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 BYNAME SORENSENgGGC. Hashington,Public Power Supply "System "RECIP RECIPIENT AFF ILIATION 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 ENCL SIZE:.-

TITLE: Licensing Submittal: PSAR/FSAR Amdts & Related Correspondence NOTES:

RECIPIENT COPIES RECIPIENT COPIES IO CODE/NAME LTTR ENCL -ID CODE/NAME LTTR ENCL NRA/DL/ADL 1 0 NRR LB2 BC 1 0 NRR L82 LA 1 0 AULUCKgR ~ Ol 1 1 INTERNALS ELD/HDS2 1 0 IE FILE 1 IE/DEPER/EPB 36 3 IE/DEPER/IRB 35 1 i IE/DEQA/QAB 21 1 NRR/DE/AEAB 1 0 NRR/DE/CEB NRR/DE/EQB il 13 1

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'2 NRR/DE/MEB 18 i NRR/DE/MTEB 17 1 NRR/DE/SAB 24 i NRR/DF/SGEB 25 1 1 NRR/DHFS/HFEBOO 1 1 NRR/DHFS/LQB 32 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 "0 NRR/DS I/AEB 26 1 1 NRR/DS I/ASB 1 -1 NRR/DS I/CPB 10 1 1 NRR/DSI/CSB "09 1 1 NRR/DSI/ICSB 16 1 1 NRR/DS I/METB 12 1 1 NRR/DS I/PSB 19 1 1 N /RAB 22 1 NRR/DS I/RS8 23 1 G Fi Ov 1 RGA5 3 3 /MI8 1 0 EXTERNALS ACRS 41 6 6 BNL(AMDTS ONLY) 1 1 DMB/DSS (AMDTS) 1 1 FEMA REP DIN 3'9 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 53 ENCL 06

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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 the generic response was accepted. Additionally, it was agreed that whichplant 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

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TABLE'.9-2b (Cont-nued)

REACTOR INTERNALS 5 ASSOCIATED coUIPViENT v HJEL ASSEHBLY (INCLUDTNG CHANNEL) of Page 5 5 Calculated Peak Fvaluation Basis Acce tonne Criteria Loadin Prirnarv l.nad Yv e Acceleration Acceleration Acceleration Envelope Horizontal Direction: Horizontal Acceleration 1.5 C 3.6 G Profile Peak Pressure Safe Shutdown Earthquake Annulus Pressurization 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:

i asia (1) Evaluation=Basis. Accelerations .and. Evaluations,are contained in NEDE-21175-3-P. The evaluation 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- -limitin@ 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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