ML20108F232

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Nonproprietary Version of Amend 1 to Westinghouse Advanced PWR RESAR-SP/90,Preliminary Design Approval,Module 5, Reactor Sys
ML20108F232
Person / Time
Site: 05000601
Issue date: 11/30/1984
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19274C482 List:
References
NUDOCS 8412190290
Download: ML20108F232 (24)
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Text

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l AMENDMENT 1 TO RESAR-SP/90 PDA MODULE 5. " REACTOR SYSTEM" O

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MAPWR-RS AMENDMENT 1 2185e:1d NOVEMBER, 1984

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AMENDMENT 1 TO RESAR-SP/90 PDA MODULE 5. ' REACTOR SYSTEM' INSTRUCTION SHEET

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Insert all pages behind QUESTIONS / ANSWERS tab.

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MAPWR-RS I AMENDMENT 1 2185e:1d NOVEMBER, 1984

490.1 The MAPWR fuel design has a new feature for those rods containing 4.2 integral fuel burnable absorber. Will the absorbing material melt during any operational transients before the fuel melting limit is

. exceeded?

RESPONSE

The melting temperature of [ ],

the absorbing material, exceeds +a,c that of UO2 , namely [ ] versus a maximum of 2800*C for +a,b,c UO .

2 In addition the absorbing material is a [

] so that its temperature will always +a,c be below the temperature of the coolest portion of the fuel. Hence, there are no transients, operational or accidental, where the temperature of the absorbing material approaches the melting point.

499.2 What is the limit and method used for creep collapse analysis for 4.2 MAPWR fuel rods? Since this is a new design, please provide pertinent information on the fuel densification limit and the initial fuel pressure of the fuel rods to assure no creep collapse occurs.

RESPONSE

Even though the MAPWR is a new design, the current fuel rod analysis methodology described in WCAPs 8218, 8720 and 8377 continues to be applicable. With the exception of thicker clad, the MAPWR fuel rod is similar to that of 17x17 0FA or Vantage 5. Therefore, the densification and collapse modeling for MAPWR fuel remains the same as I

that given in these WCAPs. The clad flattening- time for MAPWR is

>45,000 EFPH for initial backfill pressure of ( ) psia or greater.

+a,c 490.3 Provide analyses of combined seismic-and-LOCA loads on MAPWR fuel 4.2 assemblies to demonstrate the conformance to Appendix A of SRP 4.2.

RESPONSE

The MAPWR fuel assembly seismic capability has been analyzed for proposed high seismic sites covering a wide spectrum of foundation O

MAPWR-RS 490-1 AMENDMENT 1 2185e:ld NOVEMBER, 1984

characteristics in Japan. This seismic analysis was based on the S2 earthquake which is equivalent to the Safe-Shutdown-Earthquake. The I seismic response spectra used are conservative compared to site 1 seismic characteristics for all U.S. nuclear plants. 1 The results of the seismic analysis show that the MAPWR fuel assembly el '

structural integrity is maintained. SincI the fuel assembly I components are deformed elastica 11y, a coolable geometry and control rod insertion capability are assured.

h As for time fuel assembly response to LOCA loads, asymmetric blowdown loads resulting from large double-ended breaks in the main loop piping are not considered as part of the design bases for MAPWR. Analyses of the potential for pipe fracture from ductile rupture and unstable flaw extension, materials tests to define tensile and toughness properties, and predictions of leak rates from postulated flaws will be prepared and subtitled as part of the RESAR-SP/90 FDA document. These analyses will be in accordance with the technical bases presented in the USNRC General Letter 84-04, " Safety Evaluation M Topical Reports Dealing ,

with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops," I dated Feb. 1, 1984. As a result, the induced core plate motions will l be small and the cffect on the overall fuel assembly will be ,

negligible. For a discussion of the pipe breaks considered as part of I the MAPWR design bases, see Section 3.6 of RESAR-SP/90 PDA Module 7,

" Structural / Equipment Design".

490.4 Describe plans for on-line fuel system monitoring and postirradiation 4.2 surveillance. hlo

RESPONSE

Methods and instrumentation for on-line fuel monitoring (e.g., coolant activity monitoring, etc.) are discussed in RESAR-SP/90 PDA Module 13,

" Auxiliary Systems".

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MAPWR-RS 490-2 AMENDMENT 1 2185e:1d NOVEMBER, 1984

A routine fuel inspection program will be implemented on the irradiated and discharged initial liAPWR fuel during plant refueling outages. The program will involve

' visual examinations on a representative sample of assemblies from the first MAPWR fueled core at each refueling until this fuel is discharged.

Visual observations will include, but not be lhtted to, crud buildup, rod bowingf grid strap conditions and inspections for potential missing components.

Additional fuel inspections would be performed depending on the results of operational monitoring, including coolant activity, and the visual fuel inspections.

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O WAPWR-Rs 2185e:1d 490-3 AMENDMENT 1 NOVEMBER, 1984

491.1 Past agreements with Westinghouse, going back as far as Robinson and 4.3 Indian Point 2 reviews, relating to X-Y plane xenon stability, have been that specific tests wouf ; be performed to demonstrate stability for reactor classes with significant, relevant new characteristics O ca < re 5::  :

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i TABLE 1, (Cont.)

TEST atsuLTS -12.8 Foor .40s IseCH OD NDNWNIFOAN TEST SECTION

,, TYPICAL CELL eeee e e e eINLET e e e e e eINLET e e e e eee e NASS INLET e e e e e eLOCALe e e e e LOCAL e e e HEAT ee eFLUM e e e e e e e e e e e e e e e e e e e e ee e e e e e e e e e e e e e e sun ,etssuet TEleP vfLOCITY ELEVATION FRON 38eLET E3. (PSIA) ( F) (MSOES Lase GUALITY (M10ES STU/HR-50FT) (teEAS/ (3NCHES) seesesseeeeeeeeeeeeeeeeeeeeeeeee***e***o/De-SOFT) (%) setAS. PREO PRED) PRED. seEAS.

  • ee*o***esee*ese*o**ece*****eesee**. ***ppeegooe**eeeeesseeeeeeeeeeeeeeeeeee**eee**

W2540

+\Deci " "

+(b,C)

W2541 .9628 W2542 9885 w2543 .9942 U2544 .9970 C2545 1.0387 E2546 1.0330 c2547 9807 C2548 1.0139 C2549 9183 C2550 9.O179 W2559 .9629 t2552 1.0205 U2553 1.0388 C2554 1.0053 E2555 .3284 C2558 .9675 C2557 9.0167 C2558 .9906 t2559 .3700 C2560 1.0127 E2569 1.0293 C2542 .9943 C2543 1.1406 U2564 .9646 c2565 .9450 U2564 945t C2567 1.0073 C2564 ' .9958 W2569 t.0304

= 1.0449 eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee eeee i

L =12.8 FT A00 0.0. = .405 IN '

.4518 IN ID 4

DE 6 .*.05 , - I.S.I.N.E.06 W.40,s.t.Gst.lO.S 30 2005 86% E 17.5

.E. .IN.SP..AC.

. INS 2185e h ) NT 1 NOVEM8ER, 1984

TABLE 1 (cont.) Test assuLTs -t2.s poof .4os IsacM on NaNumsFonu TesY sacison TVPICAL CELL

.. ee.....ee...ee..eeee.......eeeeeeeeee. ResLET IteLET eeeeeeeeeeeee. eeeeeeeeeeeeeeeee..e eeeee.e..ee...e.........e. e .eeeeeeee...e.

IteLE7 seASS LOCAL local HEAT Flux ause petssues ressp wtLoctiv ELEVATION FROII INLET 8 (PSIA) ( F) (x10ES STM/tet-SOFT) (IEEAS/ (INCHES) e e eee.00. eeeeeeeeeeeeeeeeeeeeeeee(MSOES Last/HR-SOFT) teEAS. euALITY PREo. PREo PREo IeE AS.

,,, eeeeeeeeeoooooooeeeeeee(5)eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee)eeeeeeeee. eeeeeeeeeeeeeeeeeeeeeeeepe C2170 +(bec) - .

+Lbec)

C2E71 .9920 C2572 .8845 C2173 .gogg C2174 .333g C2 m .373g C2378 1.0034 C2177 .3419 C2 m g.1063 C2579 g,gggy C2580 ,3g43 i C2548 .9009

C2542 1.0363 l 62583 9.0829 l C2584 1.1354 C25eS ,goyg C2584 g.0565
C2547 ,3g33 W2588 334g C2549 9323

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! C2XC2 .3e75

C25;3 1.0002 C2384 1.0416 i C2595 .SSS1 l U2".L7 8445 ,

5 .3013 C2600

  • 1.0014 C2608 1.05tS C2603 1.0272 1.0343 eoeeeee.eeeeeeeeeeeeeee.eeeeeeeeeeeeee........ eeeeeeeeeeeeeeeeeee,e . eeeeeeeeeeeeeee....e e ee. ee...e eeee. eeeeeee L =12.8 FT Rgo 0.o. * .408 IN i os = .4sie in maxima vant enros is noos scos 17.s am sPAestes inesta mo o / o uTE n no s p o ws e = 1. te 2s 20 noos oss

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2185e:1d 624 MNMENT 1

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TABLE 3 1518-2 CWColl8 ELATION - STATISTICAL 8ES42.TS Sod 0.0. L 8sp h

(tack) Heat Flux

  • fftd (inch) Profile 5 rd Confleuration j Q) Deviation.S 0.360 14 10 Costne TYP-sus
0.360 14 10 51 0 9861 0.0758 Cosine TYP-5m5 31 1.0097 0.406 12.8 17.5 0.0680 Costne TYP-6n6 98 i 0.406 12.8 0.9870 0.0704 17.5 CesIne Tie 66x6 95 - 0.9899 t

0.360 14 to 0.0723 Costne TYP-5x5 i 0.360 63 0.9961 0.0946 14 20 Cosine

! Tiel-sus 38 0.9832 0.374 8 22 0.0599 Uniform TYP-5x5 67 0.374 14 1.0316 0.0897 22 Uniforu l

TYP-5x5 71 1.0095 0.374 14 22 0.0664 Costne TVP-sus

) 0.3 74 14 74 0.9893 0.0822 22 Costne i

-Tiel-Su5 70 0.9884 0.374 8 26 0.0775

) Uniform TYP-5x5 78 0.374 8 1.0198 0.0810 i 26 Uniform Tiel-sus 68 1.0398 0.374 14 '26 0.1062 i

untform TYP-sus 73 0.9914 0.0823 All Data ~87F 1.0014 0.0825 1' ,

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4 WWWR-RS i 2185e:14 492-12 i mma,8MENTjss4 AMEN

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FIGURE 1: @PWRTYPICALCELLBUNDLECROSSSECTION AMENDMENT 1

$PWR-RS NOVEMBER, 1984

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FIGURE 2: gPWRTHIMBLECELLBUNDLECROSSSECTION O i

$PWR-RS AMENDMENT 1 NOVEMBER, 1984 '

1

, y.,ww,w->-~-- amec.w- ww-,v,,,-, ,_ - _ _ _ _ _ , - , - , --

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FIGURE 3: AXIAL LOCATION OF GRIDS AND THERMCOUPLES i IN EAPWR DNB TEST BUNDLES AMENDMENT 1 EAPWR-RS NOVEMBER, 1984 i

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2g Z, Axial Distance From Beginning of Heated Length (Inches)

SEm m* =E Rm FIGURE 4 APWR DNB HEATER R00 AXIAL HEAT FLUX DISTRIBUTION

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O 492.2 Provide the documentation required by NUREG-0737 Item II.F.2. The j 4.4 response should be given item-by-item showing how your design complies with each requirement. Clearly state where your design deviates from

' he t requirements and why such deviation is acceptable.

RESPONSE

Inadequate core cooling instrumentation is considered to be part of the reactor coolant system. Therefore, see RESAR-SP/90 PDA Module 4,

" Reactor Coolant System"; Subsection 4.4.6.5 for a description of this instrumentation.

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! MAPWR-RS 492-13 AMENDMENT 1 2185e:1d l NOVEMBER, 1984

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