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{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 21, 2003 United States Nuclear Regulatory Commission                 Serial No.:  03-357 Attention: Document Control Desk                             NLOS/MM Washington, DC 20555-0001                                   Docket No.: 50-280 License No.: DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 CYCLE 19 CORE OPERATING LIMITS REPORT Pursuant to Surry Technical Specification 6.2.C, attached is a copy of the Virginia Electric and Power Company's (Dominion) Core Operating Limits Report for Surry Unit 1 Cycle 19 Paftern EM, Revision 0.
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 21, 2003 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Serial No.:
If you have any questions or require additional information, please contact us.
NLOS/MM Docket No.:
License No.:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 CYCLE 19 CORE OPERATING LIMITS REPORT Pursuant to Surry Technical Specification 6.2.C, Electric and Power Company's (Dominion)
Core Unit 1 Cycle 19 Paftern EM, Revision 0.
attached is a copy of the Virginia Operating Limits Report for Surry If you have any questions or require additional information, please contact us.
Very truly yours,
Very truly yours,
. L.Funderburk, Director Nuclear Licensing and Operations Support Attachment Commitment Summary: There are no new commitments as a result of this letter.
. L.Funderburk, Director Nuclear Licensing and Operations Support Attachment Commitment Summary: There are no new commitments as a result of this letter.
03-357 50-280 DPR-32


Serial No.: 03-357 Docket No. 50-280 cc: U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 Mr. C. Gratton U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8G9 Rockville, MD 20852 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station
Serial No.: 03-357 Docket No. 50-280 cc:
U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 Mr. C. Gratton U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8G9 Rockville, MD 20852 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station


Serial No.: 03-357 Docket No.: 50-280 Attachment CORE OPERATING LIMITS REPORT Surry 1 Cycle 19 Pattern EM Revision 0 May 2003 Virginia Electric and Power Company (Dominion)
Serial No.: 03-357 Docket No.: 50-280 Attachment CORE OPERATING LIMITS REPORT Surry 1 Cycle 19 Pattern EM Revision 0 May 2003 Virginia Electric and Power Company (Dominion)


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==
This Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 19 has been prepared in accordance with the requirements of Technical Specification 6.2.C.
This Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 19 has been prepared in accordance with the requirements of Technical Specification 6.2.C.
The Technical Specifications affected by this report are:
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 3.12.13.2 - Power Distribution Limits 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.
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 3.12.13.2 - Power Distribution Limits 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. .E and TS 5.3.A.6.b) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:
2.1 Moderator Temperature Coefficient (TS 3..E and TS 5.3.A.6.b) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:
                  +6.0 pcm/F at less than 50 percent of RATED POWER, or
+6.0 pcm/F at less than 50 percent of RATED POWER, or
                  +6.0 pcm/°F at 50% of Rated Power and linearly decreasing to 0 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.
+6.0 pcm/°F at 50% of Rated Power and linearly decreasing to 0 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.
SlC19 COLR Rev 0                                                                 Page 2 of 5
SlC19 COLR Rev 0 Page 2 of 5


2.3 Heat Flux Hot Channel Factor-FO(z) (TS 3.12.B.1)
2.3 Heat Flux Hot Channel Factor-FO(z) (TS 3.12.B.1)
FQ(z) <     K(z) for P > 0.5 FQ(z) <     K(z) for P <0.5
FQ(z) <
K(z) for P > 0.5 FQ(z) <
K(z) for P < 0.5


===0.5 whzere===
===0.5 whzere===
P=ThermalPower Rated Power 2.3.1 CFQ = 2.32 2.3.2 K(z) is provided in Figure 2.
P=Thermal Power Rated Power 2.3.1 CFQ = 2.32 2.3.2 K(z) is provided in Figure 2.
2.4 Nuclear Enthalpy Rise Hot Channel Factor-FAHN) (TS 3.12.B.1)
2.4 Nuclear Enthalpy Rise Hot Channel Factor-FAHN) (TS 3.12.B.1)
FAH(N) < CFDHx {1+ PFDH(1-P)}
FAH(N) < CFDH x {1 + PFDH(1-P)}
where: P-=ThermalPower Rated Power 2.4.1 CFDH=1.56 for SurryImproved Fuel (SIF) 2.4.2 PFDH=0.3 SlC19 COLR Rev 0                                                 Page 3 of 5
where: P-=Thermal Power Rated Power 2.4.1 CFDH= 1.56 for SurryImproved Fuel (SIF) 2.4.2 PFDH= 0.3 SlC19 COLR Rev 0 Page 3 of 5


Figure 1 S1C19 ROD GROUP INSERTION LIMITS Max w/d position = 230 steps 230 (0.4938, 230) 220 210 200
Figure 1 S1C19 ROD GROUP INSERTION LIMITS Max w/d position = 230 steps (0.4938, 230)
_____C-BA               K 190 (1.0, 113) 180 170 160 150 (0, 151)
_____C-BA K
B 140 C,
(1.0, 11 3)
(0, 151)
D-B NK (0,23)
=
F
+
4-F
+
F t
4-0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 Fraction of Rated Thermal Power 0.8 0.9 1.0 SlC19 COLR Rev 0 230 220 210 200 190 180 170 160 150 B 140 C,
Cn 130 o 120
Cn 130 o 120
  ._2 cn                                                                 D-B NK o 110 0.
._2 cn o 110 0.
O 100 cL CDoo 0 50 90 0
O 100 cL oo 0
70 80 70 60 50 40 30 20 (0,23)              =
70 CD 50 90 0
10 0            F            +  4-      F      *        +        F  t        4-0.0      0.1          0.2  0.3    0.4    0.5      0.6    0.7 0.8      0.9  1.0 Fraction of Rated Thermal Power SlC19 COLR Rev 0                                                                      Page 4 of 5
80 70 60 50 40 30 20 10 0
Page 4 of 5


Figure 2 K(Z) - Normalized FO as a Function of Core Height 1.2 1.1
Figure 2 K(Z) - Normalized FO as a Function of Core Height
:6,1.0 1.0 0.9 (12, 0.925 0.8 0 7 C
:6,1.0 (12, 0.925 0
N   .
1 2
0 N
3 4
  <0.6 0
5 6
z N
7 8
0.5 0.4 0.3 0.2 0.1 0.0 0 1  2    3    4      5    6      7    8    9    10    11    12  13 CORE HEIGHT (FT)
CORE HEIGHT (FT) 9 10 11 12 13 SlC19 COLR Rev 0 1.2 1.1 1.0 0.9 0.8 N
SlC19 COLR Rev 0                                                        Page 5 of 5}}
C 0.7 0
N
<0.6 0z 0.5 N
0.4 0.3 0.2 0.1 0.0 Page 5 of 5}}

Latest revision as of 09:30, 16 January 2025

Cycle 19 Core Operating Limits Report
ML031600972
Person / Time
Site: Surry Dominion icon.png
Issue date: 05/21/2003
From: Funderburk C
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
03-357
Download: ML031600972 (7)


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 21, 2003 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Serial No.:

NLOS/MM Docket No.:

License No.:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 CYCLE 19 CORE OPERATING LIMITS REPORT Pursuant to Surry Technical Specification 6.2.C, Electric and Power Company's (Dominion)

Core Unit 1 Cycle 19 Paftern EM, Revision 0.

attached is a copy of the Virginia Operating Limits Report for Surry If you have any questions or require additional information, please contact us.

Very truly yours,

. L.Funderburk, Director Nuclear Licensing and Operations Support Attachment Commitment Summary: There are no new commitments as a result of this letter.03-357 50-280 DPR-32

Serial No.: 03-357 Docket No. 50-280 cc:

U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 Mr. C. Gratton U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8G9 Rockville, MD 20852 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

Serial No.: 03-357 Docket No.: 50-280 Attachment CORE OPERATING LIMITS REPORT Surry 1 Cycle 19 Pattern EM Revision 0 May 2003 Virginia Electric and Power Company (Dominion)

1.0 INTRODUCTION

This Core Operating Limits Report (COLR) for Surry Unit 1 Cycle 19 has been prepared in accordance with the requirements of Technical Specification 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 3.12.13.2 - Power Distribution Limits 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..E and TS 5.3.A.6.b) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:

+6.0 pcm/F at less than 50 percent of RATED POWER, or

+6.0 pcm/°F at 50% of Rated Power and linearly decreasing to 0 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.

SlC19 COLR Rev 0 Page 2 of 5

2.3 Heat Flux Hot Channel Factor-FO(z) (TS 3.12.B.1)

FQ(z) <

K(z) for P > 0.5 FQ(z) <

K(z) for P < 0.5

0.5 whzere

P=Thermal Power Rated Power 2.3.1 CFQ = 2.32 2.3.2 K(z) is provided in Figure 2.

2.4 Nuclear Enthalpy Rise Hot Channel Factor-FAHN) (TS 3.12.B.1)

FAH(N) < CFDH x {1 + PFDH(1-P)}

where: P-=Thermal Power Rated Power 2.4.1 CFDH= 1.56 for SurryImproved Fuel (SIF) 2.4.2 PFDH= 0.3 SlC19 COLR Rev 0 Page 3 of 5

Figure 1 S1C19 ROD GROUP INSERTION LIMITS Max w/d position = 230 steps (0.4938, 230)

_____C-BA K

(1.0, 11 3)

(0, 151)

D-B NK (0,23)

=

F

+

4-F

+

F t

4-0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 Fraction of Rated Thermal Power 0.8 0.9 1.0 SlC19 COLR Rev 0 230 220 210 200 190 180 170 160 150 B 140 C,

Cn 130 o 120

._2 cn o 110 0.

O 100 cL oo 0

70 CD 50 90 0

80 70 60 50 40 30 20 10 0

Page 4 of 5

Figure 2 K(Z) - Normalized FO as a Function of Core Height

6,1.0 (12, 0.925 0

1 2

3 4

5 6

7 8

CORE HEIGHT (FT) 9 10 11 12 13 SlC19 COLR Rev 0 1.2 1.1 1.0 0.9 0.8 N

C 0.7 0

N

<0.6 0z 0.5 N

0.4 0.3 0.2 0.1 0.0 Page 5 of 5