ML20210V109
| ML20210V109 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/30/1986 |
| From: | Thoma J Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8610100504 | |
| Download: ML20210V109 (20) | |
Text
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SeptembLr 30, 1986 MEMORANDUM FOR: John -F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B FROM:
John Thoma, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B
SUBJECT:
TMI-I RELOAD MEETING SUMMARIES On Tuesday, September 16, 1986, GPUN met with the NRC staff to discuss their Cycle 6 Reload Report to be submitted by October 31, 1986. Enclosure 1 provides the list of attendees and Enclosure 2 contains the handouts provided at the meeting. The purpose of the meeting was to discuss the technical approach utilized by B&W and GPUN to identify any potential problem areas in the report.
% % 5 5 0 L M W D E f.D John Thoma, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B
Enclosures:
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MEETING
SUMMARY
DISTRIBUTION Licensee: GPU Nuclear Corporation
- Copies also sent to those people on service (cc) list for subject plant (s).
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LIST OF ATTENDEES MEETING HELD ON SEPTEMBER 16, 1986 NAME AFFILIATION John Thoma NRC/PWR-B Thierry Ross NRC/PWR-B Norm Lauben NRC/PWR-B Cecil Thomas NRC/PWR-B Daniel Fieno NRC/PWR-B Rick McGoey GPUN Licensing Frank McPhatter B&W-Fuel Engineering Joe Randazzo TMI Licensing Scott Wilkerson TMI Nuclear Engineering Joe McCarthy GPUN TMI Fuel Projects John Luoma GPUN TMI Fuel Projects Dave Distel GPUN Licensing r
TMI-1 CYCLE 6 RELOAD REPORT SUBMITTAL - GPUN/NRC PREMEETING SEPTEMBER 16, 1986
~
I.
INTRODUCTION A.
GPUN Organization B.
Status of Cycle 5 C.
Schedule for Cycle 6 Outage D.
Status of Cycle 6 Reload Report II.
CYCLE DESIGN A.
18-Month Cycle B.
Cycle Design C.
PTS / Fluence Reduction D.
Safety Analysis and Technical Specifications III.
DIFFERENCES FROM TMI-1 CYCLE 5 A.
Use of Cross-Flow Thermal Hydraulic Code (LYNXT)
B.. Core Bypass Flow C.
TACO II D.
Use of Gray APSRs E.
Removal of Power Level Cut-Off F.
Startup Program G.
NUREG-0630 IV.
OTHER V.
SUMMARY
I.
INTRODUCTION A.
GPUN ORGANIZATION B.
CYCLE 5 STATUS o
ABOUT 260 EFPD o
APSRs WITHDRAWN (9/13/86) o EXPECTED SHUTDOWN 11/1/86 (ABOUT 302 EFPD)
C.
SCHEDULE FOR CYCLE 6 0UTAGE o
START NOVEMBER 1sT o
DURATION 4-TO-5 MONTHS o
APPROVED TECH SPEC:
MARCH 1sT I
D.
STATUS OF CYCLE 6 RELOAD REPORT l
0 DRAFT RR TO GPUN (9/15/86) o TECH SPEC CHANGE REQUEST TO NRC (10/31/86)
f
(*
GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION
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i f
I 0FFICE OF THE PRESIDENT
['
I P. R. CumK VICE PRESIDENT &
VICE PRESIDENT &
DIRECTOR DIRECTOR l
TMI-l TECHNICAL FUNCTIONS H. D. HUKILL R. F. WILSON I
I i
i PLANT ENGINEERING DIRECTOR DIRECTOR SYSTEMS DIRECTOR LICENSING J. J. COLITZ ENGINEERING
& REGULATORY AFFAIRS i
T. G. BROUGHTON J. R. THORPE
)
LEAD NUCLEAR ENGINEER NUCLEAR ANALYSIS & FUELS MANAGER PWR LICENSING W. S. WILKERSON DIRECTOR R. J. MC COEY G. R. BOND 1
1 1
MANAGER TMI FUEL MANAGER SAFETY ANAL.
PWR LICENSING PROJECTS
& PLANT CONTROL ENGINEER J. D. LUOMA N. TRIK0UROS D. DISTEL l
FUELS ENGINEER SAFETY ANALYSIS J. D. MC CARTHY ENGINEER L. LANESE i
3999f
Figure 3-1.
Core Loading Diagram for THI-1, Cycle 6 7
7 6
7 7
A NO3 LO2 008 Ll4
.113 7
88 7
88.
6 88 7
88 7
B LO1 F
K01 F
C11 F
KIS F
LIS 7
88 7
88 7
88 7
88 7
88 7
C HIS F
N02 F
M02 F
M14 F
N14 F
RD8 7
88 6
8B 6
88 6
88 6
88 6
8B 7
0 A10 F
C07 F
E07 F
C09 F
E09 F
G13 F
A06 i
E 88 7
88 6
8A 6
8B 6
8A 6
88 7
88 F
B12 F
H06 F
006 F
010 F-F08 F
804 F
7 7
88 6
8A 6
88 6
88 6
8A 6
88 7
7 F
C12 A09 F
GOS F
H02 F
G09 F
B08 F
G11 F
A07 C04 G
7 88 7
8B 6
8B 6
8A 6
8B 6
88 7
88 7
B10 F
B11 F
F04 F
F06 F
F10 F
F12 F
BOS F
B06 6
6 88 6
88 6
8A 6
8A 6
88 6
88 6
6 H04 E03 F
G03 F
C07 F
011 F
K09 F
K13 F
M13 H12 H
7 88 7
88 6
88 6
8A 6
8B 6
88 7
8B 7
PIO F
P11 F
LO4 F
LO6 F
L10 F
L12 F
POS F
P06 K
7 7
8B 6
8A 6
8B 6
88 6
8A 6
88 7
7 L
012 R09 F
K05 F
P08 F
K07 F
H14 F
K11 F
R07 004 8B 7
88 6
8A 6
BB 6
8A 6
88 7
8B M
p p12 F
LOB F
N06 F
N10 F
H10 F
PO4 F
M 7
88 6
8B 6
88 6
88 6
88 6
BB 7
RIO F
K03 F
N07 F
007 F
M09 F
009 F
R06
/
88 7
88 7
88 7
88 7
8B 7
0 A08 F
002 F
E02 F
E14 F
014 F
H01 P
7 8B 7
8B 6
88 7
8B.
7 F01 F
G01 F
005 F
GIS F
FIS 7
7 6
7 7
003 F02 N08 F14 013 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 C
Ba tch Previous Cycle Location; F = Fresh Fuel Assembly
=
3-3 N&Miceps a McDermott compenn
.-m,
,n
Figure 3-2.
Enrichment and 8urnup Distribution for TMI-1, Cycle 6 8
9 10 11 12 13 14 15 2.85 2.95 2.85 2.85 2.85 2.85 2.85' 2.85 H
19,779 0
18,934 0
17,249 0
19,745 20.033 2.85 2.85 2.85 2.85 2.85 2.85 2.85 19,167 0
15,739 0
9,411 0
10,550 2.85 2.95 2.85 2.85 2.85 2.85 19,155 0
16,987 0
7,596 10,330 2.85 2.85 2.85 2.85 M
17,883 0
6,772 0
2.85 2.85 2.85 N
17,249 0
6,513 2.85 0
7,844 P
R X.XX Initial enrichment XX,XXX BOC burnup, mwd /mtU l
Babcock & WHcom 3-4 s.
y
Figure 3-3.
Control Rod Locations and Group Designations for TMI-1. Cycle 6 Fuel Transfer Canal
)
A B
1 6
1 C
3 5
5 3
D 7
8 7
8 7
E 3
5 4
4 5
3 F
1 8
6 2
6 8
1 G
5 4
2 2
4 5
H W-6 7
2 4
2 7
6
-Y K
5 4
2 2
4 5
L 1
8 6
2 6
8 1
il 3
5 4
4 5
3 i
N l
7 8
7 8
7 O
l 3
5 5
3 P
l l
1 6
1 R
i i
Z 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 X
Group Number Group No. of Rods Function 1
8 Safety 2
8 Safety 3
8 Safety 4
9 Safety 5
12 Control 6
8 Control 7
8 Control 8
8 APSRs 3-5 NAMb8 a McDermott com
Figure 3-4.
LBP Enrichment and Distribution for THI-1 Cycle 6 8
9 10 11 12 13 14 15 1.03 1.03 0.80 H
K 1.03 1.03 1.03 0.20 L
1.03 1.03 0.80 M
1.03 1.03 0.80 N
1.03 0.80 0.20 0
0.80 0.80 0.20 l
p 0.20 I
R l
No. of Concentration, BPRAs wt % B C 4
X.XX LEP Concentration (wt % B C in Al 0 )
0l80' 4
23 20 16 0.20 l
Total 3E l
Babcock &WHcom 3-6 aucce m ic e r s l
II.
CYCLE DESIGN A.
18 MONTH CYCLE o
LOW LEAKAGE DESIGN o
425 +/- 15 EFPD o
76 FRESH FUEL ASSEMBLIES o
68 BPRAs B.
CYCLE DESIGN o
CORE MAP (FIGURES 3-1, 3-1) l o
CONTROL ROD MAP (FIGURE 3-3) o BPRA MAP (FIGURE 3-4;)
C.
PTS / FLUENCE REDUCTION
~
BACKGROUND o
JANUARY 1986 BAW-1895 o
TMI-1 MET PTS
" PTS EVALUATION IN CRITERIA AT ACCORDANCE WITH CRITICAL WELD 10CFR50.61 FOR B&WOG o
ASSUMED LL CY 6,
~
REACTOR PRESSURE VESSELS" 7; VLL CY 8 o
MARCH 1986 BAW-1901 o
SAME CYCLE SCHEME
" ANALYSIS OF CAPSULE ASSUMPTIONS AND THI-1C GPUN TMI-1 RV METHODS AS MATERIALS SURVEILLANCE BAW-1901 PROGRAM" o
100 PTS MARGIN CYCLE 6 o
LOW-LEAKAGE DESIGN o
ABOUT 30% PERCENT FLUENCE DECREASE o
TWICE-BURNED ASSEMBLY o
ADDITIONAL FLUENCE OR MAJOR AXIS (FIGURE REDUCTION AT 3-1 AND 3-2)
CRITICAL WELD y
- - = -. -. - - - -
D.
SAFETY ANALYSIS AND TECHNICAL SPECIFICATIONS LIMITING SAFETY SETTINGS
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o CORE PROTECTION SAFETY LIMITS o
FLUX / FLOW / IMBALANCE SETPOINTS LIMITING CONDITIONS FOR OPERATION o
ROD POSITION LIMITS THREE BURNUP WINDOWS 2 PUMP /3 PUMP /4 PUMP CURVES
% RATED POWER VS % ALLOWABLE POWER o
OPERATIONAL IMBALANCE LIMITS THREE BURNUP WINDOWS o
LOCA LIMITED MAXIMUM LHR NUREG-0630 TACO 2 (DENSIFICATION PERIOD)
TACO 2 (REMAINDER OF CYCLE) o APSR TECHNICAL SPECIFICATIONS NONE REQUIRED FOR GRAY APSR o
POWER LEVEL CUTOFF CYCLE SPECIFIC ANALYSIS
~
III.
DIFFERENCES FROM THI-1 CYCLE 5 A.
CROSS-FLOW T-H CODE O
PROVIDES ADDITIONAL DNBR MARGIN o
MASS TRANSFER BETWEEN FLOW CELLS o
USED FOR ANO-1 AND CR-3 o
APPRdVED NRC CODE 1
~
B.
CORE BYPASS FLOW o
2% DECREASE FROM CYCLE 5 BYPASS (8.4% COMPARED TO 10.4%)
o CONSERVATIVE VS. ACTUAL. BYPASS WITH LBPs INSERTED
+
1 C.
TACO 2 o STANDARD IN ALL B&W RELOAD FUEL DESIGNS o
PROVIDES MECHANISTIC DENSIFICATION MODEL o
USED FOR CURRENT LOCA LIMITS o
EFFECTS SHOWN IN BOC ALLOWABLE PEAK LHRs l
l l
1
1 D.
GRAY AXIAL POWER SHAPING RODS APSE DESIGN o
63 INCH INCONEL POISON o
INCREASED CLAD THICKNESS o
BETTER OVERALL QUALITY APSR BENEFIT i
o REDUCED CORE PEAKING o
LOWER KW/FT WITH MOVEMENT o
IMPROVED FUEL RELIABILITY o
LOWER FUEL ENRICHMENTS APSR TECHNICAL SPECIFICATIONS o
NONE REQUIRED o
MINOR PEAKING PENALTY APPLIED. TO OTHER CURVES PREVIOUS EXPERIENCE o
SMUD (RANCHO SECO) o FPC (CRYSTAL RIVER) o DUKE (OCONEE)
'l
~
E.
POWER LEVEL CUTOFF CYCLE 5 ANALYSIS o
GENERIC XENON PENALTY IN ANALYSIS o
TECHNICAL SPECIFICATION PEAKING ENSURED WITHIN GENERIC ASSUMPTIONS CYCLE 6 ANALYSIS o
CYCLE SPECIFIC XENON PEAKING UTILIZED o
PEAKING PENALTY APPLIED IN LCO CURVES PREVIOUS EXPERIENCE o
DUKE (OCONEE) 0 ARKANSAS POWER & LIGHT (ANO-1)
--~w w
v.
,-w
,w n
I F.
STARTUP TESTING ZERO POWER TESTING o
CONTROL ROD TRIP TESTING o
ALL RODS OUT CRITICAL BORON o
ISOTHERMAL TEMPERATURE COEFFICIENT o
CONTROL ROD WORTH o
BORON WORTH POWER ESCALATION TESTING o
CORE POWER DISTRIBUTION INTERMEDIATE POWER LEVEL (40% - 75%)
FULL POWER (100%)
o INCORE/EXCORE DETECTOR CORRELATION (0 INTERMEDIATE POWER)
REVISED SLOPE CRITERION o
POWER COEFFICIENTS (O FULL POWER)
DOPPLER COEFFICIENT TEMPERATURE COEFFICIENT h
o O
G.
REVISED CLADDING RUPTURE / BALLOONING MODELS o
INCLUDED IN CYCLE 6 LOCA LIMITS o
PENALTIES AT BOC o
EFFECTS INCLUDED IN OTHER TECH SPECS I
l
- _ -