ML20206H329
| ML20206H329 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/13/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 87-179, NUDOCS 8704150329 | |
| Download: ML20206H329 (5) | |
Text
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T.S.6.9.1.7 VIROINIA ELECTRIC AND power COMPANY j
RIcuxoNn,VINGINIA 232 G1 W.L.SraWANT Vaca Pumannaar NUCLEAM OrnaAttons April 13, 1987 U. S. Nuclear Regulatory Commission Serial No.87-179 Attn: Document Control Desk E8C/J0E:ssb Washington, D.C.
20555 Docket No. 50-338 License No. NPF-4 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 1 RELOAD INFORMATION FOR CYCLE 7 North Anna Unit No.
1 is scheduled to complete its sixth cycle of operation on April 17, 1987, and will go into an outage for refueling.
The purpose of this letter is to advise you of our plans for the Cycle 7 reload core and to transmit to you the Core Surveillance Report containing specific power distribution limits applicable for Cycle 7 i
operation.
We have submitted a request for a Technical Specification change to increase the boron concentration in the RWST, associated safety systems and the refueling cavity to provide additional shutdown capacity for more reactive core design necessitated by the recent core uprate. This request was submitted to the NRC on December 22, 1986 by our letter 86-690.
The Cycle 7 core design assumed that this change would be approved prior to the onload of the Cycle 7 core.
If approval is not received, a redesign of the core would be necessary.
We have also submitted a proposed license condition change to the NRC on February 20, 1987, by our letter 87-025 to support the use of two demonstration assemblies in the Cycle 7 reload.
These assemblies each contain 24 fuel rods that are clad with a highly characterized zirconium l.
base alloy.
The supporting evaluations for this change were included with the our letter.
If approval for use of these fuel rods is not received, it will be necessary to replace either these fuel rods or the fuel assemblies.
The Cycle 7 reload core was analyzed in accordance with the methodology documented in the approved topical report VEP-FRD-42, Rev. 1-A, " Reload Nuclear Design Methodology," using NRC approved codes as referenced in the topical. These analyses were performed and reviewed by our technical j
staff. The results of these analyses indicated that no key analysis parameters would become more liniting during Cycle 7 operations than the values assumed in the currently applicable safety analyses updated for the above referenced request for the boron concentration increase Technical Specifications change.
Further, the analyses demonstrated that the Current Technical Specifications, as approved through Operating h
11g 0704150329 870413 k
PDR ADOCK 05000338 P
License Amendment No.
90, are appropriate and require no additional changes other than the boron concentration increase change and the cladding license condition change discussed above.
A review has been performed by both the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.
It has 2
been determined that no unreviewed safety question as defined in 10 CFR i
50.59 will exist as a result of the Cycle 7 reload core. provides the Core Surveillance Report containing the specific Cycle 7 values for Fxy and the axial power distribution surveillance limit, Pm.
This report is being provided as required by North Anna Unit No. 1 Technical Specification 6.9.1.7 and is based on the current total peaking factor (F ) limit of 2.15.
q During Cycle 6 operation, we experienced levels of primary coolant activity which were indicative of minor fuel element defects in the core.
assembly (ies) planning we are a fuel As a result of the primary coolant activity, containing fuel examination program to identify the defects. We expect to know by approximately May 7, 1987 if an alternate loading pattern for Cycle 7 will be needed. You will be notified if a redesign is required, and we will inform you by approximately May 26, 1987 of the results of our evaluation of the alternate loading pattern in accordance with 10 CFR 50.59.
In the event that Technical Specification changes are required to support Cycle 7 operation with a revised loading pattern, we will be contacting you to request expeditious review of the change request.
This accelerated review would be needed to support our current operating schedule which calls for Cycle 7 startup by approximately June 15, 1987.
This letter is provided for your information and planning.
- However, should you have questions, please contact us at your earliest convenience.
Very truly yours, k
- 11. L. Stewart At tachment 1.
Core Surveillance Report for North Anna 1, Cycle 7 cc:
. S. Nuclear Regulatory Commission hl' Marietta Street, N.W.
Sur'e 2900 Atlare, Georgia 30323 Mr. J. L. laldwell NRC Senior Msident Inspector North Anna Peter Station
f ATTACHMENT 1 NORTH ANNA UNIT 1, CYCLE 7 CAOC CORE SURVEILLANCE REPORT FOR FQ=2.15
_..~.. _
i TABLE 1 NORTH ANNA UNIT 1, CYCLE 7 CORE SURVEILLANCE LIMITS, F0 = 2.15 4
I..The F-xy limits for RATED' THERMAL POWER within specific core planes shall be:
i Fxy-RTP _ 1,71 for all core planes containing bank "D" control rods; 1.
l and l
2.
Fxy-RTP as described below for all unrodded core planes:
i a.
.Fxy-RTP 1 1.64 from 15% to 36% of core height, b.
Fxy-RTP s 1.62 from 36% to 60% of core height, and Fxy-RTP s 1.64 from 60% to 85% of core height.
c.
II. The axial power distribution surveillance threshold power level shall be:
1.
Pm = 100% of RATED THERMAL POWER.
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