ML20052E875
| ML20052E875 | |
| Person / Time | |
|---|---|
| Site: | North Anna |
| Issue date: | 05/07/1982 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 279, NUDOCS 8205110496 | |
| Download: ML20052E875 (5) | |
Text
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VIRGINIA ELECTRIC AND Powna COMPANY Hicuxoxn, Vanorn A 20261 g
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May 7,1982 g
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a Mr. Harold R. Denton, Director Serial No.: 279 Office of Nuclear Reactor Regulation FR/GLD: plc Attn:
Mr. Robelc A. Clark, Chief Docket No.: 50-339 Operating Reactors Branch No. 3 License No.: NPF-7 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Centlemen:
REVISED CORE SURVEILLANCE REPORT FOR NORTH ANNA 2. CYCLE 2 As discussed with members of the Staff on April 30, 1982, the purpose of this letter is to transmit to you a Core Surveillance Report (CSR) containing revised power distribution limits applicable for Cycle 2 operation. As required by North Anna Unit No. 2 Technical Specification 6.9.1.10, my March 8, 1982 letter (Serial No. 131) provided you with the CSR containing the specific Cycle 2 values for Fxy and the axial power distribution surveillance limit, Pm.
These limits were developed for use with a LOCA FQ limit of 2.10.
In an April 13, 1982 NRC letter (Serial No. 246), Amendment Nos. 39 and 20 approved the use of a LOCA Fq limit of 2.14 for North Anna Units No. 1 and 2.
Consequently, provides a revised CSR containing specific Cycle 2 values of Fxy and Pm appropriate for use with a LOCA Fq limit of 2.14.
We have l
revised the Fxy limit to a value of 1.60 for all unrodded core planes to take credit for the increased margin provided by the 2.14 Fq limit.
l As discussed with the Staff we are requesting approval of the revised CSR prior to the North Anna 2 startup. While operation in accordance with the currently approved CSR limits will result in no operational constraints, approval of the revised CSR prior to startup would eliminate a change of limits during the cycle.
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t 8205110496 820507 PDR ADOCK 05000339 P
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e visointa Ei.scTasc Ano Pows Couraxv to Mr. Harold R. Denton If you would like additional information, please contact this office.
Very truly yours, bued (R.H.Leasburg Attachment (1) Core Surveillance Report for North Anna 2, Cycle 2 (Revision 1) cc:
Mr. James P. O'Reilly Regional Administrator Region II
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a ATTACHMENT 1 Core Surveillance Report North Anna 2, Cycle 2 (Revision 1)
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1 of 2 TABLE 1 NORTH AHilA UNIT 2, CYCLE 2 CORE SURVEILLA1lCE LIMITS, FR = 2.14 I
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The F-):Y limits f or RATED THERMAL POWER uithin specific core plancs shall bc 1.
Txy-RTP 1,.71 for all core plunos containing bank "D"
control rods, and 2.
Fxy-RTP f
'1.60 for all unrodded core planes.
II.
The unini power distribution surveillance threshold power level shall bei 1.
Pm = 100% of RATED THERMAL POWER.
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