sce'~nsure's -that -the -vessel fluence .predictions are c6risistciit -,Mfiih the 10 &,R 50.61, Pressurized Thermali Shock (PTS) screening criteria -anat the Regulatory Guide 1.99' ermbrittlemebnt evyaluations, The verificziti6h'fih  6fth  luence un-certainty 'frr the dR-3 reactor j~ncludcs:
Vestim~ating thune rictairities in th'eecycles9 and tdosimetrymrncaurernents,-
Framatorne kNP                                                                              FraNI tomAon--Pr 6P'rie i-ary

I CR-3 Yr Fluence Analysis Report Cycles 7-10                                         -Calc. #. 86-.5022636-00 Paige21 o ,f23 "eLstfmating   the uncertainties in. 1116 'cycl        9, and- 1W)benchmark, comparison 'of calculuti~ouisto rnensuremnents,
              "* _stimat'ingZthie uncertainties in the eckks 7jihiotIi 10~l       pressure vessel Iluence,'an'd
              "* -determining if the sp6ifie measurement and benchmark uncertainties for cycks-7-fO
                  'are consistent with the , FANP&#xfd; 61tabase cif jeneric iincert~inties_ in the measurements&#xfd;
                   =md calcuilations.
The ernbrittle-ment evaluations in Rcgulatbuy Guide 21.99,"aind those -in 10 CFR.50.61 for the, PSscreening criteria fiapoly a iia'rgin 16rm    M-to' tte re-ference -temperatures. The -margin*terhi
   'includes tie lirodrkf 6f a'corifidence factor of 2.0 and the nieafi *hibrittleni-ent s~aindard dea'iaion.
  'he~factor of 2.0 implies a vet- ihl'e               fcoriejci h               'lcne- uncertainty as Nvell as the
   ,uncertainty in the othci- Varii~bks 66nit~ijb'ut~iig t6 the erhibrittilement. The dosimeter, mensuiernents
  -from the 'CR-3 cycl es'9 and A0 analyses would not dire&&#xfd;Iy suqp~ot this 1-gh level of confidence.
   -However, the dosimeter 'tn~a~ureffcnt iin6&dai~ties 6c~ ,onsitsteit              wvith' the FANP 'dtlahibdse.
Therefore, th6 6lc1616i&#xfd;aI ' nrc~rtaminties An the. updated fluence pred!ictioins for- CR-3 6f6~
  .supported by 72J8 additional dosimeter m'easuremnents and thioy'-iinc_ enchn'urk- comparisons of, calculations td xneibremenitg 4s ~shown "in App'eiidix A ofl'te "topical.'                  the taliculationaI uncertiahujc~s aji-calso suipportea by "the -fuence'sensiftivity 'valuation-6ofthe uincertiiiti~s in the physical and operat -ional paramieters, wvhi~h are included in the ,'eSl6          fluence uncertainty.' -The dosimctr)u iieaiuremcenti a'id ben'chmairks, as well as'thefluence 'sensitivity analyses in the topjical are suficient to support a 95-percent confidence level, with -4 &#xfd;onfidence factor of +/-2.0, i-n fhe fluen~e ies'LtWq from the'Seziii -Analytical" mnethodology.
The FANP Zgcneric -uncertainty in the dosirnetuy measuremenits hais' been de't~rmncnd to 'be unbiased, and 'hais -an estin-ated &#xfd;tsfindard deviation of 7.0 pci~cen't for the. qualified set, of dosim~eiers. The CRI-3 cycles 9 and 10 dosimetry measurement uncertainties were evaluated to Framatom~e A1NP                                                                              TWon-Proprietary

                                                                       . rl&#xfd;t_-&#xfd;I&#xfd;                     .  - - -- .- 17 7__
MR-3 PTFluence Analysis Report, Cycles 7-1,0                                       talc: #: 86-502#636-00 Page 22 of 23 deteiiiiine'if any -biasesi*erc elAdidnt, airi   to cstilmntc, -the standard -deviatioin'. -TIe dosimftry nieasurements were found to he a .ropfiateilychlii-iiitcd          to standards iraceablc "to the iNational Intf~itute -fl Standards'',and 'Technology mnd arc thereby tIunbiased by 4definitidn.             Th& mii~n measurement uncertainties associated with gcycls9 'abdc .10 'nc hs follovsi 6,24%
                                                      =91%.
5.,,O These:~i~&#xfd;sIeirc, determined from Equation 1!.6 in tetopical' and indicate that th~r6 is "consi'stency wvith the rANl database; Consequently, -)xhcn 1he'FAiP '666nagc is updaied, the tR-3 jaYc0qs    9 ;7nd 10 do~imetry iiieatiuem~di 'unMcertainties may be combined -withthe other, 728 dosimtcrs'7,. 'S'nc'e the cycles 9 and'10 measurcmenits are consistent with the FAN~P database, it is estimiated that the -CR-5 dosimeter ineasui~emcnit iinic~rtainty mnay b e rcpresent~d by the FANP AdatAbasdisthinhdrd c'%eiatk6rif'7.0   percent. -Based'on the FANTP database, there appears to bc a95 pecnt -lvlfcnfidence that 95 percent -cdf the CR-3 dosimetry measureins                me     f.~     ic reactilons -bobd~ 1.0 MeY-arc&#xfd;-&  with~hiii4.2 P'nerc'enit'nfihe true vaiues.,
      .The FANI generic uncertainty for benchmark-comparis6nis ofldosimetry, calculationis ielativc to the measurements indicates that aujiy_    benichimrk biis ini the greater than- 10 MeV results 'IS1too sijinItto 6e, uniqti'nly'identified. The esitimated' standard'-dcviat~ion betwcen -the cifculatio&i and measurements ~s'.9 percen-t. This implies that thei700ot m-eannquarec            deiation betwedn teVAI4P calculation~ of the CR-3,dosinietry an h iiuireriicns sol eapoiaey99pret general rand bounded by +/-20.04 pervent for a,95 percent confidence interval with thinyt-nine i~ndependefit b6ri~hii~irlcs.
Framatomec ANIP                                                                              NonTroprictary n-opity

CR-3 PTFIucnceAnalysis'&#xfd;kepor4 &#xfd;Y&#xfd;1&#xfd;0-10                                        Uc. #: 86-50776-6-00 Page 23 of 23 11c. wCighted n1ea' vOuds,.o-f the Tati.o of calcuUted'd6sifficte'r Uctiviltics to rneasurcments
  '(CAM) for cycl6s 9 and I-O'harc be&#xfd;n ttatisticill 6v&#xfd;aluatcd using E'                                   a quation 7.15 from theqopic 12 the standard deviation in ibe tie&#xfd;6btfizjjkComparisons is as follows:
cr&
G6     -=10.05%.
This standard devijt16jjindi6&c-s thai-theb&nchmaikcomp            on5tfre consistdfit m6th the FATQ'databi&#xfd;&. Coh&#xfd;cqu&#xfd; n-tly,,%&#xfd;hcn tbe'-'           &#xfd;a base is upda-ted' the'2'cyc16s"9 and 16 b&n6mark uncertaintics rn&#xfd;y be indhided'-wifth-the oih&#xfd;f fliirty-'iIine ben&#xfd;bmark"uncertaintics in tketopic                                     e cyclcs9 and'I 0 benchmark, uncertainti6s'and tho'se jh6 FANP d3tdbas-C indicaies.tiiat                                           -cles7-4 Ohave no the CR 3,fluence calculations fbi 69, discernNe bias in thegreqtF1rffIafi"S1,OMcV flu&#xfd;n&#xfd;c v'alues. Ina'dditi'on.,ifieconsistencyindicates that the fluen6c.-A&#xfd;-ilues cifi be repicknic&#xfd;d bj the FMO rcierence'setwhich inclu&s d
,c&#xfd;iculaiional standard deviation of 7.       &#xfd;c6ntafdosimctry locMions'. MGt is:
T&#xfd;bl&A-2.. Calculational Fluen&#xfd;e Unc&tAnfies Uncert *ntv(0/0)
Stan'dard Deviation          95%1,951/1o C6tirjd6nc6
          '12b of Oaculation                      (CF)
                 'Capsule                         7.0                              14.2 Prc.&#xfd;Sure'vtskl                     '10.0                            20:0
        -Naximum location)
Pressure Vc&#xfd;ssel                    -11.4                            22.8 Framatome I,        ANP                                                                        1\'6n'-Propricta*,}}