ML20210N640

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Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl
ML20210N640
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/03/1999
From:
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-96-06, GNRO-99-00059, NUDOCS 9908110173
Download: ML20210N640 (16)
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Text

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O ,,

Entergy operations, Inc.

Port Gibson. MS 39150 Tel 601437 2800 4 a August 3,1999 U.S. Nuclear Regulatory Commission ,

Mail Station P1-37 Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Generic Letter (GL) 96-06, Requested Sample Piping Analysis GNRO-99/00059 Gentlemen:

In response to GL 96-06 Grand Gulf Nuclear Station (GGNS) committed, in a letter dated November 4,1997, to take appropriate action to resolve the nonconforming condition for each Containment /Drywell penetration, determined to be susceptible to overpressurization due to thermal expansion of fluid. The eighteen identified penetrations will be restored to conformance with the licensing requirements prior to restart from RFO10 (now scheduled for Fall 1999).

At the request of Mr. Pat Sekerak, GGNS submits an example of the piping analysis being performed for the eight penetrations identified as being acceptable per analysis, (see summary table below). Please refer to Attachment 1 for the sample analysis for one penetration.

The current breakdown of the planned resolution is as follows:

Modification Procedure Valve Closure Time Acceptable per Required Change Change

  • Analysis 4 6 penetrations 2 penetrations 2 penetrations 8 penetrations i, This change is cpphbtkp'on NRC approval of a pending revision to the GGNS

/

licensing basis th5t includes a relaxation of the containment isolation valves closure times. This submittalis currently under NRC review. e x -)$

9908110173 990803 I}O '

PDR ADOCK 05000416 l P PDR

I

  • GNR6-99/00059 l Page 2 of 4 GGNS would also like to take this opportunity to clarify a point made in our June 9,1999  ;

letter. The descriptions of the planned resolutions for several penetrations included the I statement " Piping has been qualified using Appendix F of the ASME Code, Section Ill".  ;

GGNS's UFSAR specifically addresses the use of Appendix F in the analysis of Class 1 l piping, Non-NSSS equipment and Class 2 Non-NSSS vessels. However, the penetrations of interest are ASME Section lil, Class 2 Non-NSSS piping. Therefore, in accordance with GGNS UFSAR Table 3.9-22 the design criteria to be used in the piping analysis of ASME Section Ill, Class 2 Non-NSSS piping, in the faulted condition, must conform to the requirements of ASME Code Case 1606-1. This methodology is essentially the same as prescribed in Appendix F, except for slightly lower allowable stresses. Therefore, as the evaluation of the penetrations is being finalized, GGNS will use ASME Code Case 1606-1 methodology and equations to determine the acceptability of the penetration piping.

Please feel free to contact Dana E. Smith at (601) 437-6434 should you have any questions or require additionalinformation.

I Yours truly, DES /LFD Attachments: (2) cc: (See Next Page) a

r1 GNR6-99/00059 Page 3 of 4 cc: Ms. J. L Dixon-Herrity, GGNS Senior Resident (w/a)

Mr. L. J. Smith (Wise Carter) (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. E. W. Merschoff (w/a).

Regional Administrator U.S. Nuclear Regufatory Commission _ l Region IV '

611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Mr. S. P. Sekerak, NRR/DLPM/PD IV-1 (w/2) ,

U.S. Nuclear Regulatory Commission i One White Flint North, Mail Stop 13D18 l 11555 Rockville Piko l Rockville, MD 20852-2378 l

bec: File (LCTS/RPTS) (w/a)

File (Hard Copy)(w/a)

File (Central) (w/a) (16) l l

l j

i

' GNRD-99/00059 Page 4 of 4 E-mail:

  • Mr. W. B. Abraham Mr. W. K. Hughey Mr. G. R. Ashley (ANO - LIC) Mr. M. G. Hurley Mr. J. G. Booth Mr. C. R. Hutchinson (ANO - VP)

Mr. C. A. Bottemiller IEA (ANO - OE)

  • Mr. P. W. Brewer Mr. D. E. James (ANO - LIC)

Mr. C. E. Brooks Mr. R. S. Johnson Mr. O. P. Bulich (RB - OE) Mr. M. L. Jones Mr. F. G. Burford Mr. R. J. King (RB - LIC)

  • Mr. R. W. Byrd Mr. C. W. Lambert Mr. W. C. Cade Mr. M. J. Larson Mr. R. W. Carrol Ms. J. M. Manzella (W3 - QP)

Mr. W. F. Clark Mr. J. R. McGaha (ECH)

Mr. D. G. Cupstid Mr. T. O. McIntyre

  • Mr. J. P. Czaika Mr. R. V. Moomaw Mr. L. F. Daughtery Mr. S. D. Reeves Mr. G. G. Davie (W3 - LIC) Mr. J. C. Roberts
  • Mr. D. R. Denton (ANO) Mr. J. L. Robertson
  • Mr. C. M. Dugger (W3 - VP) Mr. W. M. Shelly Mr. W. A. Eaton Mr. C. D. Stafford Mi. C. W. Elisaesser Mr. G. D. Swords Mr. J. L. Ensley (ESl) Mr. R. L. Thomas (ECH)
  • Mr. E. C. Ewing (W3 - LIC) Mr. T. H. Thurmon ,

Mr. R. E. Garrison (M-ECH-411) Mr. J. D. Vandergrift (ANO - LIC) l Mr. T. J. Gaudet (W3 - LIC) Mr. J. E. Venable  !

Ms. C. W. Gunn Mr. A. D. Wells (RB)

Mr. C. D. Holifield Mr. R. A. Wilson

  • Always include on distribution

Attachment 1 to GNRO-99/00059 Page 1 of 3 SAMPLE EVALUATION FOR ONE PENETRATION ASME Code Case 1606-1, for Class 2 piping states:

For Class 2 Piping subjected to Faulted Operating Conditions, (a) The permissible pressure shall not exceed 2.0 times the design pressure (P) calculated in accordance with Equation (4) of NC-3641.1.

-AN D-(b) The sum of the longitudinal stresses produced by occasional loads defined in the design specification as faulted condition shall not exceed 2.4 times the allowable stress values given in Tables I-7.1 and I-7.2 of Appendix 1. Under faulted conditions, the quantity on the right-hand side of Equation (9) of NC-3650 shall be 2.4 Sm Equations (8), (10), and (11) need not be considered.

It is Grand Gulf's position that both requirement (a) and (b) must be mot to condode that no relief mechanism is needed ..

Compliance with requirement (a)

NC-3641.1, Equation (4) is as follows:

2S,(t., - A) 7 D - 2y(t,, - A) t,,, = Use nominal wa!! tNckness, (n). . , 1 A = Corrosion ai!owance per Spe:feston GGNS4*JM82 0 = Outside diameter of the pipe. (n). , y, _

y = 0.4 S,, = Maximum allowable stress awe DJsvi MINMWb##y#g 'g; Appendix 1, table I-7.0. (psTt 1-

"? g~' '~

. 7a97' ^

The value of Pis calculated, doub'ed aN =mpardWhrradNSh((~ [$hi '

96-06 ff the GL 96-06 pred~ctedcr?ssue irdatternertm ,,

appropriate measures are beirg L&c in (nowdu ;**"'" "*

_i' .

IWa@)#& JL hhh6'x . ' ' ' ' ' '

Attichm:nt 1 to

. GNRO-99/00059 Page 1 of 3 SAMPLE EVALUATION FOR ONE PENETRATION ASME Code Case 1606-1, for Class 2 piping states:

For Class 2 Piping subjected to Faulted Operating Conditions, (a) The permissible pressure shall not exceed 2.0 times the design pressure (P) calculated in accordance with Equation (4) of NC-3641.1.

-AN D-

' (b) The sum of the longitudinal stresses produced by occasionalloads defined in the design specification as faulted condition shall not exceed 2.4 times the allowable stress values given in Tables I-7.1 and I-7.2 of Appendix 1. Under faulted conditions, the quantity on the right-hand side of Equation (9) of NC-3650 shall be 2.4 Sn.

Equations (8), (10), and (11) need not be considered.

It is Grand Gulf's position that both requirement (a) and (b) must be met to conclude that no relief mechanism is needed Compliance with requirement (a)

NC-3641.1, Equation (4) is as follows:

2S3 (t., - A)

P=

D - 2y(t,, - A) t,,, = Use nominal wall thickness, (in).

A = Corrosion allowance per Specification GGNS-MS-03, (in).

D = Outside diameter of the pipe, (in).

y = 0.4 S,, = Maximum allowable stress at the Design Temperature per ASME Section 111, Appendix 1, table I-7.0, (psi).

The value of P ls calculated, doubled and compared to the predicted pressure per GL 96-06. If the GL 96-06 predicted pressure is determined to be larger than 2P, then appropriate measures are being taken to provide pressure relief for the pipe.

Attichm;nt 1 to .

. GNRO-99/00059 Page 2 of 3

. Compliance with requirement (b)'

Since all the affected penetrations include only ASME Class 2 piping, the rules of NC-

' 3650 and ASME Code Case N-1606-1 have been used to satisfy the requirements of (b).

NC-3650, Equation (9) for Occasional Loads, Level D is expressed as follows:

Sa= Sr(pressure stress) + S,(weight stress) + Ss(stress due to dynamicloads) S 2.4Si in the calculation of the stresses, the load combinations specified in Appendix C of Grand Gulf Specification SERI-M-220.0 Revision 0, " Design Specification for Nuclear  !

Piping Systems, Safety Related" were used. See Attachment 2 for more details. I The related piping stress calculations were reviewed and, S (weight stress) and S, (dynamic stress) values were extracted. The moment loading remained unchanged.

.The pressure stress is calculated as follows:

Pd' Sr = 9 _g2 2

P = Predicted ' pressure per GL 96-06, (psi).

d = Inside diameter of the pipe, (in)..

D = Outside diameter of the pipe, (in).

The calculated total stress value (S,), using the GL 96-06 pressure stress, is compved to the allowable limit (2.4S,,).

- When both requirement (a) and (b) have been met, the piping is considered acceptable.

1 l

w i Attichm:nt i to

. GNRO-99/00059 i Page 3 of 3

, . 1 SAMPLE CALCULATION:

Containment Penetration No. 50 Containment Isolation Valve Q1P45F067 Gate Valve Auxiliary Building isolation Valve Q1P45F068 Gate Valve-Containment Stress Calculation No.- PDS-99 Rev 7 Auxiliary Building Stress Calculation No. PDS-100 Rev 12 Line No. 6"-HBB-102 Outside Diameter - 6.625" )

Nominal Thickness .28' Corrosion Allowance .08" Material SA106-B Design Pressure 150 psig Maximum Pressure 35 psig GL 96-06 Predicted Pressure 1250 psig - I Design Temperature - 150*F Maximum Temperature 140'F Sn 15,000 psi i

Compliance with requirement (a) i 2S,(t, - A) 2x15000x(.28 .08)

P=

D - 2){t, - A) = 6.625 - 2 x .4 x (.28 .08) = 928psig The predicted pressure of 1250 psig is less than 2 x 928 = 1856psig Compliance with requirement (b)

The new pressure stress is calculated as follows:

Pd 2 = 1250x(6.625 -(2x.28)]' = 6470 psi S' = D 2 -d 2 2 6.625 -(6.625-(2 x.28)]2 The related piping stress calculations were reviewed and stress values were extracted.

The calculated total stress value was compared to the allowable limit (2.4S,,).

Calculation Predicted Weight Stress due to Total 2.4 Sn Acceptable?

No. Pressure Stress Dynamic (psi) ' (psi)

Stress (from calc.) Loading (from calc.)

PDS-99 6470 339 20488 27297 36000 Yes PDS-100 6470 1839 20518 28827 36000 Yes

. Since both requirement (a) and (b) have been met, the piping is considered acceptable.

L. ., .. _ . .

cati n No.: $IRI-M-220.0

- ATTACHMENT 2 fh'p x Revisicn No.: 0

(

TO GNRo- 99/coose ,

l'-

PAGE  ; 0F 9 t

SYSTEM ENERGY RESOURCES, INC.

GRAND GULF NUCLEAR STATION UNIT 1 DESIGN LOADING COMBINATION FOR ASME CODE CLASS 1, 2 AND 3 COMPONENTS SAFETY RELATED

  1. mm M

i l ~

NWPMSP M-220.0 R-0 APP C COV

1 j! SPECIFICATION NO.: MP&L-M-??0.0 j ATTACHMENT --- APPENDIX: C 1 TO GNRO- 99/o0659 REVISION NO.: 0 PAGE: 2 PAGE 2 0F 9 5

REVISION STATUS SHEET SPECIFICATION REVISION

SUMMARY

REVISION DATE DESCRIPTION O 09/18/89 Issued for Use 1

                                    • s*************************************************************

PAGE REVISION STATUS l i

I PAGE NO. PEVISION NO.

1 0

? O 3 0 4 0

'S 0 6 0 7 0 8 0 9 0 NWPMSPRSS M-220.0 R-0 APP C

'~~

Specification No.: SERI-M 220.0

. ATThCHMENT 2! App;ndix: C 10 (24/go. 99j43cosq ,

Revision No.: O Pag 2: 3 PAGE 3 0F 9 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 LOADING DEFINITION LEGEND 2.0 LOADING COMBINATIONS i

e NWPMSP M-220.0 R-0 APP C TOC

Spzeification No.: SERI-M-220.0 ATTACHMENT 2 Appendix: C To GAjRo- 99/ coos 9 - Rsvision No.: O

  1. N PAGE y . OF 9 i

1.0 , LOAD DEFINITION LEGEND l 1

PD Design pressure i

Pmax Maximum operating pressure Ptest . Testing Condition pressure j i

Loads due to linear themal expansion of the pipe Thermal (TH)

OBE Operational basis earthouake loads SSE Loads due to vibratory motion from safe shutdown earthquake loads .

SRVX SRV1 or SRVA11, whichever is controlling SRV1 Safety / relief valve discharge induced loads from one valve's subsequent actuation l

SRVALL .The loads induced by actuation of all safety / relief valves that activate within milliseconds of each other (e.g., turbine trip operations transient)

SRVADS The loads induced by the actuation of safety / relief valves  !

associated with the Automatic Depressurization System that actuate

~

within milliseconds of each other during the postulated small or' intermediate size pipe rupture DBA Design basis accident: the sudden break of the main steam or ,

recirculation lines (largest postulated break); DBA related loads include main vent clearing and pool swell, chugging, condensation oscillation, and annulus pressurization SBA' Small-break accident l IBA Intemediate-break accident FV- Fast Valve - Relief valve open system, steam / water hamer l PSPT- Pool swell pressure transient AP- Annulus pressurization 1

~

DNPT Drywell' negative pressure transient-HYDRO Weight of piping system during hydrotest conditions RVC Relief valve closed system

!=

l SAM Seismic anchor movement NWPMSP M-220.0 R-0 APP C TEXT'

Specification No.: SERI-M-220.0 ATTACHMENT 2 Appendix: C TO GNAO- 99/coosq . R: vision No.: 0

  1. 9

. PAGE S OF 9 APAM , Anchor movement due to annulus pressurization WH y Loads on the CRD System due to water hammer for full power, low power, or insert rod, whichever is controlling WH Loads on the CRD system due to start-up water hanner ST WH yg Loads on the CRD system due to failed-buffer water hanner e

1 l

l NWPMSP M-220.0 R-O' APP C TEXT

E ~ Spc:ification No.: SERI-M-220.0 ATTACHMENT 2 Appendix: C 0

TO GNRo- 99/coosa -

10[No.:

. == a or 9 l 2.0 . LOADING COMBINATIONS 2.1 The following points will be considered in combining piping loads to calculate piping stresses and support loads,

a. SRVALL or SRV1 (whichever is controlling) will be used.
b. SBA or IBA, whichever is greater will be used. SBA/IBA result in Jet impinoement and thrust loading on the piping.
c. Loads will be added using the absolute sum method with the exception of dynamic loads, for which the SRSS method will be used. SRSS combination for dynamic loads is approved by NRC in Grand Gulf SER, NUREG-0831 Supplement No. 2, Sect. 3.9.3.
d. All ASME Class 1, 2, and 3 piping systems which are required to function for safe shutdown under the postulated events shall meet the reauirements of Appendix D, Page 6 " Functional Capability of Passive 1 I

Components".

e. Loading combinations for calculating piping stresses are given in paragraph 2.2.
f. Loading combinations for calculating support loads are given paragraph 2.3.

i a

e NWPMSP M-220.0 R-0 APP C TEXT

~

Specification Ro.: N 220.0 ATTACHMENT 2 Appendix: C To GAlRo- 9q/ceosq ! , Revision No.: 0 Page: 7

. PAGE 7 0F g 2.2 The following combinations shall be used in the piping stress analysis.

. Primary Stresses Normal Operating Condition:

PD + Weight Upset Condition:

P + Weight + OBE 2

P + Weight + (OBE2 ,py2 + SRV2 x + Quencher Wtr/ Air Clrg )1/2 max P + Weight + RVC max

. P + Weight + (oBE + SRV,2 + WH 2)1/2 max P,y x + Weight + WHST Emergency Condition:

P + Weight + (SSE + SRVx2+ WH 2)1/2 (See Note 3) max Faulted Conditions:

P,,,+ Weight.+(SSE2 , py2 + SRV2)x P + Weight +(SRVADS + Chugging 2 + SSE2 )1/2 max 2 1/2 P,,, + Weight + Poolswell +[(Vent Air Clearing + PSPT)2 + SSE 3 2 1/2

+ SSE 3 P ,,x + Weight + Fall Back + [ Steam Cond./ Chugging 2

P,,x + Weight + (SSE2 + AP )1/2 P,,x + Weight + (SSE2 + DNPT )II P ,,x + Weight + SSE + Jet Impingement Test Condition:

Ptest + Hydroweight Secondary Stresses Thermal + SAM + APAM (See Note 1)

Primary ar.d Secondary Stresses P D + Weight + Thermal + SAM + APAM (See Notes 1 & 2)

NWPMSP M-220.0 R-0 APP C TEXT

3 F

Specification No.: SERI-M-220.0 {

ATTACHMENT 12

' App 2ndix: C j TO GNRo - q q / coos 9 - Revisicn No.: 0

, PAGE g 0F g Page: 8 i

  • NOTES: 1. If (SAM + APAM) > Thermal, substitute 2 x (SAM + APAM) for Thermal + SAM + APAM.
2. For Class 1 piping primary plus secondary stresses should be l I

combined per ASME Code.

3. Emergency condition applies to CRD system only.

l l

i 0

t l

NWPMSP M-220.0 R-0 APP C-TEXT

ATTACHMENT Specification No.: SERI-M-220.0 2-

, Appendix: C TO GNRo- 99/coasq Revision No.: 0

', 0F q Page: 9

, PAGE 9 2.3 The following loading combinations shall be used in developing pipe support load breakdowns.

Normal Operating Conditions TH + Weight Test I

Hydro g,setConditions SAM + TH + Weight + OBE SAM + TH + Weight + (0BE2 + FV2 + SRV + Quencher Wtr/ Air Clrg2 )1/2 x

SAM + TH + Weight + RVC i

SAM + TH + Weight + WH ST SAM + TH + Weight + (0BEI + SRV x + WHx)

Emergency Condition SAM + TH + Weight + (SSE2 + SRV + WH (See Note 1) x FB ) /

Faulted Conditions (See Note 2)'

SAM + TH + Weight + (SSE2 , py2 + SRVx)

SAM + TH + Weight + (SRV + Chugging 2 + SSE2 )1/2 ADS SAM + TH + Weight + Poolswell + [(Vent Air Clrg + PSPT)2 + SSE ] I 2

SAM + TH + Weight + Fall Back + (SteamCond/ Chugging 2 + SSE )1/2 SAM + TH + Weight + APAM + (SSE2 + AP2 )1/2 2

SAM + TH + Weight + (SSE2 + DNPT )1/2 SAM + TH + Weight + SSE + Jet Impingement NOTE: 1 This load case is applicable only for the Control Rod Drive

- (CRD) system.

NOTE: 2 The faulted thermal value is the worse case of accident thermal or operating thermal. ,

NOTE: 3 When combining anchor loads from two sides, respective dynamic loads may be combined by SRSS method.

+

NWPMSP M-220.0 R-0 APP C TEXT e

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