ML17055B614

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Summary of 860424 Meeting W/Westinghouse & Util Re Core Reloads for Bwrs.Meeting Followup to 860219 Meeting on Same Topic.Handouts & List of Attendees Encl
ML17055B614
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/02/1986
From: Haughey M
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-66539, NUDOCS 8605090336
Download: ML17055B614 (26)


Text

Docket No. 50-410 May 2, 1986 VENDOR:

Westinghouse Electric Corporation

SUBJECT:

MEETING

SUMMARY

FOR APRIL 24,

1986, MEETING WITH WESTINGHOUSE ELECTRIC CORPORATION TO DISCUSS WESTINGHOUSE'ORE RELOADS IN BOILING WATER REACTORS SPECIFICALLY, NINE MILE POINT 2 On April 24, 1986, the NRC staff met with representatives of Westinghouse Electric Corporation (W) to discuss W core reloads for Boiling Water Reactors (BWRs).

Representatives were also present from Niagara Mohawk Power Corporation (NMPC).

This meeting was a follow-up to the February 19, 1986, meeting on the same subject.

The main topic of the meeting was the schedule for W submittal and NRC review of W topical reports for core reloads in BWRs.

EncTosure 1 contains a handout from W identifying a schedule for submittal and review of each of the topical reports.

NMPC and W are planning on limiting the number and locations of W fuel bundles in the Spring 1988 reload at Nine Mile Point 2 (NMP-2) so that NKC review and approvals of the proposed topical reports will not be required for that reload.

W did identify ~

a need for review and approval of these reports by Spring 1989.

The list of NRC review dates in Enclosure 1 however identifies only the dates when W would like to see each of the topical reports reviewed not when the review is needed.

As some of these reports may be interdependent and a "need"

,date may be before Spring 1989 W was requested to identify the "need" date for each topical report.

t W stated that the report on GOBLIN is being withdrawn and the report on COMPUS was submitted for information only.

NRC confirmed that RAMONA would need to be qualified if it is to be used for a safety evaluation.

W identified the priority for review of the topical reports should be 1)

LOCA,
2) Transient, and 3) Nuclear.

NRC stated new topical reports are to be sent to Jesse Funches.

Enclosure 2 contains a list of meeting attendees.

3b 860502 3b Bb0509033 PDR ADOCH

Enclosures:

As stated cc:

See next page WD-3:DBL MHaughey/hmc 4/~86 Mary F. Haughey, Project Manager BWR Project Directorate No.

3 Division of BWR Licensing

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i Mr. B. G. Hooten Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit 2 CC:

Mr. Troy B. Conner, Jr.,

Esq.

Conner 5 Wetterhahn Suite 1050 1747 Pennsylvania

Avenue, N.W.

Washington, D.C.

20006 Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus

Syracuse, New York 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.

Box 99

Lycoming, New York 13093 Mr. John W. Keib, Esq.

Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 Mr. James Linville U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Norman Rademacher, Licensing Niagara Mohawk Power Corporation 300 Erie Boulevard West
Syracuse, New York 13202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Paul D, Eddy New York State Public Service Commission Nine Mile Point Nuclear Station-Unit II Post Office Box 63
Lycoming, New York 13093 Don Hill Niagara Mohawk Power Corporation Suite 550 4520 East West HighWay
Bethesda, Maryland 20814

May 2, 1986 MEETING

SUMMARY

DISTRIBUTION cket No(s):

50-410 NRC PDR Local PDR BWD ¹3 r/f J. Partlow E. Adensam

Attorney, OELD E. Jordan B. Grimes ACRS (10)

Project Manager M.

Ha he E. Hylton NRC PARTICIPANTS M. Haughey T. Collins W. Hodges L. Phillips bcc:

Applicant

& Service List

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SCHEDULE I

NINE MILE POINT UNIT 2

- CYCLE 3. START DATE FALL 1 9 II CYCLE 3 SER SUBMITTAL TO NRC

- EISENHUT LETTER (8-20-80)

TECH SPEC CHANGES

- SIGNIFICANT HAZARDS CONSIDERATIONS RES ART MONTHS

III, CYCLE 3 DESIGN MIXED CORE/TRANSITION CYCLE

- FIRST W BWR RELOAD ANALYSIS WITH APPROVED METHODOLOGY SER PREPARATION

- NIAGARA MOHAWK REVIEW R

1 MONT S IV, NRC TARGET FOR FINAL APPROVAL SPRING 19

SUBMITTAL QUAD+ LICENSING SUBMiITTALS STATUS SER ITEMi

'6/82 6/82 SUBMITTED RECEIVED NUCLEAR DESIGN CODES DESCRIPTION TOPICAL:

PHOENI X/POLCA SUBMITTED RECEIVED THERMAL-HYDRAULICS CODE:

CONDOR 1/83 3/83 10/85 SUBMITTED SUBMITTED N/A N/A INFORMATION N/A FUEL ROD MODEL:

PAD ECCS EVALUATION MODEL:

GOBLIN SERIES OF CODES COMPUS ON-LINE MONITORING SOFTWARE PROGRAM 9/85 1/86 6/86 8/86 9/86 9/86 1/87 6/87 6/87 6/87 6/87 SUBMITTED SUBMITTED NUCLEAR DESIGN CODES QUALIFICATION 8X8 CPR CORRELATION CHANNEL HYDRODYNAMICS STABILITY CODE AND METHODOLOGY ';

MAZDA TRANSIENT ANALYSIS METHODS; BISON QUAD+ CPR CORRELATION LOCA EVALUATION NETHOD-(APP, K)

RAMONA CODE QUALIFICATION LOCA EVALUATION MODEL" SENSITIVITY STUDIES BMR FUEL ROD ANALYSIS METHODS LOCA APP.

K.

CALCULATION" BASIC SAFETY REPORT

, " GOBLIN, CHACHA, DRAGON SERIEs Ot=

CODEs

NRC REVIEW TIMES REPORT SUBJECT SUBMITTAL SER MONTHS WCAP-9500 OPTIMIZED FUEL WCAP-10444 VANTAGE 5 FUEL 7-79 12-83 8-81 7-85 25 19 WCAP-8846 h'CAP-8720 HYBRID 84C RCCA PAD 3.3 9-76 11-76 9-77 2-79

. 12 27 NS-EPR-2649 RELAXATION OF CAOC 8-82 11-82 h'CAP-8691 WCAP-9485 REV.

1 FUEL ROD BOW SUPP.

1 PALADON 3.0 7-79 9-81 12-82 3-83

. 18 WCAP-10297 DROPPED ROD 1-82

'-83 14 WCAP-9863 ROD SWAP 7-82 5-83 10 WCAP-10021 REV.

1 WA Burnable Absorber 10-82 8-83 10 WCAP-8720 ADD.

1 PAD 3.3 (Transients) 9-79 6-82 33 MILLSTONE 2 BASIC SAFETY REPORT

- PHYSICS

- TRANSIENT

- FUEL AND T/H 3-80 3-80 3-80 3-80 2-82 6-81 1-82 2-82 23 15 22 23

NRC REVIEW TIMES (cont')

REPORT SUBJECT SUBMITTAL SER MONTHS WCAP-8762 WCAP-8218 WCAP-8377 WRB-1 15X15/14X14 OFA FUEL DENSIFICATION REVISED CLAD FLATTENING WCAP-10106 BWR NUCLEAR CODES WCAP-10125 HIGH BURNUP NEDE-22148 GE HIGH BURNUP WCAP-10444 ADD.

1 IFBA OTHER ARRAYS WCAP-10107 BWR T/H CODE BASH BART 11-83 10-73 7-74 6-82 7-82 6-82 12-85 6-82 6-84*

1-80 6-84 7

3-74 5

2-75 7

9-85 39 10-85 39 8-85 38 3-86 3

10-85 40 6-86 (EST.)

24 12-83 NOTRUMP UHI MODEL N-1 LOOP CE MODEL LOFTRAN 12-82 3-75 2-77 8-80 7 81**

5-85 3-78 2-79 10-82 6-83 29 36 24 26 23

  • Submitted 7-83
    • Submitted 10-72

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WORK SHEET wKsTIHGHOvsE FORII 8295 E INDIVIDUAL TOPICAL REVIEWS ITT L DATE REVIEW TINE NRC

)ER SMOOTHED SER DATES (S)

NTHS ~

TO 3-89 S

NUCLEAR QUALIFICATIO BX8 CPR CORRELATION 6-86 6-86 CHANNEL STABILITY 6-86 BISON QUALIFICATION 8-86 QUAD+ CORRELATION 9-86 LOCA METHODOLOGY 9-86 RANONA QUALIFICATION 1-87 LOCA SENSITIVITY 6-87 BWR PAD 6-87 LOCA CALCULATION 6-87 BSR 6-87

WORK SHEET WESTINGHOUSE FORII 8295 E INDIVIDUAL TOPICAL REVIEWS ITT DATE REVIEW TIME DATE SMOOTHED SER DATES (S)

NTHS TO 3-89 S

NUCLEAR QUALIFICATIO 6-86 BX8 CPR CORRELATION CHANNEL STABILITY BISON QUALIFICATION QUAD+ CORRELATION 6-86 6-86 8-86 9-86 LOCA METHODOLOGY RAMONA QUALIFICATION 9-86 1-87 LOCA SENSITIVITY 6-87 BWR PAD 6-87 LOCA CALCULATION 6-87 BSR 6-87

II

'C

WORK SHEET efsIINGHOUsE F0RM 8295 E INDIVIDUAL TOPICAL REVIEWS tm DAT ltlITK REViEII TIME NRC

)ER SMOOTHED SER DATES (S)

NTHS TO 3-89 S

NUCLEAR EQUALIFICATIO 6-86 I2-S1 8X8 CPR CORRELATION CHANNEL STABILITY 6-86 6-86 7-SS 7-88

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BISON ljUALIFICATION gUAD+ CORRELATION 8-86 9-86 3.".88 9-SS 3

LOCA METHODOLOGY 9-86 RAMONA QUALIFICATION LOCA SENSITIVITY 1-87 6-87 7-88 II-S BWR PAD LOCA CALCULATION 6-87 6-87 2f 4-89'-89 BSR 6-87 3-Sg 7-9

WORK SHEET NESTIIIGNOVSE FORII 8295 E INDIVIDUAL TOPICAL REVIEWS 00 IT DAT REVIEW TINE NRC fER SMOOTHED SER DATES (S)

THS TO 3-89 S

NUCLEAR QUALIF ICATIO 6-86 I2-97 8X8 CPR CORRELATION CHANNEL STABILITY 6-86 6-86 7gg

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..7.

BISON QUALIFICATION QUAD+ CORRELATION 8-86 9-86

-SS LOCA METHODOLOGY RANONA QUALIFICATION 9-86 1-87 I-8

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Enclosure 2

ATTENDANCE LIST FOR APRIL 24,

1986, MEETING ON W FUEL IN BWRS Name Mary Haughey Tim Collins Wavne Hodges Allan McFarlane David K. Greene Doug Bevard Donald Hill Larry Phillips Oraani za tion NRC/DBL/BWD-3 NRC/DBL/RSB NRC/DBL/RSB Westinghouse Nuclear Fuel Div.

Niagara Mohawk W Nuclear Technology Systems Div.

Niagara Mohawk Licensing NRC/DBL/RSB Observer Carlene Pindzia SERCH Licensinq/Bechtel Power

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