PNP 2014-054, Response to NRC Request for Additional Information - 10 CFR 50 Appendix G Equivalent Margin Analysis - Mf 2962

Response to NRC Request for Additional Information - 10 CFR 50 Appendix G Equivalent Margin Analysis - Mf 2962

ML14163A662
Person / Time
Site:	Palisades
Issue date:	06/12/2014
From:	Vitale A Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PNP 2014-054
Download: ML14163A662 (14)

Text

.- J?.- #rijca

~Entergy 1_il 1Lt7

, Palisades Nuclear Operations, Entergy Nuclear Palisades Nuclear Operations, Inc.

Nuclear Plant Plant Inc.

27780 Blue Star Memorial Highway MI 49043*9530 Covert, MI 49043-9530 Tel 269 764 2000 Anthony J. Vitale President Site Vice President PNP 2014-054 12, 2014 June 12,2014 u.s.

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Response to NRC Request for Additional Information - Palisades Nuclear Plant 10 CFR 50 Appendix G Equivalent Margin Analysis -

ME 2962 MF Palisades Nuclear Plant Docket No. 50-255 License No. DPR-20

REFERENCES:

1. Palisades Nuclear Plant, Application for Renewed Operating License, dated March 22, 2005 (ADAMS Accession No. ML050940446).

2. Entergy Nuclear Operations, Inc. letter PNP 2013-028, Palisades Nuclear Plant 10 CFR 50 Appendix G Equivalent Margins Analysis, dated October 21, 2013 (ADAMS Accession No. ML ML113295A448).

3295A448).

3. NRC email to Entergy Nuclear Operations, Inc., Request for Additional Information - Palisades Nuclear Plant 10 CFR 50 Appendix G Equivalent Margin Analysis - MF2962,

- MF 2962, dated May 13, 13, 2014 (ADAMS Accession No. ML14133A684).

Dear Sir or Madam:

In the Palisades Nuclear Plant (PNP) license renewal application (Reference 1), 1),

Nuclear Management Company (N MC), the former license holder for PNP, committed (NMC),

to submit an equivalent margins analysis (EMA) for Nuclear Regulatory Commission (NRC) approval at least three years before any reactor vessel beltline material Charpy upper-shelf energy (USE) decreases to less than 50 ft-lb, ft-Ib, in accordance with 10 10 CFR 50 Appendix G,Section IV, Fracture "Fracture Toughness Requirements.

Requirements."

Entergy Nuclear Nuclear Operations, Inc. submitted the required EMA in Reference 2.

PLP 2014-054 Page 2 of 2 concerning the In Reference 3, ENO received a request for additional information (RAI) conceming EMA submittal.

The ENO response to RAI questions 1, 3, 4, 5, and 6 is provided in the attachment.

The response to RAI question 2 will be provided at a later date, as agreed upon during a RAI clarification phone call between ENO and the NRC on June 6, 2014.

This letter contains no new commitments and no revised commitments.

II declare under penalty of perjury that the foregoing is true and correct; executed on June 12, 2014.

Sincerely, ajv/jse

Attachment:

Response to NRC Request for Additional Information - Palisades Nuclear Plant 10 CFR 50 Appendix G G Equivalent Margin Analysis - MF

- ME 2962 cc: Administrator, Region III, Ill, USNRC USN RC Project Manager, Palisades, USNRC USN RC Resident Inspector, Palisades, USNRC

ATTACHMENT ATTACHMENT RESPONSE TO RESPONSE TO NRC NRC REQUEST REQUEST FOR FOR ADDITIONAL ADDITIONAL INFORMATION INFORMATION - -

PALISADES NUCLEAR PALISADES NUCLEAR PLANT PLANT 10 CFR 50 10 CFR APPENDIX G 50 APPENDIX G EQUIVALENT MARGIN EQUIVALENT MARGIN ANAL ANALYSIS VSIS - MF

- MF 2962 2962 request for additional A follow-up request additional information information (RAI)

(RAI) was received received from the Nuclear Nuclear Regulatory Regulatory Commission (NRC), by electronic (NRC), electronic mail on May 13, 13, 2014.

2014. The The RAI RAI requested requested that the response that response to the RAI be be docketed within 30 days of receipt of the request.

request.

The Entergy Nuclear Operations, Inc. (ENO) Palisades Nuclear Plant (PNP) response to the The RAI is provided below.

NRC Request (May 13, 2014)

1. The EMA is based on American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code)Section XI, Xl, Appendix KK as supplemented supplemented by Regulatory Guide (RG)

(AG) 1.1.161 Evaluation 161 "Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Ft-Lb ASME Code Section XI, Energy Less Than 50 Ft-Lb". Xl, Appendix K, Article K-4210 and RG 1.161 both include equations for calculating the stress intensity factor due to radial thermal gradients. In Section 5. 5.11 of the EMA submittal, the licensee discusses through-wall thermal stress and states that typical through-wall stress and stress distribution during a heatup transient are shown in Figures 5-1 and 5-2. But Figures 5-1 and 5-2 5..2 of the EMA submittal do not show these stresses as discussed. Provide figures showing typical through-wall stress and stress distributions during a heatup transient to support the discussion in paragraph 5.1 5. 1 of the EMA submittal.

ENO ENO Response Response to to RAI-1 Figures detailing detailing typical heatup thermal axial stress and typical through-wall axial stress stress for the PNP reactor vessel used used in the equivalent equivalent margins margins analysis analysis (EMA) submittal submittal are are provided provided below.

below.

11 of of 12 12

10 10 Heatup Ir~nJ~J~!'t

___~I_ H~aJ~p Thermal $t!_~SS Transient l11~r.!ltal Stress- S~

- Sxx ~~~

vs 11m~

Time

---ir

-ID

' 10 I I I

-Midwall

. Midwall

- j OD 55E o0 -

1 2 3 4 5 6 7 8 U,

U, I U,

-5 [-

1

-10

-10 -- - -

-15

-15 Time (hr)

Time (hr)

Figure 5-1 Figure 5-1(a)(a) - PNP PNP Typical Typical Thermal Thermal Transient Transient Axial Axial Stress Stress Profile Profile - Stress versus Time Stress versus Time 22 of 12 of 12

r -,

Heatup Transient Thermal Stress - Sxx vs. x/t 10 10 I

r

. ----r-l I

5

-~

U, o

0 0 0.1 0.2 0,3

---

----r ------ --- -

0!5 0.6 06

~

0.7 Or7 0.8 08 0.9 09 1 Ll

-5 I

---

,:-----+-

~-

---

H

-10

__________0-.1I Trarisient (sec)I Transient Time (sec)1

- - 6300

- - 12600

- 15700 I

, _ _ --1-__

-30300

- - 30300

-15 Distance Ratio x/t Figure 5-2(a) - PNP Typical Thermal Transient Axial Through-Wall Stress Distribution NRC Request (May 13, 2014)

2. Section 5.

5.11 states, "0nly Only circumferential base metal flaws are considered in this analysis, because only the "weak"weak orientation USE is projected to drop below 50 50 ft-lbs ft-Ibs below. Please demonstrate that assuming a circumferential flaw in the as described below."

base metal with the weak Charpy V-Notch (CVN) value in the EMA is more limiting than assuming an axial flaw in the base metal with the strong CVN value. Please note that the significantly greater applied J integral associated with the axial flaw may challenge the fundamental assumption in the EMA submittal.

ENO Response to RAI-2 Based on discussions between ENO and the NRC NRC during a June 6, 2014 RAI conference call, the response to this RAI question will be provided at a later date, as agreed upon during the call.

33 of 12 12

NRC Request NRC Request (May (May 13, 13, 2014) 2014) 3.

3. The applied The applied J-integral J-integral values values for for the circumferential flaws the circumferential flaws forfor all Level AA and all Level and BB service service level conditions level conditions are shown in are shown in Figure Figure 5-1, 5-1, and and the the applied applied J-integral J-integral values values forfor the the circumferential flaws circumferential flaws for for Level Level C and D C and D service service level level conditions conditions are are shown shown in in Figure Figure 5-2. Since Section 5-2. Since Section 5. provides very 5.11 provides very limited limited information information regarding regarding the the applied applied J-integral calculations, J-integral calculations, please please confirm confirm thatthat the the calculations calculations underlying Figures 5-1 underlying Figures 5-7 and and 5-2 are based 5-2 are based onon the the formulas formulas in in RG RG 1.161, 1.761, uEvaluation REvaluation of of Reactor Reactor Pressure Pressure Vessels Vessels with Charpy with Charpy Upper-Shelf Upper-Shelf Energy Less Than Than 50 FT-LB. If 50 FT-LB." If not, not, please please describe, describe, in addition to your response addition response to to RAI-1, RAt- 1, your plant-specific plant-specific calculations calculations to to support support their their acceptance in this application.

ENO Response to RAI-3 Yes, the applied J-integral calculations underlying Figures 5-1 and 5-2 are based on formulas in RG 1.161.1.161.

NRC Request (May 13, 2014)

4. Table 4-4 was presented but without being mentioned in Section 4 regarding how it was 4.

used in the EMA analysis. Therefore, please confirm that the calculated available margins presented in Table 5-3 for various time during coo/down cooldown are results, using the relevant J-R curves adjusted by the material margin factors of Table 4-4.

ENO Response to RAI-4 As discussed discussed in Section 2.2 of WCAP-1765WCAP-17651-NP, 1-NP, Palisades "Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis, Analysis," Revision 0, RG 1.161 1.161 material margin factors (ME)

(MF) in Table 4-4 4-4 were used for the J-R curves.

NRC Request (May 13, 13, 2014) 2014)

5. Section

5. Section 5.2 5.2 provides provides justification justification for using using thethe high-toughne ss/low-sulfur model high-toughness/low-sulfur model from RG RG 1.161 1.161 in the proposed proposed EMA EMA for the high-sulfur high-sulfur plates, plates, and and Section Section 5.3 5.3 provides the the correspondin corresponding g EMA EMA results.

results. WhenWhen the the high-sulfur high-sulfur model model (e.g.,

(e.g., for for the the 6T6Tspecimen) specimen) of of NUREG/CR NUREG/CR-5265, -5265, Size uSize Effects Effects on on J-R Curves for A A 302-B 302-8 Plate, Plate," is used, used, please please demonstrate demonstrate that that

• • The The updated updated safety safety factors factors (see (see Table 5-3), after Table 5-3), after adjusting adjusting for for temperature, temperature, will will still still be be greater greater than than 1.15.

1. 15.

• • The The updated updated applied applied J/J-R J/J-R curves curves (see (see figures 5-8, 5-9, figures 5-8, 5-9, and 5-12), after and 5-12), after adjusting adjusting for temperature, for temperature, will will still still show show thatthat dJappjjeci/da dJappliecida <dJmaterja/d

< dJmaterialda a atat Japplied Japplied == Jmateriai Jmaterial.

of 12 44 of 12

If the If the above above cannot cannot be demonstrated, perform be demonstrated, perform aa sensitivity sensitivity study, study, showing showing at what at what percentage of of the the proposed J-R cuive (e.g.,

J-R curve (e.g., 90%),

90%), your EMA EMA calculation calculation results results will will meet the criteria on both both crack crack extension extension and stability.

stability.

Section 6 presents conclusions

6. Section conclusions of this this submittal. For Service Service Level C condition condition with 400°F/hr 400°Flhr cooldown, it is concluded that, The "The equivalent margins analyses for for the plate materials are acceptable and bounded by by the conservative test data reported in NUREG/CR-5265 in all cases for the Level C transient."

NUREGICR-5265 transient. This This conclusion was was repeated later for Service Level D condition with with 600°Flhr 600°F/hr cooldown, with IIC" C in the quote replaced by liD."D. Plot the relevant NUREGICR NUREG/CR 5265 6T data in Figure 5-12 and provide sufficient justification to support your conclusions.

ENO Responses to RAI-5 and RAI-6 Updated Figures 5-9 and 5-12 with the V-50 plate data are provided below, along with added Tables 5-4 and 5-5 showing the Level C and D safety factors, respectively.

Table 5-6 was added, which demonstrates the available margins on pressure loading with the V-50 plate data, adjusted for temperature, with consideration of all service loadings, Level A, B, C and D. The minimum safety factor (SF) with consideration of V-SO plate data and the PNP-specific J-applied values is 1.5, which is above the the V-50 minimum required SF of 1.15 per RG 1.161.

Figure 5-8 from WCAP-1 7651-NP, Revision 0, along with the updated Figures 5-9 and WCAP-17651-NP, 5-1 2 below, all demonstrate that at Japplied 5-12 Japplied == Jmaterial, Jmaterial, dJapplieJd dJmateriai/da, is satisfied dJapplied/daa < dJmateria~da, for all three cases (i.e., the slope of the Japplied Japplied is smaller than the Jmaterial Jmaterial at the point of intersection).

intersection) .

Therefore, as demonstrated below and in WCAP-1 7651-NP, the equivalent margins of WCAP-17651-NP, safety per ASME Code Section Xl XI (References 4 and 5) are found to be acceptable for the PNP reactor vessel beltline and extended beltline regions with predicted Charpy upper-shelf energy levels falling below the 50 ft-lb ft-Ib 10 10 CFR 50, Appendix G G requirements at end-of-license-extension.

end-of-license-extension.

Westinghouse discovered during the development of this RAI response that the Level C and D D loading J-applied curves plotted in in WCAP-1 7651-NP, Figure 5-12, were not WCAP-17651-NP, not the most limiting case. This limiting case. This error also propagated onto Figures Figures 5-2 5-2 and 5-13 in in the WCAP.

This has been updated in the attached figures as part of of this RAI response. Note Note that the conclusions to the report, including including the safety factor determination, are unchanged; unchanged; only the figures were were in in error.

error. This This has has been documented documented in in the the Westinghouse corrective action action system, system, and and will be be corrected corrected whenwhen the WCAP is is revised revised to to incorporate incorporate these these RAIRAI changes.

Lastly, Lastly, note note that that the the Level Level C and D C and D margin margin tables tables (Tables (Tables 5-4 5-4 and 5-5 below) and 5-5 below) werewere originally originally omitted omitted from from WCAP-1 7651-NP because WCAP-17651-NP Service Level because Service Level A A and and B,B, as as discussed discussed in in Section 5.3 of Section 5.3 of WCAP-1 7651-NP, are WCAP-17651-NP, the governing are the governing transients.

transients.

55 of of 12 12

Table 5-4 Available Margins 5-4 Available Margins on on Pressure Pressure Load Load for for Level Level C, C, 400°F/hr 400°F/hr Cooldown Cooldown Base Material Base Material Material Weld Material Weld Circumferential Flaw Flaw Circumferential Flaw Circumferential Flaw JJo.

1O*1 JJo.

1 O*1 Time Time SF SF J-applied xx SF J-applied material material SF SF J-applied xx SF J-applied SF material material (sec)

(sec) )

2 (in-lb/in (in-lb/in2) )

2 (in-lb/in (in-lb/in2) )

2 (in-lb/in (in-lb/in2) (in-lb/in2)

)

2 (in-lb/in 0 5.8 682 682 5.2 511 510 1,197 8.6 885 839 7.1 613 613 4,122 8.9 1,535 1,535 1,534 7.1 1,050 1,050 Minimum SF 5.8 5.2 Table 5-5 Available Margins on Pressure Load for Level D, 600°F/hr Cooldown Base Material Weld Material Circumferential Flaw Circumferential Flaw JJo.

1O*1 JJo.

1 O*1 Time SF J-applied x SF material SF J-applied x SF material (sec) )

2 (in-lb/in (in-lb/in2) )

2 (in-lb/in (in-lb/in2) )

2 (in-lb/in (in-lb/in2) (in-lb/in2)

)

2 (in-lb/in 0 5.8 682 682 5.2 510 510 798 8.1 830 830 6.9 607 607 2,748 7.0 1,491 1,491 5.2 1,023 1,023 Minimum SF 5.8 5.2 66 of of 1212

Table 5-6: Available Margins Table Margins on Pressure Pressure Load Load for All Transients, Transients, Levels Levels A, B, B, C C andand 0, D, with Consideration Consideration of V-50 V-50 Plate Plate Data Data Plate V-50 Plate Plate V-50 Plate V-50 Plate Plate Level A Circumferential Level C LevelC Circumferential Level 0D Level Circumferential and B JJ 0O1*1 JJ 0O1.1 Flaw Flaw Flaw JO*1 material material J-applied J-applied J-applied material Time (in- Time (in- Time 2 SF SF xSF SF xSF SF xSF x SF (in-lblin

))

2 (in-lb/in (sec) 2 Iblin 2)

)

2 lb/in (sec) 2 Iblin

)}

2 lb/in 2

(sec) 2

)

2 (in-lb/in (in-lblin ) )

2 (in-lb/in (in-lblin ) (in-lblin

))

2 (in-lb/in 0 1.8 397 397 0 3.4 397 397 0 3.4 397 397 397 2800 1.6 441 441 1,197 4.7 488 488 798 4.7 483 483 483 3600 1.6 459 459 4,122 1.9 893 893 2,748 1.5 868 868 5400 1.7 503 503 7200 1.8 554 554 9000 1.9 611 611 10800 10800 18.0 675 675 I Minimum SF 1.6 1.6 [ Minimum SF 1.9 1.9 Minimum 1.5 SF SF 77 of 12 of 12

Applied J-Integral Applied J-lntegral Curve Curve - Circumferential

- Circumferential Flaw, Flaw, Level Level C D, aa =

C && D, lIlOt, SF=1

= 1/10t, SF=1 400 400 -

-Load LeveIC

- Load Level C

- - -Load LevelD Load level 0 -_ .. ----------

300 f::j C\4 c:

.Q

~

e Ie) 200 ,--~

~

J; 100 100 ~ ---------------------------------------------------------------

0o -

0.8 0.8 0.9 0.9 1 1.1 1.1 1.2 1.2 1.3 1.3 1.4 1.4 Flaw Flaw Depth Depth inin Base Base Metal Metal aa (in)

(in)

WCAP-1 7651-NP, Revision WCAP-17651-NP, Revision 0, 0, Updated Updated Figure Figure 5-2 5-2 with with Corrected, Corrected, Limiting, Limiting, LevelLevel C C and and 0D Transients Transients of 12 88 of 12

Circumferential Flaw Circumferential Stability -- Base Flaw Stability Base Metal, Metal, P=2.75ksi P2.T5ksi 100F/hr Cooldown, a/t=1/4t, IOOF/hr Cooldown, alt=114t, SF=1.25 SFI .25 1800 1800

- Japplied T=533F

- Japplied T=533F

- Japplied T=480F

- Japplied T=480F 1600 I- I __ Japplied T=460F 1600 Japplied T46OF Japplied T=313F Th31 3F r

- - Japplied 1400 1400 I JR.Base

<===

JR Base T:;S33F T=533F

- - JR JR Base Base T=480F T=480F

- JR JR Base Base T=460F T=460F 1200 ~

1200 I -=====- JR Base T=313F T=31 3F N I~ .= da =0.1" Line da=O.1 Line I

N

(

=

• 6T V-50 plate data at I SOF

.E 1000

a'"i I:1 A 6T V-50 plate data c::

C 800 800

~ 0)

C)

CD

• * +,

+

• tr*

• t C

'"i

-; 600 400 l AAA

!A 0

~

A

~ A A A

~ A 200 I

0o 2.1 2.1 2.2 2.2 2.3 2.3 2.4 2.4 2.5 2.6 2.7 2.7 Flaw Depth Flaw Depth aa (in)

(in)

WCAP-1765 WCAP-17651-NP, 1-NP, Revision Revision 0, 0, Updated Updated Figure Figure 5-9 5-9 with with V-50 V-50 Plate Plate Data Data Included Included 99 of 12 of 12

Circumferential Flaw Circumferential Flaw Stability Stability - Base

- Base Metal, Metal, Level Level C C && 0,D, aa == 1/10t, SFI lIlOt, SF=1 1800 1800

- - Level C

) Lom LOJ T = = 121F

- - -Leve{DLoadT=135F Level DLoooT= 135F 1600 ~ I 1600

~=JR Baset/1O4IDF JR Base tl10 400F

- JR Base JR Base t/10 tIlO 500F 5XF 1400 ~ I 1400 JR

==- BasetIlO6lOF JR Baset/10610F

<= =da=0.1

<= da= 0.1D 1200 ~ I 1200 N"

• • 6TV-50pIatec1ata 6T V-50 pille data Ii 180F 100F

,<c= ~ 6TV-50 pIe data 6TV-5O plme

.0 1000 1-1 adusted to rolF

~

E 1:7)

C)

~= 800

i;

~ *

• I

• 600 600 ~

o o

400 400

~ A_ ~ -A-J j - - - - - - - - i - - - - - - - - -~

- A - ~- - - - - - - -----------_.

A A A A A A 200 0o 0.8 0.8 0.9 0.9 1 1.1 1.1 1.2 1.2 1.3 1.3 1.4 1.4 Flaw Flaw Depth Depth inin Base Base Metal Metal aa (in)

(in)

WCAP-1 7651-NP, Revision WCAP-17651-NP, Revision 0, 0, Updated Updated Figure Figure 5-12 5-12 with with V-50V-50 Plate Plate DataData Included Included andand Corrected, Corrected, Limiting, Limiting, Level Level C C and and D 0 Transients Transients 10 of 10 of 12 12

Circumferential Flaw Circumferential Flaw Stability.

Stability Weld Weld Metal, Metal, Level Level C C& D, aa == 1/10t,

& 0, lIlOt, SF=1 SF=1 1800 1800 1600 1600 -LeveIC Load 121F

- Level C Load 121F Level D

- - - Level D Load Load 135F 135F 1400 1400 -===JRWeld

-JRWeld tl10t/10 400F 400F

-JRWeldfJ1 05O0F JR Weld tl10 500F 0 1200 ====JRWeldf J1O61OF JRWeldtl10610F 0 1200 c:::> =- da = O.1n da0.1 N'

C4 c

..:::: 1000 B 1000

~

1!

~ 800 s

oJ,

-,)

800 800 600 400 II

-- ------- ~ -------------------------------------- .

200 00 ~_ _ _ _ _ _ _ _~_ _ _L __ _ _ _ _ _ _ _ _ i 0.8 0.8 0.9 0.9 1 1.1 1.1 1.2 1.2 1.3 1.3 1.4 1.4 Flaw Depth in Base Metal a (in) _.

fl__

WCAP-1 7651-NP, Revision WCAP-17651-NP, Revision 0, 0, Updated Updated Figure Figure 5-13 5-13 with with Corrected, Corrected, Limiting, Limiting, LevelLevel C C and 0 Transients and D Transients 11 of 11 12 of 12

References References 1.

1. Regulatory Guide Regulatory Guide 1.161, 1.161, "Evaluation Evaluation of of Reactor Reactor Pressure Pressure Vessels Vessels with with Charpy Charpy Upper-Shelf Energy Upper-Shelf Energy Less Less than than 50 Ft-Lb, U.

50 Ft-Lb," U. S. Nuclear Regulatory S. Nuclear Regulatory Commission, Commission, June June 1995.

1995.

2.

2. Westinghouse Report Westinghouse Report WCAP-17651-NP, WCAP-1 7651-NP, Revision Revision 0, 0, "Palisades Palisades Nuclear Nuclear Power Power Plant Plant Reactor Vessel Reactor Vessel Equivalent Equivalent Margins Margins Analysis,"

Analysis, February February 2013 2013 (ADAMS (ADAMS Accession Accession No.

No.

ML13295A448).

ML13295A448).

3. Code of Federal Federal Regulations, Regulations, 1010 CFR Part Part 50, Appendix G, "Fracture Fracture Toughness Toughness Requirements, U.S. Nuclear Regulatory Requirements," Regulatory Commission, Commission, Washington, D.C., Federal Register, Volume 60, No. 243, dated December 19, 1995.

4. ASME Boiler and Pressure Vessel (B&PV) Code,Section XI, Xl, Division 1, Appendix K, Assessment of Reactor Vessels with Low Upper Shelf Charpy Impact Energy Levels,"

"Assessment Levels, 2007 Edition up to and including 2008 Addenda.

5. ASME B&PV Code,Section XI, Xl, Division 1, Appendix G, "Fracture Fracture Toughness Criteria for Protection Against Failure,"

Failure, 1998 Edition up to and including 2000 Addenda.

12 of 12 12 of 12