ML17276B002

Forwards Resolution Re Fuel Design & Plant Operation,Per 820106 Telcon.Response Answers Core Performance Branch Concerns Re Channel Box Deflection,Waterside Corrosion, Seismic LOCA Leads Analysis & on-line Fuel Failure Detection

ML17276B002
Person / Time
Site:	Columbia
Issue date:	01/19/1982
From:	Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
References
GO2-82-84, NUDOCS 8201290423
Download: ML17276B002 (18)

Text

REGULATORY IFORNA'TION DI'STRISUTION SYN ORIDS)

AOC'ESS ION NBR: 820 1'290423, DOC ~ DATE: 82/01/19 NOTA R I'ZED: NO, DOCKET FACIL,'50'397 KPPSS Nuclear 'ProJeots Unit "2i washington IPubl ic Powe 05000397

'AUTH, NAME AUTHOR AFFILIATION

, BOUCHEY~G ~ DE '4'ashington,Public ',Power Supply 'System

>REC IP ~ NAME RECIPIENT A F F IL'IATION

'SCHNENCEREA ~ Licensing Branch '2

SUBJECT:

Forwards nesolution re fuel Pdesipn '8 plant operationEper 820106telcon.Response answers Core Performance 'Branch concerns, ne'channel box Ideflection~watenside corrosionE Yseismic LOCA leads analysis 8 online fuel ",failure Tdetection, DISTRISUTION CODE: SOOIS iCDPIES iRBCEIVEO:UTR, ENCL.SIZE:. CD TITLE: PSAR/PSAR AMOTS and ~'Re 1.ated ~Cor respondence NOTES:2 copies =all matl!PMN 05000397 RECIPIENT ~COPIES REC IP IENT ICOPIES

-ID CODE/NAME L'TTR ENCL ID CODE/NAME LTTR ENCL ACTION: A/D LICENSNG 1 "0 LI~C BR 0P BC 1 0

.LIC BR P2 LA 1 0 AULUGKg R ~ 01 1 1 INTERNALs ELD r0 IE .06 "3 "3 IE/DEP/EPDB 35 1 1 IE/DEP/EPLB "36 J3 MPA 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EQB 13 13 f3 NRR/DE/GB 28 '2 2 NRR/DE/HGEB '30 2 '2 NRR/DE/MEB 18 1 1 NRR/OE/MTEB 17 1 1 NRR/DE/QAB 21 1 1 NRR/DE/SAB '24 1 1 NRR/OE/SEB 25 1 1 NRR/DHFS/HREB40 1 NRR/OHFS/L'QB >32 1 1 NRR/DHFS/OLB >34 1 NRR/DHFS/RTRB20 1 1 NRR/OS I/AEB 26 1 1 NRR/OS I/A8 8 '27 ,1 1 NRR/DSI/CPB 10 1 .1 NRR/DS I/CSB 09 .1 ~ 1 NRR/DSI/ETSB 12 1 1 NRR/OS I/IiCSB 16 1 1 NRR/DSI/PSB 19 1 1 NRR/DSI/RAB "22 1 1 NRR DS I/RS8 23 1 NRR/DST/LGB '33 1 L 04 1 1 EXTERNAL: ACRS 41 16 16 BNL(AMDTS ONLY) 1 1 FEMA REP OIV '39 1 LPOR ~ 03 1 1 NRC,POR 02 1 1 NSIC 05 1 1 NT I' 1 1

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eaosa904a3 eao>~9 PDR ADQCK 05000397 A PDR Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 January 19, 1982 G02-82-84 SS-L-02-PLP-82-003 Docket No. 50-397 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission lV pa Washington, D. C. 20555

Subject:

NUCLEAR PROJECT NO. 2 CORE PERFORMANCE BRANCH CONCERNS, RELATED DURING PHONE CALL JANUARY 6, 1982 The subject phone conversation related seven (7) NRC concerns relating to fuel design and plant operation. Attachment 1 lists those participating in the phone conversation and Attachment 2 lists the concerns and the WNP-2 resolution.

Very truly yours, G. D. Bouchey, uty Director Safety & Security PLP/jca Attachments cc: R Auluck - NRC WS Chin - BPA R Feil - NRC Site

4 PARTICIPANTS IN WNP-2/NRC DISCUSSION RE: FUEL DESIGN AND RELATED OPERATIONS - JANUARY 6, 1982 PL Powell Supply System CH Powers Supply System BM Moore Supply System RM Nelson Supply System A Wood Supply System R Auluck NRC M Toker NRC Attachment 1

NRC CONCERNS-WNP-2 RESOLUTION Channel Box Deflections - This issue has been addressed in Appendix I to t e as icensing Review Group issue CPB-7 (attached).

Waterside Corrosion - This issue has .been addressed in Appendix I to the i - as icensing Review Group issue CPB-2 (attached).

Seismic LOCA Loads Analysis - This analysis is currently being performed y enera ectric on e alf of the Licensing Review Group (LRG). WNP-2 is a participant in, and acts as chairman, of the LRG and will use the GE analysis to address thi s i ssue.- Present schedule will meet a submittal by June 30, 1982.

Cladding Ballooning, Rupture and Flow Blockage - Presently, NRC staff is reviewing e enera ec ric generic ocument NEDO 2(566 that addresses this issue. In the interim, the PCT margin below 2200 F is being requested by the staff to be allocated specific~lly to this concern. WNP-2 committs to relinguishing the PCT Margin (2200 F-1960 F) unti 1 the NRC review of NEDO 20566 is completed. At that time WNP-2 will reevaluate the PCT margin allocation based on the results of that review.

'n Lihe'uel Failure Detection - Fuel failure detection at WNP-2 is accomp is e using e ain team Line Radiation Monitoring System and the Offgas Monitoring System (FSAR descriptions in Section 11.5). Possible gross fuel failure is alerted by a reactor scram and main steam line valve closure initiated at three (3) times full power background level by the main steam line radiation monitors (see Technical Specification Section 2.2, Limiting Safety System Instrumentation Setpoints). Gradual fission particle release increase is addressed by Technical Specification 3/4.4.5 (specific activity).

It. is felt that the combination of both systems and implementation of the applicable technical specifications adequately addresses on line fuel failure detection for WNP-2. I Post Irradiation Examination - WNP-2 will establish a routine fuel inspec-ion program to provi e in ormation on irradi ated and discharged fuel following each refueling. The program will involve visual examination of selected assemblies. Typically visual examination will be made by five to ten per cent of the discharged fuel, concentrating on the lead fuel bundles. Yisual examination should include but not be limited to: crud buildup, rod bowing, missing components, etc. Additional fuel inspection should be performed depending on the results of operational monitoring including coolant activi ty, and the visual fuel inspection.

Attachment 2 Page 1 of 2

7. Additional Information in the Initial Core Fuel Design - The FSAR sec-tion escrow sng t e snsts a - ue eslgn re erences a GE 'document that is presently out of date. WNP-2 and the NRC recognize that the appropriate GE document will not be available from GE unti 1 mid-January, 1982. In the interim the following information is forwarded for NRC review:

The WNP-2 initial core fuel bundles contains 62 fuel rods and 2 water rods. The fuel rods are helium backfi lied to 3 ATM. This design i s designated by General Electric as P8X8R meaning the fuel roads are pre-pressurized, the bundle has a 8 by 8 rod configuration (total of 64 rods) and the bundle is what is called a retrofit design.

For the WNP-2 core, Table 1 gives general fuel rod parameters that describe the WNP-2 fuel. The three bundle types shown in Figures 1, 2 and 3 are loaded in a C-Lattice configuration in the quarter core pattern shown in Figure 4.

For a more detailed description of P8X8R fuel bundles and type C-Lattices, see Sections 1 and 2 of "Generic Reload Fuel Application,

General Electric Co., December, 1981 (NED0-24011-A-2).

TABLE 1 WNP-2 FUEL ROD PARAMETERS Parameter Initial Core Rod Array 8x8 Number of Fuel Rods/Bundle 62 ~

Fuel Rod Material U02 Pellet Diameter (in.) 0.410 Pellet Length (in.) 0.410 Pellet Immersion Density (5) (Theoretical) 96 Clad Material Zl -2 Clad I.D. (in.) 0.419 Clad O.D. (in.) 0.483 Clad Thickness (nominal) (in.) 0.032

'Pellet Clad Gap (cold, nominal) (in.) 0.009 Active Fuel Length (in.) 150.0 Plenum Length (in.) 9.48 Fuel Rod Pitch (in.) 0.640 Number of Water Rods/Assembly 2 Water Rod 0. D. (in.) 0.591 Number of Spacergrids/Assembly Grid Material Zr-4 with Icon el springs End Fittings Material (rods) Zircaloy Fill Gas Pressure (He) (atm) 3.0 Total Core Weight (MTU) 139.3 Core Average Enrichment w/o U 1. 87

6 5 4 3 4 5 6 5 4 2 1 1 3 5 2 1 GD1 WATER

3. 1 I GD1 ROD 1 3 3

WATER ROD GD2 1,2 3 4 GD1 2 5' 1 2 2 4 '5 r

4 5 6 ROD TYPE NO. ENRICHMENT 1 19 3.00 W/0 2 7 2.60 W/0 3 10 2.20 W/0 4 10 2.00 W/0

.5 8 1.70'/0 6 4 1.30 W/0 GD1 3 1.70 W/0 GD2 1 1.70 W/0 5 3.00 W/0 AVERAGE BUNDLE ENRICHMENT ~ 2.19 W/0 EXCLUDING NATURAL URANIUM ENDS ~ 2.33W/0 ~

FIGURE I WNP-2 INITIAL CORE FUEL ASSEMBLY ENRICHMENT DISTRIBUTION MAP - HIGH ENRICHMENT BUNDLE

2 2 2 3 4 3 1' 2 3.'

1 GD1 1 2 WATER 1 GD1 1 1 ROD WATER RQD GD1 1 I 2 2 GD1 1 1 2 2 1 1 2 2 3 2

ROD TYPE NO. ENRICHMENT 1 . 24 2.20 W/0 2 22 1.70 W/0 3 8 180 W/0 4 4 120 W/0 GD1'J 4 1.70 W/0 & 220 W/0 AVERAGE BUNDLE ENRICHMENT= 1;76 W/0 EXCLUDING NATURALURANIUM ENDS = 1.83 W/0 FIGURE 2 WNP-2 INITIAL CORE FUEL ASSEMBLY ENRICHMENT DISTRIBUTI'ON MAP - LOW ENRICHMENT BUNDLE.

\

1 1 1 1 1 1 1 1 1 1 1 1 WATER 1 1 ROD WATER 1 1 "ROD 1 1 1 1 1 1 1 1

1' ROD TYPE NO. ENR ICHMENT 62 '0.71'/0 AVERAGE BUNDLE ENRICHMENT 0.71 W/0 236U FIGURE 3 M/NP-2 INITIAL CQRE FUEL ASSEMBLY ENRICHMENT DISTRIBUTION MAP - NATURAL URANIUM BUNDLE,

1 1 1 1 1 ~

l. 1 1 1 1 2 2 2 3 3,

FUEL TYPE TOTAL NO. ENRICHMENT 240 1.76 W/0 432 2.19 W/0 92 0.'Pill W/0 AVERAGE INITIALCORE ENRICHMENT ~ 1.87 W/O 23SU FIGURE 4 WNP-2 INITIAL CORE LOADING,PATTERN - QUARTER

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CORE SYMMETRIU

WNP-2 ISSUE:, CPB-2 WATERSIDE CORROSION QUESTION:

The appLicant has not addressed the potentiaL for fuel corrosion failure similar to that which occurred at the Vermont Yankee plant.

RESPONSE

As indicated in the General Electric presentation given to the NRC in December 1979'he failures appeared. to be associated with a metallic incursion in the feedwater.

This event has occur ed only once in the BWR operating history and is unlikely to reoccur.

Subsequent to this events General Electric provided an operation recommendation for corrosion product control which should preclude this type of event at WNP-2. The Supply System plans to employ those General ELectric operating recommendations which have been proven to be effective at severaL operating BWR plants for maintaining water quality parameters at or below GE's water quality speci f ication Limits.

MNP-2 REFERENCES-

1. Letter. from R. E. Engel (GE) to N. Tokar.(NRC)i Product Control"r dated October 3r 1980.

NFN"172-80'Corrosion

MNP-2 ISSUE: CPB-7'HANNEL BOX DEFLECTION QUESTION:

The applicant has not referenced General. Electric Licensing Topical Report NEDE-21354-P which describes the fuel c'hannel design. Of specific concern is the commitment to control rod driveline friction testing recommended in Section 4.4.2 of NEDE-21354-P.

RESPONSE

NEDE-21354-P is the Licensing Topical Report applicable to the WNP-2 design. Included in Section 4.4.2 of this report is a recommendation to conduct periodic control rod drive-line friction tests. Operating experience with this channel design has demonstrated that excessive deflections and subsequent channel wear are unl.ikely ~ Consequent lyr the General Electric recommended periodic contr ol rod driveline friction test is no longer necessary. The. technical specification requirements for periodic scram time testing and rod notch testing would provide an indication of a pend-

'ing driveline friction concern. Should either of these tests suggest a driveline friction problems the pressure test described in NEDE-21534-P (4.4.2) would then be i so late the cause.

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