ML20076F115
| ML20076F115 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/27/1983 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20076F118 | List: |
| References | |
| NUDOCS 8306010426 | |
| Download: ML20076F115 (3) | |
Text
Mamrq Address Alibims Power Compsny 600 North 18th Street Post Offics Box 2641 Birmingham, Alabama 35291 Telephone 205 783-6081 F. L Clayton, Jr.
2 ' ; 2 T "'
AlabamaPower g
the southem electrc system May 27, 1983 Docket No. 50-364 Di rector, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washi ngton, D.C.
20555 Atte nti o n:
Mr. S. A. Va rga Joseph M. Farl'ey Nuclear Plant - Unit 2 Tu rbi ne Val ve Technical Specification Change Request Gentlemen:
In accordance with Unit 2 Technical Specification 3/4.3.4, Alabama Power Company is requi red to perform weekly surveillance testing of turbine valves to demonstrate valve operability.
These surveillance requi rements necessitate stroking all turbi ne stop, governor, reheat stop and reheat intercept val ves through a complete cycle f rom thei r normal operational position.
Due to significant operational transients associated with this testing and the generation of unnecessary radioactive waste as the reactor core nears end-of-life, Alabama Power Company requests a one-time change to Technical Specification 4.3.4.2a and 4.3.4.2b to waive turbine valve testing du ring the remainder of the cu rrent fuel cycle for Unit 2.
In order to perform the existing turbine valve technical specification surveillance requirements, the reactor must be reduced to approximately 90% powe r.
As the reactor core nears end-of-life, cycling the reactor power imposes operational dif ficulties in mai ntaining the axial flux difference within the technical specification target band limitations due to xenon oscillations.
The return to full power following the turbine valve tests performed near the end of reactor core life necessitates the processing of significant amou nts (i.e., 20,000 gallons) of reactor coolant.
Additionally, the return to full power causes operational difficulties associated with overcoming negative reacti vity due to xenon buildup.
These power transients and the potential for delays in returning to full power f rom turbine valve tests performed near the end of reactor core life are unnecessary because the turbine valves and overspeed system have been demonstrated highly pp9by reliable as discussed below, ll0 8306010426 830527 gooO DR ADOCK 05000
1 Mr. S. A. Varga May 27, 1983 U. S. Nuclear Regulatory Commission Page 2 Alabama Power Company has reviewed the results of the weekly turbine valve testing and valve operation during turbine trips and has determined that the turbine valves consistently closed on demand during at-power testing and trips at the Farley Nuclear Plant - Units 1 and 2.
This history of trouble-f ree valve operation provides assurance of the reliability of these valves and the overspeed protection system.
The turbine valves include four turbine stop valves in series with four governor valves for the high pressure turbine and four reheat stop valves in series with four reheat intercept valves for the low pressure tu rbi nes.
These turbine valves are designed to close in the event of certain conditions, one of which is turbine overspeed.
The need for a turbine trip due to overspeed is detected by three sensors.
The prima ry overspeed sensor is part of the Digital Electro-Hydraulic Control System, which produces a turbine t rip at 103% of rated shaf t speed.
The first backup overspeed sensor is a mechanical device that trips the turbine at 111% of rated shaf t speed.
The seconda ry backup overspeed sensor is part of the elect ro-hydraulic control system, which produces a turbine trip at 111.5% of rated shaf t speed.
This redundancy in both turbine valves and overspeed protection controls provides assurance that tu rbi ne speed control will be mai ntai ned.
Fu rthermore, documented assurance of the reliability of the turbine valves has been provided by extensive testing of the turbine valves and overspeed protection system.
In addition to the turbine valves, the redundant main steam isolation valves provide another mechanism to terminate steam flow to the turbi ne.
This proposed one-time change is similar to the one-time change granted by the NRC in Amendment No.18 dated October 8,1982.
Due to the demonstrated high reliability of the turbine valves and the overspeed p rotection system, this proposed change does not represent a significant hazards consideration, as defined in 10 CFR 50.92, and does not jeopardize the safe operation of the Farley Nuclear Plant - Unit 2.
The Plant Operations Review Committee has reviewed and app roved this proposed one-time technical specification change.
The Nuclear Operations Review Board will review this change at a futu re meeti ng.
Alabama Power Compar.y requests approval by July 29, 1983, of this one-time change to Technical Specificaton 4.3.4.2a and 4.3.4.2b (see attachment) for the remainder of the second fuel cycle at Unit 2 based on the operational difficulties currently being experienced.
This cycle is expected to end in October 1983.
This proposed one-time change does not supersede the October 8,1982 submittal requesting deletion of Technical Specification 3/4.3.4.
NRC approval of the October 8,1982 submittal would negate this request for a one-time change.
M r. S. A. Va rga May 27, 1983
]
U. S. Nuclear Regulatory Commission Page 3 i
This proposed amendment i s designated as Class III for Unit 2 in accordance with 10 CFR 170.22 requi rements.
Enclosed is a check for
$4,000 to cover the total amount of fees required.
In accordance with 10 CFR 50.30(c)(1)(i), three signed originals and forty (40) additional copies of the proposed change are enclosed.
4 You rs ve ry truly,
. L. Clayton, r.
FLC/GGY:1sh-D32 SWORN TO AND SUBSCRIQfD BEFORE-ME Attachment THIS
/2 7L DAY OF A0;p, 1983 cc:
Mr. R. A. Thomas U
Mr. G. F. T rowb ri dge
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J Mr. J. P. O'Reilly mitrfful11M Mu Mr. E. A. Reeves N'ota ry Publi c Mr. W. H. B radf ord D r. I. L. Mye rs My Commission Expi res:
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