ML17276B371

Forwards Response to SER Question 23 Amending Util 820114 Response Re Criteria for balance-of-plant & NSSS Tables. Info Will Be Incorporated

ML17276B371
Person / Time
Site:	Columbia
Issue date:	02/19/1982
From:	Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
GO2-82-237, NUDOCS 8204010489
Download: ML17276B371 (13)

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REGULAT INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:8200010489 DOC ~ DATE: 82/02/19 NOTARIZED: NO DOCKET FACIL:50-397 NPPSS Nuc lear Projects Unit 2~ l<ashington 'Public Powe 05000397 AUTH. NAME, AUTHOR AFFILIATION BOUCHEYpG,D. liashington Public Power Supply System

'RECIP.NAME, RECIPIENT AFFILIATION SCHNENCERgA ~ Licensing Branch 2

'V V SUBJECT'orwards response to SER Question 23 amending util.620114 response re criteria for balance-of-plant 8 NSSS will be incorporated.

tables'nfo DISTRIBUTION CODE: B001S 'COPIES RECEIYED:L'TR ENCL 1 SIZE:

TITLE: PSAR/FSAR AMDTS and Related Correspondence h

NOTES:2 copies all matl:PM ~ 05000397 RECIPIENT COPIES RECIPIENT 'COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME L'TTR ENCL A/D LICENSNG 1 0 LIC BR 02 BC 1 0 LIC BR 02 LA 1 0 AULUCKgR ~ 01 1 INTER(AL: ELD 1 0 IE 06 1 1 IE/DEP/EPDB 35'PA 1 1 IE/DEP/EPLB 36 3 3 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EQB 13 3 3 NRR/DE/GB 28 2 2 NRR/DE/HGEB 30 2 '2 NRR/DE/MEB 18 1 1, NRR/DE/MTEB 17 1 1 NRR/DE/QAB 21 1 1 NRR/DE/SAB 2Q 1 1 NRR/DE/SEB 25 1 -1 NRR/DHFS/KFEBOO 1 1 NRR/DHFS/LQB 32 1 1 NRR/DHFS/OLB '30 1 1 NRR/DHFS/PTRB20 1 1 NRR/DS I/AEB '26 1 1 NRR/DS I/ASB 27 -1 1 NRR/DSI/CPB 10 1 NRR/DS I/CSB 09 NRR/DS I/ETS8 12 1 1 , NRR/DSI/ICSB 16 1 1 NRR/DS I/PSB 19 NRR/DSI/RAB 22 1 NR S I/RS8 23 1 NRR/DST/LGB 33 1 1 E FIL 00 1 1 RGN5 '2 2 EXTERNAL: ACRS 41 16 16 BNL(AMDTS ONLY) 1 FEMA REP DIV "39 1 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 (8

~TOTAI NUMBER OF COPIES REQUIRED: LTTR 5 . ENCL 8

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8204010489 820219 PDR ADOCX OSO0OS97 PDR Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 February 19, 1982 G02-82-237 SS-L-02-PLP-82-007 Docket No. 50-397 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

0 NUCLEAR PROJECT NO. 2 SUBMITTAL OF SER OPEN ISSUES

'/

Reference:

Letter, G.D. Bouchey (SS) to A. Schwencer (NRC),

G02-82-41, Same Subject, dated January 14, 1982 The reference letter submitted Supply System responses to various NRC Branch/Supply System meetings. Attached is an amended response to MEB 23 provided in the reference letter. This amended response verifies that both BOP and NSSS tables provided in the original response use the same criteria: "Evaluation of Topical Report - Piping Functional Capability Criteria", dated July 17, 1980. This revised response will be inserted in a forthcoming FSAR revision.

Very truly yours, G. D. Bouchey Deputy Director, Safety and Security PLP/jca Attachment cc: R Aul uck - NRC gooI WS Chin BPA Feil - NRC Si te R

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3.9.3 .ASME Code Class 1 2 and 3 Comrmnents,Comrmnent Su orts and Core Su rt Structures 3.9.3.1 Loadin Combinations Desi 'Transients and Stress Limits Question 23 The loading combinations and stress limi.ts used in the design of (1) all ASME Class 1, 2 and 3,systems,- components, equip-ment and their supports, (2) all reactor internals a'nd (3) control rod drive components need t'o be clarified in the,FSAR Section 3.9.3.1 and the majority of Tables 3.9.2(a) through 3.9.2 (ac) in the PSAR do not clearly defin'e 'the loading and stress limits. We will requi~e a concise sum>> com-'inations mary (preferably in table form) of this iziformation'. This summary should include a listing of all th'e loads which were considered for each service condition or load case plus the acceptance criteria. Appendix 110-1 to NRC Question 110.27.

contains loading combinations and acceptance criteria appli-cable to all of the above system, components, equipment and supports. Table 3.6-5 of the Ngp-2 "Plant Design Assessment or SRV and. LOCA Loads" presents information which is not completely acceptable. We will require a commitment to the Appendix 110-1 mentioned above. Xn addition, we will require a clarification of the applicability of Table 3.6-5, i.e.,

are all of the loading combinations and acceptance criteria in Table 3.6-5 applicable to all of the systems, etc., discussed in the first paragraph above.

components,'quipment,

Response

The Table number 3.6-5 in the question 'appears to be in error.

Table 3.5-5 appears to be the table to which the question, refers.

See revised Table 3.5-5 of the WHP-2 "Plant Design Assessment for SRV and LOCA Loads" for load combinations and acceptance criteria for balance of plant (attached)"..

See Table Q23-1 for the load combinytions and acceptance cri-=

teria for NSSS piping and equipment.

1 Summation The effects of hydrodynamic loads listed in:the load combination table will be documented in the New Loads update. This item is closed.

. TABLE 2.5-5 (BAR R '2).

LOAD COMBINATIOHS AN&" ACCZPTAHC CRANIA FOR ASIDE CODE CLASS 1 2 and 3 BOP PIPING "AND EQUIPMENT **

9.. ',-

qP) ~

Load  :

pesign Assessment C)l )) rr h I;oad Coinb ina t i ons Kcce tance Criteria P+6, N.

r

".

Hormal h)' )r=

(A)

H+'BE +SRVOHZ Upset (B)

H+ OBE +SRV Upset (B)

TWO H+ OBZ +SRV 'eset (B)

H+ OBE +SRV +SBA Emergency * (C)

H+ OBE +SRV +SBA Emergency * (C)

H+ SSZ +SRV +SBA/IBA Faulted

• N+ SSZ +SRV +SBA/IBA Faulted * (D) 9 H+ SSE +SRV OHZ Faulted * (D) 10 H+. SSZ +SRV

~

Faulted * (D)

H+ SSZ +SRV AZZ Faulted * (D) 12 N+ SSZ +DBA ,r:,,.Faul,ted * (D) h (1) As equired by the appropriate subsection. i.e., HB, HC or HD of ASSAM Section XII, Division 1, other loads, such as the~1 t=ansient, thermal gradients, and anchor point dis-placement portion of the OBE or SRV, may require consideration in addition to those primary stress-producing, loads listed.

(2) SBA, IBA, and DBA include all event induced loads, as applicable, such as chugging, pool swell, drag loads, annulus pressuriza-tion, etc.

• All ASME Code Class 1, 2 and 3 piping systems'-which are required to function for safe shutdown under the postulated events shall meet the equirements of NRC's memorandum, "Evaluation'f Topical Report- Pipin Functional Capability Criteria", dated July 17, 1980.

h

'"'Equipment includes pumps, valves, supports, vessels. For belting used in, connection with the support of ASME Code Class 1,2, and 3 components, vendor load capacity data sheets are used or where design is by the architect engineer, stress levels are maintained less than specified minimum yield at temperature.

4N r rrrlrhrN r h N ~ r h ~ ~r

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r) W 4r)'rhr )*)lh'h hi h);

LOAD DEF32TITIOH LEGEND (Table 3.5-5) f.

Eoxmal (N) Normal loads include ixiperqel pressure and dead weight Operational Basis Earthquake lqads SSZ Safe Shutdown Earthquake loads SRV Safety/relief valve diacharge induced loads from two adjacent valves SRV The loads induced by actuation of all safety/relief valves SRV The loads induced by the actuation of safety/relief valves associated wiM the automatic depressurization system SRV The loads induced by the actuation of. one safety/relief valve Small Break Accident:

Int:ermediate Break Accident DBA Design Basis Accident

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0

LOAD N5LHAILUN Hnu ~vvcr<w~ic i~xi ASME COOE CLASS l, 2, ANO 3 NSSS P I P ING ANO fgUIPHE NT Design Evaluation Serv ice)

N Load Combination

+ SRV'(~)

Basis Upset Upset

~s r Upset.

Upset

'8) Level J (s)

N + OBE + SRV Emergency Upset (g)

N + SSE + SRV(~) Faulted Faulted (o)

N + SBA + SRV Emergency Emergeacy (c)

N + IBA. + SRV Faulted Faulted (o)

N + SBA + SRV Emergency Emergency (c)

MS)

N + SBA + OBE + SRV Faulted Faulted (O)

H + IBA + OBE + SRV Faulted Faulted~ (O) 8 + SBA/IBA + SSE + SRV Faulted Faulted (O)

~N + LOCA + SSE Faulted Fau1ted (O)

LOAD DEFINITION LEGEND Normal(N) - Normal and/or abnormal loads depending on acceptance cd.teri'a.

OBE Operational basis earthquake loads.

Safe Shutdown earthquake loads.

SRV Safety/relief valve discharge induced loads from two adjacent valves (one valve actuated when adjaceat valve is cycling).

SRV The loads induced by actuation of all safety/relief valves which activate within milliseconds of each other (e.g ,

turbine trip operational transient).

""e SRVADS The loads induced by the actuatioa of safety/relief valves associated with Automatic Depressurization System which actuate within milliseconds or each other during the postulated sm 0 r intermediate size pipe rupture.

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~ X g LOAD COMBlNATION TASLE (CONT'O)

The lass of coolant accidene assocddted. vith the pasaxLaced. pipo rupture of large pipes (e.g, main srezm, faedwater, re~cul'a.

eLan. piping) .

Pool, swell d=asa/fallout loads bemreen the main vene. discharge

~outlet piping. and components, and. the locaced suppression paar.

water uppers surface Poo1 saa11 ~acc leads an pdpdnt sad. coapanencs located stove tto suppressdon peal sacer upper cur=ace.

Os~~~g pressure induced loads on submerged piping and components during condensatian os~4'ians motion induced loads'rom chug~ 'uilding Building mat~'on induced loads f-am main vena zi clog VerticaJ. an* har""aural loads on main venc piping.

Annulus. press~~tioa loads The abnormal transients associated. Mth a Scull Break hccidenr.

The abnormal rransiencs assorted. vf.th an Xntermediate Braik Acc&enr.

CAde ~s 1 ~ 2, Rnd, g pgp~g systems Mhich func~n for safe shutdown.under the postulated events shall meet the.

~uir~ts of NRC's I

/Sg g Wdpr&AIJttaet Eg/g (tdsngdpsP a p 7~p / gy ~Q s;..l;.-.I c.f. l;I+ c,:/..:-," J s,a > lP 7J ip8o.

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• • The most. limit'ing case combinat.ion among LOCA through LOCA 1 7 I

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