ML20198R756
| ML20198R756 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/04/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| 86-356, NUDOCS 8606100198 | |
| Download: ML20198R756 (14) | |
Text
{{#Wiki_filter:* VIHUINIA ELECTRIC AND l'OWEM COMi%NY Hncuuonn.Vn uannu unuan W. I.. STMWANT Vers Pasassammt June 4, 1986 ~ w m =*= or..rion. Mr. Harold R. Denton, Director Serial No. 86-356 Office of Nuclear Reactor Regulation E&C/KLB/ap Attn: Mr. Lester S. Rubenstein, Director Docket Nos. 50-338 PWR Project Directorate No. 2 50-339 Division of PWR Licensing-A License Nos. NPF-4 U.S. Nuclear Regulatory Commission NPF-7 Washington, D.C. 20555 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NCS. 1 AND 2 CORE SURVEILLANCE REPORTS FOR 2893 MWt OPERATION By letter dated May 2,1985, Virginia Electric and Power Company requested an amendment to the North Anna Unit 1 and 2 Technical Specifications to allow operation with a core rated thermal power of 2893 MWt. This submittal was supplemented with additional information by letters dated February 6, 1986 and April 30, 1986. This letter transmits the Core Surveillance Reports associated with 2893 MWt operation for North Anna 1, Cycle 6 and North Anna 2, Cycle 5. The North Anna 1, Cycle 6 and North Anna 2, Cycle 5 reload cores were r' analyzed in accordance with the methodology documented in topical report VEP-FRD-42 Rev. 1, " Reload Nuclear Design Methodology," using NRC approved codes as referenced in the topical. These analyses were performed and reviewed by our technical staff. The results of these analyses indicated that no key analysis parameters would become more limiting than the values assumed in the safety analyses applicable to a core rated thermal power of 2893 MWt. Further the analyses demonstrated that the current Technical Specifications, as modified by the changes included in the references above, are appropriate and require no additional changes. A review has been performed by both the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that no unreviewed safety question as defined in 10CFR50.59 will exist as a result of operation of the North Anna 1, Cycle 6 and North Anna 2, Cycle 5 reload cores at core rated thermal power levels of 2893 MWt. 8606100198 860604 PDR ADOCK 0500 8 p............- ,f &'I i
vamonw A Es.rcraic Awo Powru Coweawy To Harold R. Denton provides the North Anna 1 Cycle 6 Core Surveillance Report containing the cycle specific values for Fxy limits and the axial power distribution surveillance limit, Pm. Attachment 2 provides the North Anna 2, Cycle 5 Core Surveillance Report containing the cycle specific values for N(z) and the Axial Flux Difference limits. Both Core Surveillance Reports are based on a total peaking factor (FQ) limit of 2.15. In accordance with Section 6.9.1.7 of the Unit 1 and 2 Technical Specifications, we will need written authorization from you in order to. implement the information contained in these reports within the next sixty days should the core uprate Technical Specifications amendments become effective during thac time period. Please contact us if you have any questions or require any additional information. Very truly yours, p., 'W W. L. Stewart Attachments 1. North. Anna Unit 1, Cycle 6 CAOC Core Surveillance Report for FQ=2.15 and Power Uprate to 2893 MWt. 2. North Anna Unit 2, Cycle 5 RPDC Core Surveillance Report for FQ=2.15 and Pcwer Uprate to 2893 MWt. i ~
vsmoiNIA Es.ECTRIC AND POWER COMPANY TO larOld R. Denton cc: Dr. J. Nelson Grace Regional Administrator NRC Region II NRC Senior Resident Inspector North Anna Power Station Mr. Leon B. Engle NRC North Anna Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A Director, Office of Nuclear Reactor Regulation Attention: Chief, Reactor Systems Branch Division of PWR Licensing-A U.S. Nuclear Regulatory Commission Washington, D.C. 20555 p.- --*--6 -y-. -,, w __y
ATTACMENT 1 NORTH ANNA UNIT 1, CYCLE 6 CAOC CORE SUdVEILLANCE REPORT FOR FQ=2.15 AND POWER UPRATE TO 2893 Mt Y
TABLE 1 NORTH ANNA UNIT 1, CYCLE 6 UPRATED CORE SURVEILLANCE LIMITS, FQ = 2.15 I. The F-xy limits for RATED THERMAL POWER within specific core planes shall be: 1. Fxy-RTP 1 1.71 for all core planes containing bank "D" control rods, and 2. Fxy-RTP S 1.66 for all unrodded core planes. II. The axial power distribution surveillance threshold power level shall be: 1. Pm = 100% of RATED THERMAL POWER. i e l I l
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ATTAC N NT 2 NORTH AfslA UNIT 2. CYCLE 5 RPDC CORE SURVEILLANCE REPORT FOR F@2.15 AND POWER UPRATE TO 2893 Mit
NORTH ANNA UNIT 2 CYCLE 5 RPDC CORE SURVEILLANCE REPORT FOR FQ=2.15 AND POWER UPRATE TO 2893 MWt This Core Surveillance Report is provided in accordance with Section 6.9.1.7 of the North Anna Unit 2 Technical Specifications. The Burnup-dependent Cycle 5 N(z) function for Technical Specification 4.2.2.2 is shown in Figures 1-5. N(z) was calculated according to the procedure of VEP-NE-1A. The N(z) function
- will be used to confirm thct the heat flux hot channel factor, FQ(z), will be limited to the Technical Specifications values of FQ(z) ~< 2.15 K(z), P > 0.5 and T
FQ(z) 3 4.30 K(z), P <0.5. The Cycle 5 Axial Flux Difference (AFD) limits for Technical Specification 3.2.1 are shown in Figure 6. These limits were calculated according to the methods of VEP-NE-1A and are slightly more restrictive than the limits at non-uprated conditions. The limits on Axial Flux Difference assure that the FQ(z) upper bound envelope is not exceeded during either normal operation or in the event of xenon redistribution following power changes.
- The N(z) function, when applied to a power distribution measured under equilibrium conditions, demonstrates that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10CFR50.46.
80R625RCA307
N(Z) FUNCTION TOP AND BOTTOM 15% EXCLUDED NORTH ANNA UNIT 2 CYCLE 5 AT 2893 MW AS PER TECHNICAL SPECIFICATION 4.2.2.2.G BURNUPS 2,000 to 3,000 MWD /MTU 5~ HEIGHT N(Z) HEIGHT N(Z) (FEET) (FEET) 0.0 6.2 1.196 0.2 6.4 1.200 i 0.4 6.6 1.201 0.6 6.8 1.201 O.8 7.0 1.199 1.0 7.2 1.197 1.2 7.4 1.197 1.4 7.6 1.198 e 1.6 7.8 1.196 E 1.8 1.167 8.0 1.190 8 2.0 1.163 8.2 1.184 ,3 s 2.2 1.159 8.4 1.176 I 2.4 1.155 8.6 1.165 l 2.6 1.148 8.8 1.154 5 2.8 1.143 9.0 1.147 n 3.0 1.133 9.2 1.142 n 3.2 1.130 9.4 1.135 E i.2 3.4 1.137 9.6 1.127 j 3.6 1.149 9.8 1.119 r 3.8 1.156 10.0 1.114 I N s 4.0 1.161 10.2 1.112 '~s l K 4.2 1.164 10.4 4.4 1.165 10.6 4.6 1.163 10.8 i.i 4.8 1.158 11.0 5.0 1.154 11.2 5.2 1.156 11.4 5.4 1.165 11.6 5.6 1.174 11.8 5.8 1.184 12.0 6.0 1.192 1.0 C 2 4 6 6 10 12 CORE HEICHT IFEEll Figure 1 - N(Z) Function for N2C5 at 2893 from 2,000 to 3,000 MWD /MTU Burnup
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N(Z) FUNCTION TOP AND BOTTOM 15% EXCLUDED NORTH ANNA UNIT 2 CYCLE 5 at 2893 MW AS PER TECHNICAL SPECIFICATION 4.2.2.2.G BURNUPS BETWEEN 5,000 AND 7,000 MWD /MTU HEIGHT N(Z) HEIGHT N(Z) (FEET) (FEET) I 0.0 6.2 1.205 0.2 6.4 1.212 0.4 6.6 1.216 0.6 6.8 1.221 0.8 7.0 1.221 1.0 7.2 1.220 1.2 7.4 1.215 1.4 7.6 1.207 o 1.6 7.8 1.198 E 1.8 1.154 8.0 1.188 y i3 2.0 1.146 8.2 1.178 2.2 1.137 8.4 1.169 o r 2.4 1.129 8.6 1.158 2.6 1.124 8.8 1.151 5 2.8 1.122 9.0 1.145 3.0 1.116 9.2 1.144 n N 3.2 1.114 9.4 1.145 Ui.- \\ 3.4 1.116 9.6 1.148 I h 3.6 1.121 9.8 1.148 i [ 3.8 1.125 10.0 1.150 -8 4.0 1.130 10.2 1.152 I 4.2 1.132 10.4 4.4 1.133 10.6 / 4.6 1.133 10.8
- i 4.8 1.136 11.0 5.0 1.144 11.2 5.2 1.156 11.4 5.4 1.169 11.6 5.6 1.181 11.8 5.8 1.191 12.0 6.0 1.200
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I N(Z) FUNCTION TOP AND BOTTOM 15% EXCLUDED NORTH ANNA UNIT 2 CYCLE 5 AT 2893 MW AS PER TECHNICAL SPECIFICATION 4.2.2.2.G BURNUPS GREATER THAN 14,500 MWD /MTU '5 HEIGHT N(Z) HEIGHT N(Z) (FEET) (FEET) 0.0 6.2 1.223 0.2 6.4 1.229 0.4 6.6 1.230 0.6 6.8 1.230 O.8 7.0 1.230 1.0 7.2 1.234 1.2 7.4 1.235 l 1.4 7.6 1.232 5 1.6 7.8 1.225 E 1.8 1.168 8.0 1.215 0 2.0 1.164 8.2 1.205 ,,7 s 2.2 1.159 8.4 1.195 I 2.4 1.153 8.6 1.184 8 2.6 1.146 8.8 1.172 6 2.8 1.139 9.0 1.153 n 3.0 1.128 9.2 1.144 n / 3.2 1.124 9.4 1.141 E i.e. / \\ 3.4 1.127 9.6 1.144 j / 3.6 1.137 9.8 1.144 / 3.8 1.144 10.0 1.145 r Y 4.0 1.152 10.2 1.145 i / (__ 4.2 1.157 10.4 j 4.4 1.161 10.6 4.6 1.164 10.8 4.8 1.164 11.0 i. 5.0 1.166 11.2 5.2 1.176 11.4 5.4 1.190 11.6 5.6 1.199 11.8 5.8 1.205 12.0 6.0 1.215 i n.o C 2 4 6 8 to th conc wcicar inct ' Figure 5 - N(Z) Function for N2C5 at 2893 MW greater than 14,500 MWD /MTU Burnup
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