ML20212R611
| ML20212R611 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/20/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 86-181, NUDOCS 8702030001 | |
| Download: ML20212R611 (3) | |
Text
F Tech. Spec. 6.9 VINGINIA ELECTHIC AND POWEN CO>tPANY Ricnwoxn,VinoimA 20061 W.L.STHWANT Vacs Pumminant NecLeAE oramations January 20, 1987 United States Nuclear Regulatory Commission Serial No.86-818 Attention: Document Control Desk N0/DAH:vlh Washington, D.C.
20555 Docket Nos.
50-338 50-339 License Nos.
NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2
SUMMARY
OF CORE POWER UPRATING IMPLEMENTATION AND TESTING On August 25,
- 1986, the United States Nuclear Regulatory Commission issued Amendments Nos. 84 and 71 to Facility Operating License Nos.
NPF-4 and NPF-7 for the North Anna Power Station, Units No. I and No. 2 (NA-1 and NA-2).
These amendments revised the licenses and Technical Specifications for NA-1 ar.d NA-2 to increase the rated core power from 2775 megawatts-thermal (MWt) to 2893 MWt.
This letter report is submitted to the USNRC pursuant to the requirements of Technical Specification 6.9 for both NA-1 and NA-2 to provide a summary report following amendment to the license involving a planned increased in power level.
Amendment No.
71 to Facility Operating License No.
NPF-7 for NA-2 was implemented the first week of September 1986 with power escalation to 2893 MWt core power on September 5,
1986.
Amendment No. 84 to Facility Operating License No. NPF-4 for NA-1 was implemented the first full week of October 1986 l
(
vith power escalation to 2893 MWt core power on October 9, 1986.
For both NA-1 and NA-2, the protection and control instrumentation changes necessary to implement the revised Technical Specifications were made in accordance with Instrument Calibration Procedures approved by the Station Nuclear Safety and Operating Committee (SNSOC).
A SNSOC approved l
implementation schedule designed to assure that no Technical Specifications would be violated during the implementation process was followed. Revisions to l
Periodic Tests (to assure compliance with Technical Specification surveillance requirements), Station Curves, and other affected station procedures required power uprating implementation were approved by SNSOC and implemented for core simultaneously with the instrumentation changes. Other procedures not required for core power uprating implementation will be changed prior to their nexc performance.
I 8702030001 870120
[
PDR ADOCK 05000338 1(O l
p PDR L
Implementation of the Technical Specification
- changes, including the instrumentation rescalings, was accomplished on each unit with the reactor operating at 2775 MWt and connected to the electrical grid. On both units the SNSOC conducted an additional review of the instrumentation changes after they had been implemented and immediately prior to rescaling the ex-core nuclear instrumentation (NIS) at 2775 MWt from 100% Nominal Full Power (NFP) to indicate 95.9%.
This relates to the new 100% NFP rating of 2893 MWt.
The implementations went very smoothly on both NA-1 and NA-2.
Power escalation from 2775 MWt core power to 2893 MWt was controlled by Special Test procedure 2-ST-50 for NA-2 on September 5,
1986, and by Special Test procedure 1-ST-68 for NA-1 on October 9, 1986. These procedures were approved by the SNSOC and required significant primary and secondary plant parameters to be carefully monitored during the power escalation to the new licensed core power of 2893 MWt.
At 2775 MWt prior to the power escalation, the actual secondary plant parameters were compared with a computer model generated heat balance. A similar comparison between actual secondary plant parameters and predicted values from the computer model heat balance was made after the power escalation at 2893 MWt.
For both NA-1 and NA-2, good agreement between the computer generated heat balance parameters and actual plant parameters at both 2775 MWt and 2893 MWt was obtained. During the power escalation from 2775 MWt to 2893 MWt power was stabilized after each 0.5% increase in reactor power and primary and secondary plant data recorded and evaluated and a secondary plant walkdown conducted to assure that no unexpected changes in plant parameters were occurring. The power escalation to 2893 MWt went very smoothly on both NA-1 and NA-2 with no unexpected changes in plant parameters.
Flux map data were obtained at stable equilibrium conditions at 2775 MWt before the core upratings, i.e. on 10/07/86 for NA-1 and on 8/26/86 for NA-2, and at 2893 MWt after the core upratings, i.e. on 10/14/86 for NA-1 and on 9/09/86 for NA-2, using the moveable incore detector system.
Full core, three-dimensional power distributions were determined by analyzing these data using the Westinghouse developed computer program INCORE which couples the measured flux map data with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core. A comparison of the core power distributions and incore peaking data before and after the core upratings showed only minor changes in the core power distributions and peaking factors which were well within acceptable limits.
Steam generator moisture carryover measurements were made using a radioactive sodium tracer in accordance with SNSOC approved Special Test procedure 1-ST-1 on 6/28/86 for NA-2 and 7/11/86 for NA-1 to establish baseline data before the core upratings. Moisture carryover was found to be slightly higher on NA-1 than on NA-2.
After the core upratings the moisture carryover measurements were repeated on 10/30/86 on NA-1 as the more limiting unit.
Moisture carryover was found to be only slightly higher after the core upratings than before the upratings. Moisture carryover measurement results were well below the limits specified by the turbine vendor, Westinghouse.
i
In summary, the Virginia Electric and Power Company has implemented Amendment Nos. 84 and 71 to Facility Operating License Nos. NPF-4 and NPF-7 for NA-1 and NA-2, respectively, and has increased the operating reactor core power on both units to 2893 MWt and has found the results of testing done in conjunction with the core power upratings to be acceptable.
Very truly yours, f%
3 A.
W. L. Stewart cc:
U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station
.m m--
=
r-
--we>
wa--
-r-
-