ML20133M045

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Proposed Tech Specs 3.4.11 Re RCS Pressure & Temp Limits
ML20133M045
Person / Time
Site: River Bend Entergy icon.png
Issue date: 01/10/1997
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20133M037 List:
References
NUDOCS 9701220235
Download: ML20133M045 (19)
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Text

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I ATTACHMENT 3

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TECHNICAL SPECIFICATION MARK UP .

Revised Figure 3.4.11 1 i

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RIVER BEND 3.4-32 Amendment No. 81

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ENCLOSURE 1 i Structural Integrity Associates, Inc. Letter Report Revised (12 EFPY) P-T Curves for River Bond Station

Letter #GLS-96-059; SIR 96-096, Rev. 0 l
October 22,1996 .

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StructuralIntegrity Associates, Inc.

3315 Amoen Egresmy j suite 24 i October 22,1996 san .;ose. CA 95118-1557  !

GLS-96-059 pnons .os.ps.s2co SIR-96-0%, Rev. O k 806-p8-8964 sstevens@structint com Mr. Erwin J. Zoch, P.E.

River Bend Station Entergy Operations, Inc. -

l P. O. Box 220 St. Francisville, LA 70775

Subject:

Revised (12 EFPY) P-T Curves for River Bend Station

Dear Erwin:

In accordance with the Reference I contract, this letter repon documents the results of the  ;

i pressure temperature (P-T) curve calculations performed by Structural Integrity Associates (SI)' l for 12 effective full power years (EFPY) for River Bend Station (RBS). The input, methodology, j

analysis, and results are described below. In addition, attached please find a copy of SI Calculation No. RBS-03Q-301, Revision 0, " Pressure-Temperature Curve Calculation for 12 EFPY," 10/16/96, and a floppy disk containing the RTeT and P-T curve EXCEL spreadsheets developed as a part of this work. The attached items, together with this letter report, constitute the complete set of deliverables for this project in accordance with Reference 1.

INTRODUCTION I

This report documents the development of revised P-T curves for RBS valid for up to 12 EFPY of operation. The P-T curves documented herein are intended to replace the currently existing l P-T curves [2] which are valid for up to 8 EFPY of operation. The developraent of the 8 EFPY

, P-T curves, in accordance with Regulatory Guide 1.99, Revision 2 (RG 1.99) (3), is documented in Reference 4. The Reference 4 report includes the effects of the beltline, bottom head (CRD penetrations), and feedwater nozzle locations. The detailed specifics of precisely how the P-T curves were calculated are not included; however, all of the necessary inputs are included.

Tabulated values for the current P-T curves are provided in Reference 5.

There were three objectives to this current work, as identified in Reference 1:

l. RTmy. Determination: The Reference 4 report provides RTer estimates for cil of the

, various RBS beltline materials. Since RTmi si an important and significant input prrameter to the development of P-T curves, an EXCEL spreadsheet specific to RBS was

, generated to validate the RTm7 estimates contained in Reference 4. The spreadsheet can be used in the future to provide RTm7 estimates for any EFPY.

Asses. SM $#ser Bestas. IN PL Lamasseste. M Inesst.1 meson assesmetries. lat.

Miene 216-464-ages P%ns 301-5862323 Phons 964-444-1882 Phone 02 306-550s $dver Sonne MD Phone 301589-2500

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! Page 2 October 22,1996 Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. O i

a e 2. j Modr/Dewlqpment: A valid calculational tool (EXCEL spreadsheet) was developed for l computing P-T curves for RBS. The spreadsheet tool is convenient in that it possesses l~

both computational and plotting capabilities, both of which are necessary for generating P- l T curves This tool provides fbrther convenience in that it can be used by Entergy for i i future use in developing their own P-T curves, as well as to fulfill their requirement of j

providing the tabulated P T points for the developed P-T curves. The tool was  !

" benchmarked" by first matching it to the current 8 EFPY curves. This step ensured  ;

j consistency with past work done for RBS in the Reference 4 repon. Of particulir interest I

! were the thermal stress intensity factors previously used in the Reference 4 analysis. Since there can be signi6 cant variation in these factors depending upon the method of

calculation used, benchmarking the model eliminated any "mconsistencies. Benchmarking

! against Reference 4 is considered reasonable, since it is apparent that significant effon has

! been expended in developing the RBS P-T curves in the past. The past work was initiated l to address Generic Letter 88 11 requirements and implement Technical Specification 1 l changes.

3. P-TCurw Dewtopment
Once the spreadsheet model was developed and benchmarked,

! P-T curves were developed for 12 EFPY using the RTm7 estimates established for RBS.

, The curves were generated in the format shown in Reference 2 so that they are suitable for j placement into the RBS Technical Specifications.

i j The results of each of the objectives identified above are presented in the sections which follow.

l RTwor DETERMINATION i

i Appendix A of Reference 4 provides RTer estimates for the RBS beltline materials in i accordance with RG 1.99 for various EFPY levels. An EXCEL spreadsheet was set up to j perform the RTer calculations, and is shown in Table 1. The inputs used for the calculations in

! Table I were obtained from Appendix A of Reference 4 unless otherwise noted. All details of the calculations are identified in the notes to the table. The results in Table 1 are seen to be identical to those of Appendix A of Reference 4 for 12 EFPY, thus validating the previous RTer i estimates and those used in the current evaluation.

MODEL DEVELOPMENT f

f In this section, the methodology used for calculating the P-T curves is detailed. This i methodology documents the equations used in the P-T curve EXCEL spreadsheet developed for i this work. The methodology is based on the requirements of References.6 and 7. The 1992 4

edition of Section XI, Appendix G of the ASME Code was compared to the 1989 edition, which j is the latest NRC-accepted version of the ASME Code. Side-by-side comparison of these two j editions of Appendix G reveals that the they are identical from a methodology point of view.

Therefore, this analysis fulfills the requirements of both versions of Appendix G.

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( Structurallatogrity Associates, Inc.

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Page 3 October 22,1996  !

Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. 0 i The approach used for calculating the P-T curves is summarized below. Note that the following

! is based on developing a model that calculates P-T curves which match those previously l developed in Reference 4:

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a. Assume a coolant temperature, Tw A range of temperatures are assumed that resuk in P-T points appropriate for the boiling water reactor (BWR) operating l regime.

, b. For the T%, assumed in step (a), compute the temperature at the assumed flaw

! tip, Tp4,(i.e.,1/4t into the vessel wall). This is accomplished by adding a through-wall temperature drop term, ATw, to Tm to account for the temperature drop due to heat transfer between the inside surface and the 1/4t l location. The value of ATw was varied such that the resulting P-T Cuive A l matched that previously determined in Reference 4. This eliminated any l inconsistencies that might have arisen if ATw were determined by independent heat transfer analysis.

l l c. Calculate the allowable stress intensity factor, Km, based on Tp4, using the relationship from Reference 6:

l Km = 1.223 elm 44T ARM @) + 26.78  ;

l where: T = Tp4, ('F) l ART = adjusted reference temperature for limiting beltline material ('F) l Km = allowable stress intensity factor (ksi/ inch) l Note that a maximum value of 200 ksi/ inch is allowed.

d. Calculate the allowable pressure stress intensity factor, Ky, using the appropriate i relationship for the P-T curve under consideration:

( Ky = Km/I.5 for Curve A (i.e., pressure test curve)

K, = (Km-Kg)/2.0 for Curves B and C (i.e., core not critical l and core critical curves) where
Kg = thermal stress intensity factor (ksi/ inch)

The value of Kg was varied such that the resulting P-T Curve B matched that previously determined in Reference 4. This  !

eliminated any inconsistencies that might have arisen if Krr were determined by independent thermal stress analysis.

l Ky = allowable pressure stress intensity factor (ksi/ inch)

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-c. Compute the pressure, P. The relationship for the pressure, P, to the allowable pressure stress intensity factor, K,, is as follows:

Ky = M, o, + Mg g ,

I where: M, = membrane stress correction factor from Figure G-2214-1 of Reference 6. The bounding upper line for M. (corresponding to e/o p= 1.0)in Figure G-2214-1 was used. Note, however, that any differences introduced by this assumption were i effectively removed by adjusting ATw and Krr such that the

resulting P-T limits matched the previous RBS P-T curves, as 4' mentioned above.

i e, = membrans stress due to pressure (ksi)

! = PR/t for a thin-walled vessel P = pressure (ksi) l

R =

vesselinside radius (inches) .

i t =

vessel minimum wall thickness (inches)

! Mb " bending stress correction factor = (2/3)M. l

! o, = bending stress due to pressure (ksi)

! = 0 for a thin-walled vessel ,

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l Thus, P = Kyt/(RM.)

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1 f. Repeat steps (s) through (e) for other temperatures to generate a series of P-T l i points. ,

4 g. Subtract any applicable instrument errors for temperature and pressure from

! T and P, respectively. The resulting pressure and temperature series constitutes the P-T curve Instrument errors were assumed to be zero for RBS, as j they were not used in the prior P-T curve work. The P-T curve relates the i .n T . required reactor fluid temperature in the beltline region to the reactor

! pressure in the beltline region. For the purposes of this evaluation, it was assumed

< that the minimum reactor metal temperature and the minimum reactor fluid i temperature were equal. This assumption is consistent with prior P-T curves

developed for RBS.

1 The following additional requirements were used in the Reference 4 report to define the lower i' portion of the P-T curves. These limits are established by the discontinuity regions of the vessel (i.e., flanges, nozzles, etc.), and were retained throughout the current analysis (i.e., they were j assumed correct and do not change since the discontinuity regions are not affected significantly by fluence):

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Fw Cum A:

  • Thermal stresses were assumed to be negligible during the pressure test condition and were therefore not considered.
  • If P is greater than 20% of the pre-service hydro test pressure, the temperature  ;

must be greater than RTmy of the limiting flange material plus 90'F [7). The pre-service hydro test pressure was assumed to be 1562.5 psig (=312.5/0.20),

based on the fact that the current 8 EFPY P-T curves establish this limit at* 312.5  :

psig [5).  !

  • If P is less than 20% of the pre-service hydro test pressure, the temperature must be greater than RTer of the limiting flange material plus 60'F. This has been a standard recommendation by GE for the BWR industry [4). For the RBS flange <

material, this minimum temperature is 70*F [5). j Fw Cum B:

  • If P is greater than 20% of the pre-service hydro test pressure, the temperature must be greater than RTer of the limiting flange material plus 120'F [7).
  • If P is less than 20% of the pre-service hydro test pressure, the temperature must be greater than RTer f othe limiting flange material plus 60*F. This has been a standard recommendation by GE for the BWR industry (4). For the RBS flange material, this minimum temperature is 70*F [5).

Fw Cum C: }

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  • Per the requirements of Paragraph IV.A.2 of Reference 7, the core critical (Curve C) P-T limits must be 40*F above any Curve A or B limits. Curve B is more limiting than Curve A, so Curve C is Curve B plus 40'F.
  • Another requirement of Paragraph IV.A.2 of Reference 7 (or actually an allowance  :

for the BWR), concerns minimum temperature for initial criticality in a startup.

Given that water level is normal, BWRs are allowed initial criticality at the closure j flange region temperature (RTer + 60*F) if the pressure is below 20% of the t pre service hydro test pressure. This corresponds to 70*F for RBS.  :

  • Also per Paragraph IV.A.2 of Reference 7, at pressure above 20% of the pre service hydro test pressure, the Curve C temperature must be at least that ,

required for the pressure test (Curve A at 1,100 psig). As a result of this  ;

requirement, Curve C must have a step at a pressure equal to 20% of the i pre-service hydro pressure to the temperature required by Curve A at 1,100 psig, ,

or 40*F, whichever is greater. (For the curves covered in this analysis through 12  !

EFPY, the 40'F step is limiting.) l i

An EXCEL spreadsheet was developed to perform the necessary calculations described abovc .:.d generate the P-T curves. A " benchmark" case was run in the spreadsheet for 8 EFPY. The limiting ART value of 60.5'F for 8 EFPY, and the vessel dimensions for the RBS plate matenal ,

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i Page 6 October 22,1996 l Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. 0 documented in Reference 4 were used as input to the spreadsheet for this case. The results i generated by the spreadsheet were identical to those contained in the Reference 4 report after appropriate" adjustment" of the ATw and Krr values. This comparison of the two sets of curves  :

demonstrated that the spreadsheet results are consistent and accurate.

! P-T CURVES FOR 12 EFPY The P-T curve EXCEL spreadsheet was next used to generate the 12 EFPY P-T cunes. 'The  !

l . limiting ART value used comes from Table 1 for 12 EFPY, and is 72.3*F. This value was entered

into the spreadsheet to generate the 12 EFPY P-T cunes. The results are shown in Table 2 and Figure 1. Also contained within this table and figure are the current 8 EFPY Tech. Spec. curves

[2,5] for comparative purposes.

SUMMARY

AND CONCLUSIONS l The analysis documented in this report develops RTm7 estimates and P-T curves for the RBS reactor pressure vessel. EXCEL spreadsheets were developed for each of these items.

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l Table i provides the results of the RTmT estimations. Those results are identical to estimates previously developed in the Reference 4 report, thus confirming the past results and the spreadsheet used for the current analysis.

The P-T cune spreadsheet developed for RBS was benchmarked against the results previously developed in Reference 4. Comparison of the calculated results for 8 EFPY to those contained in the current Tech. Spec. P-T curves for 8 EFPY [2,5] demonstrate the validity of the spreadsheet, as the two sets of results were identical. -

l Finally, Table 2 and Figure 1 provide the results of the P-T curve spreadsheet for 12 EFPY. The results are seen to be reasonable based on the " shift" in results from those at 8 EFPY. This, coupled with the results of the " benchmark" test case, conclude the Figure 1 P-T limits to be appropriate for RBS for 12 EFPY of operation.

i It should be noted that the 12 EFPY P-T cune is also applicable for power uprate conditions.  !

Actually, the implementation of power uprate has no effect on the development of the P-T curves, other than in determining the length of time the curves are applicable for (i.e., implementation of l power uprate may cause 12 EFPY to be achieved sooner than if power uprate were not I

implemented). In calculating the full power operating time after power uprate implementation, it ,

is important that the EFPY value be determined using methodology which is consistent with that l f

used to estimate fluence. Otherwise, developed P-T limits will not be reflective of the assumed Suence level. Based on this, both the fluence estimate and the EFPY value should be based on the ,

100% core thermal power value of 2894 MWt.

Structural Integrity Associates, Inc.

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[ SPREADSHEET LIMITATIONS J

It should be noted that although the spreadsheet tool for generating P-T curves has been j validated, each future use of this spreadsheet should be validated on a case-by-case basis. All
possible temperature limitation requirements were not placed into the spreadsheet for " automatic" j imphmentation. For example, the minimum temperature described above for Curve C that

] requires the minimum Curve C temperature to be equal to the temperature of Curve A at 1,100 i psig was not necessary for this analysis (i.e., Curve A @ 1,100 psig = 168'F whereas C'urve A

{ plus 40*F at pressuresjust above 312.5 psig = 170*F which is more limiting). At some point in the near future (i.e., beyond 12 EFPY), this requirement will be necessary (it was implemented in

, the 32 EFPY curves in Reference 4). Therefore, modifications of the spreadsheet to account for j this and other requirements may have to be made as a part of future use of the spreadsheet.  ;

i OTHER OBSERVATIONS A few observations were made during the course of performing this work that may be worthy of.

{. consideration by Entergy in future P-T curve work. These items are as follows:

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  • Se Kg and AT,,a values usedare slightly conservative. Based on observations I made during this effort for RBS, as well as other evaluations done for other BWRs I

by SI, the values for Kg and ATw that had to be used to match the previously developed P-T curves for 8 EFPY are slightly conservative. Less conservative i values could be technicallyjustified, thereby improving P-T limits. Although the

{ magnitude of this improvement is not precisely known, it is estimated to be on the

orde of a few degrees in temperature. This may be of benefit for RBS operation 4

in the future when shifts in material properties become more significant and the P-l T operating window shrinks.

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  • De vessel dscontinuity limitsportion of the P-Tcurves may be conservative.

l Typically, GE uses stresses available from Design Stress Reports or computes stresses using conservative stress concentration factors for geometric i l discontinuities for application to vessel discontinuity regions (i.e., nozzles, I i penetrations, flanges, etc.). Based on analysis SI has performed for other BWRs l using more re6ned plant-specific stress analysis, these assumptions can lead to

! overly conservative P-T limits. This would only be applicable for the lower curved i portions of Curves B and C (i.e., between 70'F and 100*F for Curve B, and

between 70*F and 140*F for Curve C) since the other discontinuity limit portions j of these curves are set by the requirements of Reference 7. If these limits are too l restrictive for RBS operation, further evaluation may provide relief. This issue

] affects regions of the P-T curve that are not typically a problem for BWR

operation; thus, it is mentioned for future reference purposes only.

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Page 8 October 22,1996 Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. O We would like to thank you for the opportunity to complete this work for Entergy, and hope you find it to your satisfaction. Ifyou have questions, please contact me.

Prepared by: b I- L MN% Verified by: _

Gary f. Stevens, P. E. H. L. Gusti(P. E. -

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REFERENCES

1. Entergy Contract No. NRSM1469 dated 9/26/96.
2. RBS Technical Speci6 cations, Amendment No. 81, Figure 3.4.11-1," Minimum l Temperature Required vs. RCS Pressure," SI File No. RBS-03Q-202.
3. USNRC Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactot Vessel Materials," U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, (Task ME 305-4), May 1988.
4. GE Report No. SASR 89-20, Revision 1, " Implementation of Regulatory Guide 1.99 -

Revision 2 for River Bend Station Unit 1," March 1990, (LAR90-02, SCRB-14842 dated l 3/20/90), SI File No. RBS-03Q-203.

! '5.

' Letter No. G-LD-2-085 from W. D. Arndt (GE) to Mr. J. C. Deddens (GSU), " Tabulated Values from 8 EFPY Curves River Bend Station," May 26,1992, (EOI File

  1. 3221.110-000-004A), SI File No. RBS-03Q-201.
6. ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Nonmandatory Appendix G, " Fracture Toughness Criteria for Protection Against Failure," 1992 Edition.

l 7. U. S. Code of Federal Regulations, Chapter 10, Part 50, Appendix G, " Fracture Toughness Requirements," l-1-% Edition.

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Table 1 ,

RTNDT Estimates for RBS for 12 EFPY h

(Data Source Appen&r A of SASR 89-20. Rev.1. ~8mplemenlahon of Regulatory Guide 1.99 Rewsion 2 Sar Rwer Berni Stahon thut 1.~ hearch 1990p g RPV thickness = 5 41 enches

% Reference Fluence = 6 600E+18 necm' at 32 Reference EFPY (nonunal peak value at RPV ID)

Deswed EFPY lor RTi er Pressw*nn = 12.0 EFPY Estimated Fluence * = 2.475E+18 n/cm'(nonunal peak value at RPVID)

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Attenuated Fluence at 1MT * = 1.789E+18 nicm' i Fluence Factor * = 0.5431 o .. ,, f . ,

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._ For1M T Port flame & j. Nest.., .Lat InIgelRTuer " ^^

-, FacterM ARTeer m IAerg in ARTm i esenereas so pse.' '

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" see.' - "m cu(es%) en(at %) m m m e, m m <

Vessel Place 22-1-3 C3138-2 - 9 0.08 _ 0 63_ 51 27.7 13.8 0.0 64.4 Vessel Piste 22-1-1 C3054-1 -

-20 0 09 0 70 58 31.5 15.7 0.0_ _ 43 0 VesselPloes 22-1-2 C3054-2 - 2 0.00 0.70 58 31.5 15.7 00 65 0 '

, VesselWald BE1 BF. BG 492L4871 A421827AE -60 0.04 0.95 54 29.3 14.7 0.0_ -1.3 O Vessel Wold _BE, BF, BG 492L4871 A421827AF -50 0.03 41 22.3 00 -5.5 0.98 _ ___11.1 VeseelWold BE, BF. BG EP6756 0342 (Tandem [ -50 0.00 0.92 122 68.3 28.0 0.0 72.3 _

t VesselWold BE, BF, BG 5P6756 0342 (Smgle) -60 0.00 0.93 122 66.3 28 0 00 62.3 Limleing geIINne ART = 72.3 Notes: 1. Esemated Fluence = (Reference Fluence) * (Desired EFPY)f(Reference EFPY).

2. Altonusted Fluence = (Estunated Fluence) e * ** where x = IMT distanca per Secton 1.1 of RG 1.99.
3. Fluence fedor = f "'"*
  • where f = (Allenueled Fluence at 1MT)A(1x10") per Secton 1.1 of RG 1.99.
4. Obteened from RG 1.99, Table 1 (Welds) and Table 2 (Base Metal)
5. ART, , = (Chemestry Factor)*(Fluence Factor)' per Sechon 1.1 of RG 1.99.
6. o = 17*F for base metal and 28*F for welds, except that a. need not exceed 0.50* ART,.y per Sechon 1.1 of RG 1.99.  !
7. Adjusted Reference Temperature (ART) = Initial RTwo, + ART,e1 + 2*(o g' + s,#)"' per Sechon 1.1 of RG 1.99. ,

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Table 2 (continued) '

P-T Calculation Results for 12 EFPY O ess I tename esameCampenseea vasessemuseorgFeegetspee,Tenemme Y EFPv =

- veneewes innanees =

Sao o.45 .eumes ase.n=enweeeds aws nee e. tto.3 eumee nr . yts v Ut lengper hne enstwsupe Enar e og y

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1 SOO A A'S -

C 1.400 ,' .,'

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,',,a SHIFT FROM AN INITIAL

, ,e WELD RTc OF .50*F.

.o .

ta 600 ,, ,. A= SYSTEM HYDROTEST LIMIT WITH E

e 8/ '/ FUEL IN VESSEL

/ / 8= NON-NUCLEAR HEATING LIMIT.

C= NUCLEAR (CORE CRITICAL) LIMIT.

l 400 VESSEL DISCONTINUITY l LIMITS I 312.5 PSIG

***

CORE BELTLINE LIMITS A WITH 122.3*F SHIFT B

200 7 I

' CURVES A', B', AND C' ARE VALID FOR BOLTuP C 12 EFpy OF OPERATION.

70*F CURVES A. 8, AND C ARE VALIO FOR 8 EFPY OF OPERATION.

0 0 100 200 300 400 500 600 Minimum Reactor Vessel Metal Temperature (*F)

Figure 1. P-T Curves for 12 EFPY l GLS-96-059/ SIR-96-096, Rev. 0 15

.

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