ML18153A664
| ML18153A664 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/31/1995 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18153A663 | List: |
| References | |
| NUDOCS 9511150022 | |
| Download: ML18153A664 (6) | |
Text
e CORE OPERATING LIMITS REPORT SURRY 1 Cycle 14 Pattern OJ Revision O August 1995 S1C14/0J COLR Rev O (Aug 95) 9511150022 951110 PDR ADDCK 05000280 p
PDR Page 1 of 6
e
- 1. 0 INTRODUCTION This Core Operating Limits Report (COLR) reflects changes in parameters impacted by the implementation of the core uprate -
increase in rated power from 2441 MWt to 2546 MWt for Surry Power Station Unit 1.
Accident reanalyses for core uprate utilized a maximum positive moderator temperature coefficient (MTC) of +6 pcm/°F versus the previous analysis value of +3 pcm/°F.
Technical Specifications (TS) 3.1.E and 5.3.A.6.b place an upper limit of +6 pcm/°F on the MTC.
Section 2.1 of this COLR incorporates the +6 pcm/°F value.
The increase in power requires that a reduction in the F~H limit be made to ensure that the LOPAR. fuel still meets thermal-hydraulic requirements.
To_
accommodate this without unnecessarily penalizing the SIF fuel, separate F~H limits for LOPAR and SIF fuel have been established to ensure that the appropriate DNB limit is met for the applicable fuel type. This change is reflected in COLR Section 2.4 Nuclear Enthalpy Rise Hot Channel Factor -
FAH(N)..
For this cycle the fully withdrawn rod position has been changed to 227 steps (see Figure 1).
This COLR for Surry Unit 1 Cycle 14 operation at uprated conditions has been prepared in accordance with the requirements of TS 6.2.C.
The Technical Specifications affected by this report are:
TS 3.1.E and TS 5.3.A.6.b - Moderator Temperature Coefficient TS 3.12.A.2 and TS 3.12.A.3 - Control Bank Insertion Limits TS 3.12.B.1 and TS 3.12.B.2 - Power Distribution Limits S1C14/0J COLR Rev O (Aug 95)
Page 2 of 6
e e
2,; 0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections~
These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.2.C.
2.1 Moderator Temperature Coefficient (TS 3.1.E and TS 5.3.A.6.b) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:
+6. o pcm/°F at less. than 50 percent of RATED POWER, or
+6. O pcm/°F at SO% of Rated Power and linearly decreasing to O pcm/°F at Rated Power 2.2 Control Bank Insertion Limits (TS 3.12.A.2) 2.2.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.
2.3 Heat Flux Hot Channel Factor-FQ(Z)
(TS 3.12.B.1)
FQ(Z) s FQ(Z) s CFQ p
CFQ 0.5
- K(Z) FOR P > 0.5
- K(Z) for P s 0.5 THERMAL POWER where:
P = --------------
RATED POWER 2.3.1 CFQ = 2.32 2.3.2 K(Z) is provided in Figure 2.
S1Cl4/0J COLR Rev O (Aug 95)
Page 3 of 6
2*: 4 Nuclear Enthalpy Rise Hot Channel Factor - Fti.H (N}
(TS 3.12. B.1)
Fti.H(N) s CFDH * (1 + PFDH * (1 -
P))
THERMAL POWER where:
P = -------------
2.4.1.a 2.4.1.b 2.4.2 RATED POWER CFDH = 1.56 for Surry Improved fuel (SIF)
CFDH = 1.346 for LOPAR fuel PFDH = 0.3 ff S1Cl4/0J COLR Rev O (Aug 95)
Page 4 of 6
FIGURE 1 CONTROL BANK INSERTION LIMITS FULLY WITHDRAWN = 227 Steps
/
.475, 2~ 7).
/
/
/
/
C Be.nK
,.V
/
V
/
z 230 220 210 200 190 180 170 160 O
150 V i/
i=
ci5 -
140 0
C
- a. ~ 130
- a...
~ ~ 120
~ ~ 110 5 g-100 ffi §_ 90
§ 80 a:
70 60 50 40 30 20 10 0
(0, 151
/
/
/to. 23) 0 0.1
/
/
/
/
/
D Be.r:k V
/
/v
/
/
/
/
0.2 0.3 0.4 0.5 0.6 0.7 0.8
. FRACTION OF RATED THERMAL POWER S1Cl4/0J COLR Rev O (Aug 95) 1.0, 18:J)
/
/"
0.9 Page 5 of 6
e e
(
FIGURE 2 K(Z) - NORMALIZED FQ AS A FUNCTION OF CORE HEIGHT 1.2 1.1
- 6. 1.0 1
- ~
0.925 --
0.9 0.8 -
N.....,
0 LL.
O 0.7 w
N :J
< 0.6
== a:
0 z I 0.5 -
N......
~
0.4 0.3 0.2 0.1 0
0 2
3 4
5 6
7 8
9 10 11 12 CORE HEIGHT (FT)
S1Cl4/0J COLR Rev O (Aug 95)
Page 6 of 6