ML20246N183
| ML20246N183 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/06/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246N163 | List: |
| References | |
| NUDOCS 8903270317 | |
| Download: ML20246N183 (2) | |
Text
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UNITED STATES
.8 NUCLEAR REGULATORY COMMISSION o
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wAsHwaTow.p.c. noses SAFETY EVALUAT_ ION BY THE OFFICE OF NUCLEAR REACTOR. REGULATION RELATED T0. AMENDMENT.NO. 27.TO FACILITY OPERATING. LICENSE NO. NPF-42 5
WOLF CREEK NUCLEAR-OFERATING CORPORATION i
WOLF CREEK GENERATING STATION DOCKET NO. 50-482 INTRODUCTION By letter dated May 7,'1907, the Wolf Creek Nuclear Operr. ting Ccrperation I
recuested changes to the Wolf Creek Generating Station (WCGS), Unit Nc.1 Technical Specifications 3.1.3.1, Group Height, and its associated Bases to-allow continued operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for diagnosis and repair, with one or more control roc: assemblies incperable due to a rod control urgent failure alarm or other electrical prcblem in the red control system provided all affected control rods remain trippable.
As described in the WCGS Updated Safety Analysis Report (USAR) the Control Red Drive System (CRDS) serves to insert or withdraw rod cluster control assemblies within the reactor core to control average core temperature and to shut down the retctor. The CRDS performs its intended safety function, reactor trip, by putting the reactor in a suberitical condition when a safety system setting is reached, with any assumed credible failure of a single active component. The essentiel elenents of the CRDS (those required to ensure reactor trip) are iscisted frcm nonessential portions of the CRDS (the rod control system).
The CRDS provides a Rod Cct. trol Urger.t Failure alarm, which indicates that an electronic / electrical malfunction has occurred within the CRDS. The conditions thct can cause this alarm do not affect the ability to trip any control rces. This may result in a situation where the control rods cannot be stepped in or out of the reactor, however, the rods remain trippable and therefore capable of performing their safety function.
WCGS Technical Specifications 3.1.3.1 ACTION b, currently reevires that, "with more than one full-length rod inoperable or misaligned from the group step counter demand position by more than 12 steps (indicated position), be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />". Althcugh the current Technical Specification recognizes the greater significance of rods being inarvable or known to be untrippable, acknowledgement of the lesser significance of electrically incperable reds would allow additional time for diagnosis and repair of sa1 functioning equipment while maintaining safe operation of WCGS.
The proposed amendment request provides a distinct ACTION statement for an inoperable rod consistent with the significance of the malfur.ction. A rod that is increrable due to being untrippable is more significant than a rod that cannot be stepped due to an electrical malfunction, but remains 8903270317 890306 PDR ADOCK 05000482 p
2.
Accordingly, the license is amended by changes to the Technical Specif1-cations as indicated in the attachment to this license amendinent and Paragraph 2.C.(2) of Facility Operating License no. hPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specificatier.s cer.tained in Appendix A, as revised thrcugh Amendment No. 27, and the Envirorsental Protection Plan contained'in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility it. ectordance with the Technical Specificatier.s and the Environmental Protecticn Plan.
3.
The license amenduent is effective as cf its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Jose A. Calvo, Director Project Directorate - IV Division cf Reactor Prefects - III, IV, V and Special Projccts Office of Nuclear Reactor Regul6 tion Attachrent:
Cher.ges to the Technical Specificaticr.s Date of Issuance: March 6,1989 l
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