ML17277A686

Forwards Table 3.9-2b, Reactor Internals & Associated Equipment, to Be Submitted in Amend 32 to Fsar.Ser Confirmatory Issues 9 & 10 Closed

ML17277A686
Person / Time
Site:	Columbia
Issue date:	07/26/1983
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
RTR-NUREG-0892, RTR-NUREG-892 GO2-83-661, NUDOCS 8308030141
Download: ML17277A686 (6)

Text

REGULATORY 1lRNATION OISTRISUT ION SYS+(BIOS)ACCESSION NBR:8308030141 DOOGDATE: 83/07/26 NOTARIZED:

NO DOCKET FACIL:50-3'07 HPPSS Nuclear Projects Unit 2~Washington Public Powe 05000397"AUTHNAME AUTHOR AFFILIATION SORENSENgGGC.

Hashington,Public Power Supply"System"RECIP BYNAME RECIPIENT AFF ILI ATION SCHh'ENCERg4

~Licensing Branch"2

SUBJECT:

For wards Table 3'2bg"Reactor Internals&'Associated Equipmenti" to be submitted in Amend 32 of FSAR.SER Confirmatory Issues 9&10 closed, DISTRIBUTION CODE: 8001S COPIES RECEIVED:LTR ENCLSIZE:.-TITLE: Licensing Submittal:

PSAR/FSAR Amdts&Related Correspondence NOTES: RECIPIENT IO CODE/NAME NRA/DL/ADL NRR L82 LA INTERNALS ELD/HDS2 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB il NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFEBOO NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DS I/CPB 10 NRR/DSI/ICSB 16 NRR/DS I/PSB 19 NRR/DS I/RS8 23 RGA5 EXTERNALS ACRS 41 DMB/DSS (AMDTS)LPDR 03 NSIC 05 COPIES LTTR ENCL 1 0 1 0 1 0 3 1 1?2 i i 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 6 6 1 1 1 1 1 1 RECIPIENT-ID CODE/NAME NRR LB2 BC AULUCKgR~Ol IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB?8 NRR/DE/MTEB 17 NRR/DF/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB "09 NRR/DS I/METB 12 N/RAB 22 G Fi Ov/MI8 BNL(AMDTS ONLY)FEMA REP DIN 3'9 NRC PDR 02 NTIS COPIES LTTR ENCL 1 0 1 1 1 1 i 1 0 1 1 2'2 1 1 1 1 1"0 1-1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 53 ENCL 06 Ell i~>>>>M<<M>>r>>3>>~Mr a i M<>>>~~I>r.v If>>>>IIV>>I>,ff M M Vnr<<'~M~<<I'rl ill\>>IV>I vr'v v>w M (MM M~>>QM>>>~w'>~w'll II vl vl q r)~~>>M g g-,')f MME l<<lt f'f>>I>>MF.<<)>><<M 0 g 0 I Mrl IM k-M" v.'I~>>M~'<~>>>~M>I" Or'>>ow w w~1 i>><<V II>>i I'w ft]M'l'i<XE>M'M'e'>><<l>l>M V<<Ef (1 J>M>>w<l Z4<<4 V~'>>g'>>,)I'M'M>>~'I w J><<fig J MMM i>J MI t g'1 w MM p4 VV>><<i'y EI>I>-lrr IM)EM>>MI>>II>>Cw>>>, IM J>>Mg>M<<,"C r','ME II>,<<II>>'MME>P->>V>

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~'IN'Washington Public Power Supply System P.O.Box 968 3000 George Washington Way Richland, Washington 99352 (509)372-5000 July 26, 1983, G02-83-661 Docket No.50-397 Director of Nuclear Reactor Regulation Attention:

Mr.A.Schwencer, Chief Licensing Branch No.2 Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555

Dear Mr.Schwencer:

Subject:

NUCLEAR PROJECT NO.2 SAFETY EVALUATION REPORT (NUREG-0892)

CONFIRMATORY ISSUES (9)FUEL ROD MECHANICAL FRACTURING, AND (10)FUEL ASSEMBLY STRUCTURAL DAMAGE FROM EXTERNAL SOURCES;CLOSURE OF The Licensing Review Group (LRG)generic response to the subject issues, NEDE-21175-3-P, was submitted to the NRC in July, 1982.Subsequent correspondence and meetings lead to a final meeting with the staff on June 10, 1983, at which the generic response was accepted.Additionally, it was agreed that plant specific closure would be contingent on a plant unique assessment of vertical displacement and combined loads.The attached table, to be submitted in FSAR Amendment No.32, provides these values.With this submittal NUREG-0892 confirmatory issues (9)and (10)are closed.Should you have any further questions, please contact Mr.P.L.Powell, WNP-2 L'icensing.

Very truly yours, c~=S4~~G.C.Sorensen, Manager (Acting}Nuclear Safety 5 Regulatory Programs PLP/tmh Enclosure cc: R Auluck-NRC WS Chin-BPA A Toth-NRC Site 830803;ii4i 830726 PDR ADOCK 05000397'E PDR

>~~~4'~<"J 14k~V l'I 4 I I L TABLE'.9-2b (Cont-nued)

REACTOR INTERNALS 5 ASSOCIATED coUIPViENT v HJEL ASSEHBLY (INCLUDTNG CHANNEL)Page 5 of 5 Acce tonne Criteria Loadin Prirnarv l.nad Yv e Calculated Peak Fvaluation Basis Acceleration Acceleration Acceleration Envelope Horizontal Direction:

Peak Pressure Safe Shutdown Earthquake Annulus Pressurization Horizontal Acceleration Profile 1.5 C 3.6 G Vertical 3irection:

Vertical Accelerations 5.4 G 12.0 G 1.Peak Pressure 2.Safe Shutdown Earthquake 3.'Safety Relief Valve 4.Chugging'0 NOTES: (1)Evaluation=Basis.

Accelerations.and.Evaluations,are contained in NEDE-21175-3-P.

The evaluation i asia acceleration-=envelope.,is-defined;by a coincident BG vertical accelcratinn with the 3.6C hnriznntaX-acceleration.

The 3;-60.horizontal.

value is-reduced-linearly to zero as the.corresponding vertical acceleration increased from S=-to=12 G's.(2)The calcul'ated..maxixaum fuel-.'assembly=gap-opening-for-the inst--limit in@-load combinatioh.is 0.25 i~eh.This is.less-than-the gap=.(0.5~nch) required~o start the disengagement of the'los~er-tie plate from the-fuel-support=

casting.(3)The fatigue analysis indicates that the fuel asseably has adequate fatigue capability-to-withstand the Joadings resulting from multiple SRV actuations and the OHF+SRV event.

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