ML20046B840
| ML20046B840 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/28/1993 |
| From: | Jaffa R GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20046B838 | List: |
| References | |
| TR-083, TR-083-R03, TR-83, TR-83-R3, NUDOCS 9308060291 | |
| Download: ML20046B840 (34) | |
Text
-
TMI-1 Cycle 9 Core Operating Limits Report TOPICAL REPORT 083 Rev. 3 BA Number 135400 TMI-l Cycle 9 Reload Task Force June, 1993 APPROVALS; f
v'- /C - 93 x
Originator
/ //
Date
&)
s Cy i '9 Reload Task' Force ($hairman date d yx x_
c etes Man'ager, TMI ' Fuel Projects Date d ~28 - 73 Director, Nuclear Analysis & Fuel Date A 9b Plant Review Group Date I
l J
This COLR is Effective as of :
Cycle 9 Initial Criticality 9308060291 930802 PDR ADOCK 050002B7 l'
P PDR L;
l DOCUMENT NO.
TR-083 TITLE TMI-1 Cycle 9 Core Operating Limits Report REV
SUMMARY
OF CHANGE APPROVAL DATE
~
1 Revised Error Adjusted Rod Insertion Limits g4 I"/t/4 A Curves for 2, 3, and 4 Pump Operation from 105 +/- 5 EFPD to EOC to reflect the increase in rod position indication error from MIN
~
1.5% WD to 2.0'; WD.
Similar curves for the 0-45 and 45-105 EFPD windows were not corrected as the identification of the larger error was not made until after 105 EFPD.
2 Incorporated the LOCA limited maximum allowable
/ /
linear heat rate (MALHR) curve into this report, p/ g/ g aswell as bounding values for these limits as a function of cycle burnup and core monitoring system level. Removal of the LOCA limited MALHR curve from the Technical Specifications to the 7K~
14/,3M u 1
COLR has been reviewed per GPUN S.E. 135400-016, Rev.-3.
Reorganized the COLR references based on this re vi s i on.
This revision goes into effect upon NRC approval of TSCR-208 and TSCR-220.
L 3
The following changes were made to the COLR as a I~ #b 93 result of the license extension of Cycle 9 from 590 to 650 EFPD:
- APSR Position Limit added.
gpggy
- A 590-650 EFPD window was added to the CMS Bounding Values for LOCA MALHR (Table 2).
- For Rod Insertion Limit curves (4, 3, and 2 Pump),
the 105 + 5 EFPD to E0C window was revised to 105 + 5 To 590 + 10 EFPD, and a new 590 + 10 EFPD to E0C win'dow was added.
Incorporated Reload Pathodology references from T.S. Section 6.9.5 into COLR to support TSCR 225.
b kf G/IC/93 1
Reorganized the COLR tables, figures and g
re fe rences.
e Aooooo3612 83
~
TR 083 Rev. 3 Page 1 of 32 t
ABSTRACT This..;s Soerating Limits Report (COLR) has been prepared in accordance with the requirems'ta of THI-1 Technical Specification 6.9.5.
The core operating limits were gens ated using the methodologies described in References 13 through 31 and were l'aumented in References 1 through 7.
The information in l
this COLR was reviewed foc acc i* TMI-1 in References 8 through 12.
The Full Incore System (FIS) operability requirements contained within describe the number and location of Self-Powered Neutron Detector (SPND) strings that must be operable in order to monitor imbalance and quadrant tilt i
using the FIS.
l APSR position limits are required to prevent the current core end-of-cycle temperature coefficient from exceeding the analyzed limit.
Quadrant tilt limits for FIS, out-of-core detector [OCD) system and minimum incore system { MIS) are given in Table 1.
Rod position limits are provided in Figures 1 to 3 to ensure that the safety criteria for DNBR protection, LOCA kw/ft limits, shutdown margin and ejected rod worth are met.
Imbalance limits for FIS, OCD and MIS are given in Figures 4 to 6.
COLR Figures 1 through 6 may have three distinctly defined regions:
1.
Permissible Region 2.
Restricted Region 3.
Not Allowed Region (Operation in this region is not allowed)
Inadvertent operation within the Restricted Region for a period not exceeding four (4) hours is not considered a violation of a limiting condition for i
operation.
The limiting criteria within the Restricted Region are potential ejected rod worth and ECCS power peaking.
Since the probability of these accidents is very low, especially in a four (4) hour time frame, inadvertent operation within the Restricted Region for a period not exceeding four (4) hours is allowed.
COLR Figure 7 indicates the LOCA limited maximum allowable linear heat rates as a function of fuel rod burnup and fuel elevation.
Bounding values for monitoring these limits for the current cycle in terms of cycle burnup and axial detector levels are listed in Table 2.
t i
1
l TR 083 Rev. 3 Page 2 of 32
)
TABLE OF CONTENTS I
l PAGE I
References 3
Full Incore System (FIS) Operability Requirements 5
APSR Rod Insertion Limits 6
j l
Table 1 Quadrant Tilt Limite 7
i Table 2 Core Monitoring System Bounding Values for 8
LOCA Limited Maximum Allowable Linear Heat Rate Figure 1 Error Adjusted Rod Insertion Limits 9
4 Pump Operation Figure 2 Error Adjusted Rod Insertion Limits 13 3 Pump operation Figure 3 Error Adjusted Rod Insertion Limits 17 2 Pump Operation Figure 4 Full Incore System Error Adjusted 21 Imbalance Limits Figure 5 Out-of-Core Detector System Error Adjusted 24 Imbalance Limits i
Figure 6 Minimum Incore System Error Adjusted Imbalance Limits 27 Figure 7 LOCA Limited Maximum Allowable Linear Heat Rate 30 Enclosure ( Non-Tech. Spec. Required Operating Limits )
31 l
z l
)
i l
I
e TR 083 Rev. 3 l
Page 3 of 32
References:
Main Body 1.
BAW-2134 Rev.
1, "Three Mile Island Unit 1 Cycle 9 Reload Report,"
October 2991.
2.
BWFC Doc. No. 86-1203799-00, "TMI-1 Cycle 9 Core Limits & Setpoints,"
May 1991.
i 3.
GPUN Calc. No. C1101-202-5412-174, Rev.
1, "TMI-1 Cycle 9 Revised' Error Adjusted Rod Insertion Limits," May 1993.
4.
BWFC Doc. No. 62-1203848-00, " Power Escalation Test Specification TMI-1 Cycle 9," August 29, 1991.
5.
BWFC Doc. No. 86-1223242-00, "THI-1 Cy 9 Ext. Maneuvering," May 1993.
6.
BWFC Doc. No. 32-1201485-01, "TMI-l Cy 9 Maneuvering Analysis," May 1993.
7.
BWFC Doc. No. 51-1223255-01, "THI-1 Cycle 9 Extension Evaluation Summary," May 28, 1993.
8.
GPUN Safety Evaluation 135400-014, Rev.
1, "TMI-1 Cycle 9 Reload Design," November 23, 1992.
9.
GPUN Safety Evaluation 135400-015, Rev. 1, "TMI-1 Cycle 9 Core operating Limits Report," June 3, 1993.
10.
GPUN Safety Evaluation 135400-013, Rev. O,
" Tech Spec LOCA Limit Changes," June 28, 1991.
11.
GPUN Safety Evaluation 135425-008, Rev. O, "TMI-1 Cycle 9 Length Extension to 650 EFPD," June 1993.
12.
GPUN Safety Evaluation 135425-006, Rev. O,
" Tech Spec 6.9.5.2 Reference to BAW-10179P (TSCR 225)," May 3, 1993.
i 13.
Letter from J. H. Taylor (B&W) to J. A. Norberg (NRC), " Extended 4
Lifetime Incore Detector Error Allowances", April 21, 1988, JHT/88-28.
14.
BWFC Doc. No. 86-1172640-00, " Detector Lifetime Extension Final Report for TMI-1," September 1988.
15.
GPUN Safety Evaluation 000622-001, Rev. 1,
" Control Rod API and RPI 24
{
Month Cycle Extension," April 16, 1992.
TR 083 I
Rev. 3 i
Page 4 of 32 i
i h
References (continued):
i Methodoloov t
16.
BAW-10122A, Rev.
1, " Normal Operating Controls," May 1984.
i 17.
BAW-10116-A, " Assembly calculations and Fitted Nuclear Data," May 1977.
18.
BAW-10117P-A, " Babcock & Wilcox Version of PDQ User's Manual," January "7.
19.
EnW-10118A, " Core Calculational Techniques and Procedures," December 1979.
20.
BAW-10124A, " FLAME 3 - A Three-Dimensional Nodal Code for Calculating Core Reactivity and Power Distributions," August 1976.
21.
BAW-10125A, " Verification of Three-Dimensional FLAME Code," August 1976.
l 22.
BAW-10152A, " NOODLE - A Multi-Dimensional Two-Group Reactor Simulator,"
June 1985.
23.
BAW-10119A, " Power Peaking Nuclear Reliability Factors," February 1979.
24.
BAW-10103A, Rev. 3, "ECCS Analysis of B&W's 177-FA Lowered Loop NSS,"
July 1977.
25.
BAW-1915P-A, " Bounding Analytical Assessment of NUREG-0630 Models on LOCA kw/ft Limits With Use of FLECSET," November 1988.
26.
BAW-10104P-A, Rev. 5,
- B&W ECCS Evaluation Model," November 1988.
27.
BAW-10162P-A, " TACO-3 Fuel Pin Thermal Analysis Computer Code," November 1989.
28.
BAW-10179P-A, Rev. O, " Safety Criteria and Methodology for Acceptable Cycle Reload Analyses," February 1991.
29.
BAW-10141P-A, Rev.
1, " TACO-2 Fuel Pin Performance Analysis," June 1983.
30.
BAW-10120P-A, " Comparison of Core Physics Calculations with Measurements," March 1978.
31.
BAW-1775, " TACO Loss-of Coolant Accident Limit Analysis for 177-FA Lowered Loop Plants," February 1983.
Enclosure ( Non-Tech. Spec. Required Operating Limits )
32.
BAW-10143P-A, 1WC Correlation of Critical Heat Flux", April 1985.
33.
BAW-10156A "L T
Core Transient Thermal Hydraulic Program", February 1986.
TR 083 Rev. O Page 5 of 32 Full Incore System (FIS)
Operability Requirements e
The Full incore System (FIS) is operable for monitoring axial power imbalance provided the number of valid Self Powered Neutron Detector (SPND) signals in any one quadrant is not less than 75% of the total number of SPNDs in the quadrant.
Quadrant SPNDs 75 %
WX 85.75 64.5 XY 99.75 75.0 YZ 89.25 67.0 ZW 89.25 67.0 e
The Full incore System (FIS) is operable for monitoring quadrant tilt provided the number of valid symmetric string Individual SPND signals in any one quadrant is not less than 75% (21) of the total number of SPNDs in the quadrant (28).
Quadrant Symmetric Strings WX 7,9,32,35 XY 5,23,25,28 YZ 16,19,47,50 ZW 11,13,39,43 Source Doc.:
B&W 86-1172640-00 Referred to by:
Tech. Spec. 3.5.2.4.a and 3.5.2.7.a j
=
TR 083 j
Rev. 3
. j Page 6 of.32 1
1 APSR Position i mits E
Up to 610 EFPD, the APSRs may be positioned as necessary for transient imbalance control. Prior to exceeding 610 EFPD, the l
APSRs shall be fully withdrawn. If EFPD is greater than 580 ANQ APSRs are fully withdrawn, the APSRs shall not be inserted-for the remainder of the fuel cycle and 0-99% WD shall be considered a " Restricted Region" as defined in_the abstract section of this COLR.
Source Doc.:
B&W 51-1223255-01 4
e
+ru w
ty e-
c g Table 1 Quadrant Tilt Limits 4
Steady State Limit Steady State Limit Maximum Limit 15% < Power _< 50%
Indicated Power > 50%
Indicated Power > 15%
Full Incore System (FIS) 6.83 %
4.39 %
16.8 %
i Out-of-Core Detector
. System (OCD) 4.05 %
1.96 %
14.2 %
Minimum incore System (MIS) 2.80 %
1.90 %
9.5%
- b..i U e
au6 R
Source Docs.:
B&W 86-1203799-00, B&W 51-1223255-01 Referred to by:
Tech. Spec. 3.5.2.4
TR 083 Rev. 3 Page 8 of 32 Table 2 Core Monitoring System Bounding Values for LOCA Limited Maximum Allowable Linear Heat Rate (kW/ft) 1 CMS 0-40 40-438 438-511 511-572 572-590 590-650 Level EFPD EFPD EFPD EFPD EFPD EFPD 8
15.0 15.4 16.0 15.5 15.0 14.75 7
15.4 15.6 16.0 15.5 15.0 14.75 6
16.2 16.1 16.0 15.5 15.0 14.75 5
16.1 16.1 16.0 15.5 15.0 14.75 4
16.1 16.1 16.0 15.5 15.0 14.75 3
14.9 15.7 15.6 15.5 15.0 14.75 2
14.5 15.5 15.5 15.5 15.0 14.75 1
14.5 15.5 15.5 15.5 15.0 14.75 The maximum linear heat rate for each CMS level, as measured with the NAS Thermal Hydraulic Package (Display 4), should be less than the corresponding bounding value from Table 2 above.
Source Doca.
B&W 62-1203848-00 B&W 32-1201485-01
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Error Adjusted Rod Insertion Limits 45 +/- 5 EFPD to 105 +/- 5 EFPD g
2 Pump Operation
~~
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'If 'd Indicated Rod Index, % Withdrawn j*N Source Doc. B&W 86-1203799-00
- m. o Referred to by Tech Spec 3.5.2.5.b and 3.5.2.4.e.2 go$
o 6
Figure 3 (Page 3 of 4)
Error Adjusted Rod Insertion Limits 105 +/- 5 to 590 +/- 10 EFPD g
2 Pump Operation
.. ~
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om
Figure 3 (Page 4 of 4)
Error Adjusted Rod insertion Limits 590 +/- 10 EFPD to EOC i
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0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 260 270 280 290 300
'O lc H Each Div. = 1% WD o e :c Indicated Rod index, % Withdrawn e<
m*
Om Source Doc. B&W 86-1203799-00/B&W 861223242-00/GPUN C1101-202-5412-174, Rev.1 Nuu o
Referred to by Tech Spec 3.5.2.5.b and 3.5.2.4.e.2 o
d
TR 083 Rev 0
Figuro 4 (Paga 1 of 3) page 21 or 32 Fullincore System Error Adjusted imbalance Limits 0 to 45 +/- 5 EFPD l
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-35
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5 to 15 20 25 30 35 Indicated Axial Power imbalance, %FP Each DN. = M FP Source Doc. S&W 86-1203799-00 Referred to Dy Tecn Spec 3.5.2.7.a and 3.5.2.4.e.3 j
i 1
TR 083 Figuro 4 (Paga 2 of 3)
Rev. O m e 22 or32 Full incore System Error Adjusted imbalance Limits 45 +/- 5 EFPD to 105 +/- 5 EFPD i
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5 10 15 20 25 30 35 Indir 'ted Axial Power imbalance, %FP Each DN. - 1% P Source Doc. B&W 86-120379A Referred to ey Tecn Spec 3.5.2.7.a and 3.5.2.4.e.3 t
C Figure 4 (Page 3 of 3) w es3 R ev 3 Full Incore System
%a 2: :o2 Error Adjusted imbalance Umits 105 +/- 5 EFPD to EOC E
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-35
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5 10 15 20 25 30 35 Indicated Axial Power imbalance, %FP Each Div. = 1% FP Source Docs. B&W 86-1203799-00 & 51 1222255-01 Referred to by Tech Spec 3.5.2.7.a and 3.5.2.4.e.3 4
.. = _
TR 083 Figuro 5 (Pago 1 of 3)
Rev-o Page 24 or22 Out-Of-Core Detector System Error Adjusted Imbalance Limits 0 to 45 +/- 5 EFPD gii lilllilll!Iili "o
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.c TR 083 Figuro 5 (Page 2 of 3)
Rev. O Out-of-Core Detector System page 25 or 32 Error Adjusted imbalance Limits 45 +/- 5 EFPD to 105 +/- 5 EFPD i
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Referrec to Dy Tecn Spec 3.5.2.7.b and 3.5.2.4.e.3
v l
Figure 5 (Page 3 of 3)
Ta en R ev T Out-of-Core Detector System QJa e 32 Error Adjusted imbalance Limits 105 +/- 5 EFPD to EOC 5 i Ii
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10 15 20 25 30 35 Indicated Axial Power imbalance, %FP Each Div. = 1% FP Source Docs. B&W 86-1203799-00 & 51-1223255-01 Referred to by Tech Spec 3.5.2.7.b and 3.5.2.4.e.3 I
i e
k TR 083 Figure 6 (Pago 1 of 3) 7 of 3, Minimum incore System Error Adjusted imbalance Limits O to 45 +/- 5 EFPD lil!Illlliilli" 5: I-REsmicED REGION no lll[ j {jjl ; }
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to 15 20 25 30 35 indicated Axial Power imbalance, %FP Each DN. = 1W Source Doc. B&W 86-1203799 00 Referrec to oy Teen Spec 3.5.2.7.c and 3.5.2.4.s.3 l
I i
TR 083 Figure 6 (Page 2 of 3) nov. c Page 28 r 32 Minimum incore System Error Adjusted imbalance Limits 45 +/- 5 EFPD to 105 +/- 5 EFPD 5'l'
llllIlllIlIilE "O
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5 10 15 20 25 30 35 I
Indicated Axial Power imbalance, %FP Each DN. = 1W Source Doc. B&W 86-1203799 00 Referred to by Toen Spec 3.5.2.7.c and 3.52.4.e.3
a Figure 6 (Page 3 of 3)
, oss R ev 3 Minimum incore System a=;e a e y Error Adjusted imbalance Limits 105 +/- 5 EFPD to EOC lll ll l
llE 5i!
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35
-30
-25 20
-15
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-5 0
5 10 15 20 25 30 35 Indicated Axial Power imbalance, %FP Each Div. = 1% FP Source Docs. B&W 86-1203799-00 & 51 1223255-01 Referred to by Tech Spec 3.5.2.7.c and 3.5.2.4.e.3
u TR 083 R ev. 2 Page 30 ::5 32 FIGURE 7 LOCA Limited Maximum Allowable Linear Heat Rate 20 l
19 18
~
8 ft.
17 l
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\\
4 ft.
6 ft.
10ft
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16 g
2 ft 3"
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'm o
TR 083 Rev. O Page 31 of 32 Enclosure Non-Tech. Spec. Required Operating Limits l
l
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TR 083 Rev. O Page 32 of 32 i.)
i i
Core Minimum DNBR Operating Limit
-l i
i The core minimum DNBR value as measured with the NAS i
Thermal Hydraulic Package (Display 1 or 4) should not be less than 2.01 (102% ICDNBR).
1 4
I i
1 i
i i
Source Doc.: BAW 2134 l
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-