ML19320C240

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Submits Addl Info Requested by NRC Re Util 800618 Request for Amend of Tech Specs to Include Addl safety-related Snubbers.Design & Const of Safety Injection Sys Where Snubbers Added Is Discussed.One Oversize Drawing Encl
ML19320C240
Person / Time
Site: North Anna Dominion icon.png
Issue date: 07/11/1980
From: Sylvia B
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Youngblood B
Office of Nuclear Reactor Regulation
References
616, NUDOCS 8007160507
Download: ML19320C240 (34)
v • d • e


Text

>

N VrnorxrA Er.nc rnrc Axo Powen CORPANY Rtcaxoxo,VinorxzA const July 11, 1980 Mr. Harold R. Denton, Director Serial No. 616 Office of Nuclear Reactor Regulation N0/RMB:smv Attn:

Mr. B. J. Youngblood, Chief Docket No. 50-3,39 Licensing Branch No. 3 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

MULTIPLE ST.1CTURE ARS CONCERN NORTH ANNA UNIT NO. 2 In our letter Serial No. 537 dated June 18, 1980, we requested that the North Anna Unit No. 2 Technical Specifications be revised to include additional

' safety-related hydraulic snubbers as a result of recent reanalyses to bring the affected systems into compliance with FSAR commitments. During review of this matter, the NRC staff requested that Vepco provide additional information on the design and consttuction of the safety injection system where the addi-tional snubbers were added and a commitment to resolve the multiple structure Amplified Response Spectra (ARS) concern curren', ' under evaluation on North Anna Unit No. 1.

This letter provides the addi uonal information requested as identified in an NRC memorandum to B. J. Youngblood from R. J. Bosnak as clarified in a subsequent telephone conversation between the NRC, Vepco, and Stone and Webster on July 7,1980.

The additional inforection requested and our responses are given below:

1.

Request A list of all North Anna Unit 2 piping systems which are not similar to those in North Anna Unit 1.

(By not similar, we mean that the system model, analysis and results for a given system in Unit I are not directly applicable to the same system in Unit 2.)

Response

A list of all North Anna Unit 2 piping systems subject to a mulciple ARS concern ewhich are not similar to Unit 1 as defined by the NRC above is contained in Attachment 1.

The listing identifies those systems which are not similar in configuration and analysis for both units. It should be noted that this definitit of similar as applie b to the piping design is more restrictive than our use of the word U $ g similar in our letter Serial No. 510 to the NRC dated June 6,1980.

g It was our intention to state that the results of the evaluation to determine the effect of imposing an enveloping criteria for selecting THIS DOCUMENT CONTAINS

.8007160507 P0OR QUAL.lTY PAGES

~

viuoim tucmc m Poun courm to Mr. Harold R.

enton, Director amplified response spectra on Unit I would be applicabic to Unit 2 due to the similarity in the general piping configurations of the units and the design methods used. We did not intend to imply that the analysis and results were identical for the two units.

A number of systems not included on this list are considered to be similar in configuration and analysis as defined in the Bosnak memo.

These systems have a common analytical model with results applicable to both unf s.

The as-built configuration of these systems, however, is not it

_ical between Unit I and Unit 2 because of variances in the design and location of supports. The variations in location are either within design installation tolerances or have been reviewed by the site stress engineer for acceptability with respect to t)e common analysis.

The variations in design and fabrication of cor-responding supports are resolved by individual analysis.

The supports, although designed to identical loads, may have dif fering maximug load capability beyond the common design loads. Therefore, if it should be required to evaluate s significant support load increase on a common analysis MSK, the evaluation will consider the Unit I and Unit 2 support designs individually.

2.

Request A commitment to resolve the seismic analysis issue for these systems as is being done for North Anna Unit 1.

Reponse In order to justify the North Anna Unit 2 plant piping designs against a potentially imposed enveloping criteria for selecting amplified response spectra, we will commit to perform a multi-phase evaluation on Unit 2 piping systems not similar to the Unit 1 piping systems as defined in the Bosnak meno.

The multi-phase evaluation will be as described for Unit 1 in our letter Serial No. 510 to the NRC dated June 6,1980.

The sequence of events includes a detailed engineering review of all piping problems not similar to Unit No. 1 subject to potential ef fect of mor e than one set of response spectra (Phase I) and calculational evaluation of these problems or of those localized problem areas, where necessary, to demonstrate suitability of design (Phase II).

The Phase I engineering evaluation will com-mence immediately and can be accouplished in approximately six weeks.

Our anticipated completion date for Phase I on Unit 2 is August 31, 1980.

We propose to conduct the Phase II ef fort for Units 1 and 2 in parallel, thus impacting our previous target date for completing Phase II on Unit 1 of September 15, 1980. We believe that a minimum of four months will be required to complete Phase II for both ur4.ts af ter completion of Phase I on Unit 2.

Therefore, our target ( ate for completing Phace II on Units 1 and 2 is December 31, 1980.

If at any time during the detailed Phase I and II ef fort results design of a particular piping system obtained clearly show that a or support cannot be justified against the concept of multiple structure input, the system will be reviewed per Technical Specifi-cation requirements and appropriate action taken.

viaSGu Euctute o Powen Conm To Mr. H' rold R. Denton, Director a 3.

Request

' Provide design and construction information for the safety injection system where the fif teen snubbers will be added (we believe that this system is described by 1GK 104B) as follows:

1 s

3 a.

A detailed explanation for this action, i

l b.

The MSK or. problem number of the same system in North Anna Unit 1.

c.

Isometric drawings (as-built condition) indicating where addi-tional snubbers will be added.

d.

Relevant response spect i at the supports.

i e.

Computer print out showing the input to the problem, complete

/

static and dynamic analyses in the original and modified con-figurations, and the corresonding ASME stress calculations.

The analyses in the modified configuration should be based on envelope spectra as per verbal commitment.

Response

a.

A detailed explanation of the addition of the snubbers in the Safety Injection System was provided to the NRC in our letter Serial No. 575 dated June 27, 1980.

b.

Stone and Webster Drawing No. Il715-MSI-104A shows the corre-4 sponding Unit 1 Safety Injection piping.

c.

Isometric drawing 12030-SAB-104B-5, showing the as-built condi-

)

tion, is included as an enclosure to this letter. The drawing l

shows the locations w:

the additional snubbers have been a

added.

d.

The isometric drawing shows the building attachment point for each support.

The relevant response spectra for the two build-ings involved with MSK-104B are included.

Specifically, we have included ARS plots and supporting input listings for the Reactor Containment External - elevation 256.96, the Missile Shield

~

Structure - elevation 267 and the Reactor Containment External Structure - elevation 204.

c.

As agreed with the NRC in our July 7 telecon, this item applies only to the analysis performed using the envelope spectra and l

the modified support configurations.

}:

We have included a summary of the stress analysis results as to this letter.

We will send additional data to you for the NRC's use.

The additional data will include the i

math nodel of the system, a listing of lumped masses used in

the analysis, 'a list of piping design data, a list of valve and flange weights, _ a set of valve drawings, and a set of enveloped 9

E i

VIkOINEA Etzcruic no l'owru CoxPixv To Mr. Harold R. Denton, Director I

.. ARS citrves 'for ' this- ~sys tem.

This additional data will be com-

piled and forwarded to you as soon as possible.

Our target date for submittal of this data is July 20, 1980.

Please let us know if you have any questiort or comment on the above. We plan to submit a final. detailed report upon unpletion of this effort but would be happy to discuss our progress on this matter with you at any time.

i Very truly yours, B. R. Sylvia

]

Manager - Nuclear Operations and Maintenance RMB/smv:SU4 a

Attachments I'

cc:

Mr. Robert A. Clark, Chief l

Operating Reactors Branch No. 3

-Division of Licensing

Washington, D. C.

-20555 Mr. James P. O'Reilly, Director Office of Inspection and ~ Enforcement Region II.

Atlanta,_ Georgia 30303

.n 9 k

c.

ATTACIDENT 1 Page 1 of 2 List of North Anna Unit 2 Piping Systems (MSK's) which are NOT similar to a corresponding system in North Anna Unit 1-MSK NO.

System 12050-101A MS 12050-101B MS

^

12050-101C MS 12050-101D MS 12050-102A FW 12050-102B FW 12050-102C FW 12050-102D FW 12050-102K Wet Lay-up 12050-102L Wet Lay-up 12050-102M.

Let Lay-up 12050-103B Comp. Cooling 12050-103C Comp. Cooling 12050-103D Comp. Cooling 12050-103E Comp. Cooling 12050-103F Comp. Cooling-12050-103G Comp. Cooling 12050-103H Comp. Cooling 12050-103J Comp. Cooling 12050-103K Comp. Cooling 12050-103L Comp. Cooling 12050-103M Comp. Cooling 12050-103AA SIS 12050-103AC

-CVCS 12050-103AJ SIS 12050-103AQ CVCS 12050-103AS CVCS i

12050-103BB SIS 12050-103BD SIS 12050-103BH CVCS 12050-103BQ Instr. Air.

i 12050-104B LHSI 12050-104E RS 12s50-104F _.

QS j

12050-104G QS 1

12050-104H RH 12050-105A' WS 12050-105B WS 12050-105C WS 12050-105F WS w1

..e

_y:

Page 2 of 2 System MSK No.

SIS-12050-107B SIS 12050-107C QS 12050-107D SIS 12050-107E QS 12050-107H CVCS liO50-111D CVCS 12050-111E CVCS 12050-111F CVCS 12050-111G CVCS 12050-111N CVCS 12050-111Y CVCS 12050-111AC QS 12050-114B RS 12050-114D QS 12050-114E RS 12050-114F.

RS 12050-114G RS 12050-114K RS 12050-114L RS 12050-114M QS' 11715-107E QS 11715-107F SIS 11715-111B CH & SI 11715-111C SI 11715-111AF CC WS 11715-118G CC 11715-118K CC 11715-118N CV (Misc. Piping) 11715-121D SEPIA-

-12050-103A6 (Prob. 710)

Componect Cooling WGCB 12050-103A6, A7 (Prob. 30A,B,C)

Aux. Fced (Prob. 300) 11715-107G CVCS 11715-111A (Prob. 649)

ATTACH tAERT

'2 PAG E I

oF /O I

STONE & WEBSTER ENGINEERING CORPORATION PAGE PIPE STRESS ANALYSIS

SUMMARY

SHEET z._

gg 12050 PROBLEM No.

VEPCO N. ANNA UNIT 2 J.O.

JOB (DENTIFICATION C.'.. c,2c. Titi>, 07-Od %

L.H.5.I.5" ANAtyST

' 7"/ J#

12050-SSR - h (MSR-lO Y3)

CHECKER b' d F PIPING SYSTEM REPORT OR MSK 12050-FP O d, O s C, D 6 (,_

REVISION

- DATE REF. OR AWINGS CLASS 2 AND 3-STRESSES (M AXIMUM) 6ASED OM; Rov.LD55 M AX. STRE_% PTS.*

6-rt-r o CONomON: tWii l.0FE.D CUk.r NBE) - 51X n-g~

a V (.lBJ50 );ll.2.SJv)

CALCULATED POINT No.

BR ANCH No.

STRESS (PSO '

&@ MQ GLP tSet.+ % es STRES$(psi) e/

/

/ % 92.

?lT80 260 35 JLG70

2. 6 /

3G

' / 2. 6 4 /

1 79 36

/2433 2.6 24

//o 3 G

2. 8 Zf 9337 y

1 C t. A L S 7 k3 STM S*LS trict.*JtA AtJCHo a M C'/ E A'.E AJTS 1

ATTACHMENT 2

PA4E

2. cf /C 9

STONE D WEBSTER ENGINEERING CORPORATION PIPE STRESS ANALYSIS

SUMMARY

SHEET

)*E PROBLEM No. <

12050 VEPCO N. ANNA UNIT 2 J.O.

JOB IOENTIFICATION C. 'htC CO.%[ jut 07-09 -SO _

  • L. H. S.1. $.

AN ALYST N-7'9'd3 PIPING SYSTEM 12O50-SSR -3 ( m64-109 8 ) - CHECKER J

REPORT OR MSK

~ ~ "

12050-FP-4A,4 C ; D d E OATE Revision REF DR AWINGS P;A5LD ON:

CLASS 2 AND 3-STRESSES (MAXtMOM)

Ro?.%0%

i 3 ns 6 8 0 AX.5 TRESS PTS.'

ConOiTiOudEtJVELOPED CORVE CDBE,)* SIX M C ALCUL AT ED d

POINT No.

BR ANCH No.

STRESS (PSI)'

M OY M Q sg 1 se se sire 55(P50 4

/G/z.4 3Z. fo70 l2975 9

z8o

/zGL8 26/

/z595 ZG

//907 28

/o/o 6 V

24 3 sTnsa.es met _o oe Anc +w m.w e m ors 4 tecs v w -

Amcaer 2 wAc. e 3 or /c

~

I STONE & WEBSTER ENGINEERING CORPORATION PAGE PIPE STRESS ANALYSIS

SUMMARY

SHEET og a

JOB IDENTIFICATION VEPCO N. ANN A UNIT 2 J.O.

12050 PROBLEM No.

b N b I* b-ANALYST U Jc Cn.WCiuh 07-CS - 80 PIPING SYSTEM 12050-SSR-3 (m44-104B)

CHECKER L M'.k 7-

-30 REPORT OR MSK 12050 - FP-4 A, B. ', D.c_ i, REVISION OATE REF. DRAWINGS SASCO cv; Rc n;gn 7-2.-80 CLASS 1-EQUATION 9 fv0RMAL f UPSET conDI T! o^l 7 iew;

'W'0EI.C? Ebb b VI V'L ** b!)(

MbX bYSb'bb PTba'

^

CONDITION:

OWA8M N SS POINT No.

BRANCH No.

(PSll 1.5 S,,, (P S I) b 2.5 583

?,(.iu:_,c.

112.2.7 sueca 188 18 413

?:0vs.v 900 E34 177E9 50900 90Z.

!762J 3vvDO S

\\~l409

=>O uu O 1

1

A TTAcg AAN T

'2 PA6F 4 OF /0 E

STONE & WEBSTER' ENGINEERING CORPORATION PAGE PIPE STRESS ANALYSIS

SUMMARY

SHEET g

g7 VEPCO N. ANNA UNIT 2 a,c, 12050 PROBLEM No.

JOB IDENTIFICATION L. H. S. I. $"

ANatvST C 'h(L Ut Witu/ C7-Ok-FO PIPING SYSTEM

.N 7-7'80 12050-SSR-3 ( YniX-1043)

CHECKER REPORT OR MSX 12050- FP-4 A 3 O)C., D (, E REVISION -.

DATE REF. ORAWINGS O

6ASED ON; 2073065 7-I-80 CLASS 1-EQUATION 9-FAULTED CONDITION t/

3 0'51

  • /

b bb b IJ b b *'

lI Pi bb U'

CONDITION:

L D M SS AROWABLE STRESS POINT No.

BRANCH No.

(PSI) 3.0 S,. (P SI) 6 25733 60000 189 71547 60000 900 1853) o0000 90E 1780 f e0000 I%

1T756 60000 8

17600 600JJ

+

=

.w.

O A'ITAC HmDUT 2 PAbE 5 OP 10 PAC GTont.r WconTrn Encincen NG cottbonATioff

+

PIPE STRESS AN ALYSIG SUMM ARY SHEET or Q

V E.P C O - M A F> U A # 7_

,,o, 1 Z 0 9,0,, g n o g,,g y y o, Jon locurtricaison sr C W.r-M.F),De G7-t0-eO L. H. 5. l. 5 An, 12 050 - 55 R-3 MS K.- 1043 cyccx co _f &_.,..gj y_,o_yo PIP:NC SYSTEM

~

ntronTonuS4 "4

oArt 1Z050-FP-4 A,6 6 C.

nevision

\\

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R 0 E cj % 5 5 g gg7n nin7.LO A D SUMM ARY

  • O. o. E T."

( EMV E,Lo PE D) 6-80.

Conorion:

CALCULATED FOnCES Atl0 uo;.tEt T3. to. Atl0.*T.-LO.

H.TH AiMT

~

POINT LO C^*'C I g

u, 1

't.,,

g u, no*

OtsCasntan g

p, 1

p, 907 SPR ) R6 909 SIu S E R.. -ESE 6130 910

$ yuks'sa 39Z5 16I 71 6 SPRIUG 109 gy['h 112 1 f

l SPRlU6 4 I683 j

SSb VE RT. SUUg 1064 dbC V

. 5, U 13 0

$1g' lb i l '

84Z-5*

15 8 SPRIMG 6PN'NU 6 633 lbZ VERT.SMUB.

Eb6 vg h $ fg f IZ3b'!

274-[h[33,PRM I858 5 11 32.

s 505l VER

~

Z84 g,gi E90 AMCHOR ZO73 3Eb 4961 3618 9701 E31L 35 gN6 93 5348 SPKIN6 6 14 0) 40 VERT. SuuP;.

19I vkUN.'s"Nuk 2936 SPRING (

O29 c,7

~

VERT.5MOS 56

(,fy, 19 01 955

. ATT&x MENT 1.

PAGE G cp /C PAcc 2 STON E. G. VIE RGTr n !?NGIN EERIN G CO R'PO R ATION 4

PIPE STRESS ANALYSIS

SUMMARY

SHEET or 4' Z-3.o.17.05t__ rnootrn no _47-0

.rori soturiricar,r,on VE PC O - N A U M A up 07 60 An a ty s r C,. '>n c. C/vm.

PIPING SYOTtM __ L. H. 5. l. S'

~

neronion uss I2050 -55 2-h M5K-104_b cuccnco P d~-> #7!. 4 3-e6-Bo

~

./ 0 n ty,3,ou

- 04rr ner.onawinc.s 12.0 50 - F P-4 A, 6 6 C.

~

ROE 9055 R ESTR AINT*LO AO SUMM ARY f

-Bo.

" O. 6. E. T.* ( E MVE Lo PED) conomon:

catcutarco ronces Ano uourrirs. to.4no.*7.-to.

nesinarnr

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y p,

+

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DiSCnlPrio.e

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p,

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p, b4 6PRIU6 2 Z.0 vp)[73d6 k

'283 g0 23 6 AUGHOR l 71 2 EZ.0 1007 3337 3876

2. % 9 15P Ri tJ6 l' 1011 OI VE RT. 5Mu t

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Arrenwur 2 P%e 7 cF /o GTotlE.rm WEDGTrH FNGINEERitJG CORDOR ATIOtl PAcc b 4

PIPE STRESS ANALYSIS ~SUMM ARY SHEET or R

Jon loEntirscATion NEPC.O - M A MMA R 2

,.o. GO 5 0 ioat.c n o.

L. H. S. i. 5" C.. 'h /

iA; tA O'7 6 0 An Ai.y si PIPING SYSTEM 17.050 - SS R-3 MSK-1043 cnccxco p %e,aja u 7 -, o -w

~ nEronT on uSg

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nEvision oATE R

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~

3

" D. S. E.1"

( E.N V E LO PE D'>

b - l Z.- 80 conomon:

11ESTi!AINT CAlcutATEo FORCES ANo uoMEtlTS to. Allo FT.-to.

PotNT LOCATION /

DiSCn\\PTloM f

5, f

5, R F M,

f, "M R hi r

g y

g 907 SPRING

'^7

~

909 sNu8hER 253 5689 910 shu^3agg 3515 14 5 7-

' Eb SPRING 10 9 p36 1883 SPKIN6 4 1569 E56 VERT. swue SPRIN6 E 1039 E60 vsRT.sMua 130 E5' 1589' 7E4 9,

15 8 SPRING 162. vtfgy.Tyuk.

593 6

D SPRlh>6 &

1105-E66 vtgy. syug.

4 E74[^vih7%"oe 1758 499 31 5

b Z84

EERIs 507i e

2.90 AMC. HOR E.7. 51 360 SM5 4304 94Z.5 1.717 35 d$Io.

87_.

4686 SPR'M6 6 40 VERT. SMU{

IIbb SPRIN6 -6 ggI-VERT.sMOB E358

<?RIN G S bb VERT.SMU8.

Mb 56

$.N/.

162.5 769 S

i

..1.

Arrac.umevr q_

PA4e B oF /d 4

STON E.G, WEnGTrli FNGINEERING CORPOR ATION PACC 4 PIPE STRESS ANALYSIS

SUMMARY

SHEET or 5C$

N' O - O-O

llr, l,*,','l*e 'rQ'7gu'*?E. 1. S.S s

neronT an uss Il 0 5 0 -M " -b W -\\0 % sucCxc0 2hw

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=

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% 6 E C-nEVISION DATL RON055 R ESTR AINT LO AD SUMM ARY

~

3775

  • D.3. E,.T " ( ENVE LO PE.D) 6-it-Bo.

Cou0 mon:

1 flESTi!Al?!T CALCULATED FonCES Atto uoMEllT3 tu. Atto F'f.-LO.

PolflT LOCATION /

g r,

+

u, t, 'n, t u, DisCntnlon

+

p, g

p, 64 SPRING SPRI N6 h E68

. E7 O VERT. SNUB 2.26 ANCHOR.

1895 Z49 ZE%

3978 3738 E7E4 SPRIN6 4 ggg gI VERT. SNUS.

j 4

i i

l e

e I

I 6

1 or PIPE STRESS AN ALYSIS SUMM ARY SHEET 42 VEPC O,_N. ANNA UNtT4 2.

3.o.,_12050maIohe u no.

.i, 4%

9 80- 9 o

.rosi erer nier er:ArlonL.H. S AFETY I NJ.

S YS.

auntysr 12050- SS R-3 MSK-lO4 B _ c,,ccrta f,Lmd 7-t o W3 t,s.,nc sisT ru nu oier on use onE 12050-FP-4 A, B 6 C.

n cy, sic 9 scr. caawincs EQUIPMENT LOADING SUMM ARY EQUIPMENT l.D. LH.S.I. PUMP NOZZ LE PO!NT NO, CALCULATED FORCES (LB)

CALCULATED MOMENTS (FT-L5'.

LOA 0!NG CONDITION Fx FY FZ MX MY MZ

" O. B. E. I."

i 118 4 697 665 1580 2632 343

  • D. B. E. I. "

I265 692 671 1575 2672 337

" O. B. E. T.

i 12.4 9 729 Til 16 %

3t40 684

' D. B. E. T. "

1361 738 739 1744 3 419 837

  • D L"

-2 207 1

-225.

-S 232.

l l

i1 I

ALLOWABl.E LOADS

'I

.l Fx FY Fr Mx Mr Mz CONDITION i

NOTES AND REFERENCES i

BASED ON RO293055 J TIS 06-12 i 1

I

t Act STOf1C 6 Wl'.!: STER 1:::GifJCCHil4G C o ll!'O H ATIO rJ or PIPE STRESS ANALYSIS

SUMMARY

SHEET M

. inn int niin ir.ATIOta 7EPCO_JJ. ant 4 A UNIT #2.

, o',,_tE0 50 - ::

u no.

NGP M

9 /1 /80 L.H. SAFE ty I N y. s yS.

A N A t.y s r N 9CNf*

7

'O~SO retenG 9 510u 12 O 50- 559t-3 Msk-t O 4 8 C H r. c M C o._

nr.s orir on u x DATC-120 50-W-4 A,8 f c REvls 0N HEr. OR Aw NGs EQUIPMENT LOADING SUMM ARY L.RS.I. PUMP MOZILE ( 2-si-P-1 A)

POINT NO.

58 EQUIPMENT l.D.

CALCULATED FORCES (LB)

CALCUL ATED MOMENTS (FT-LE'.

LOADING CONDITION Fx FY FZ Mx MY MZ

" O B. E.I. "

1698 110 5 740 2288 1760 373 1565 1020 694 21\\8 l647 351

\\ D B. E. I. il

" O. B. E.T "

l'793 1140 797 2383 237c) 721

" D.B.E.T.#

1 170 4 1012 777 2263 2561 874 3

271

-1 256

-16 (98 "b L" ALLOWABLE LOADS Fx Fy Fz Mx MY Mr CONDITluN

~

i NOTES AND P.EFERENCES BASED ON RO293055 J 715 06-12.-80

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