ML20063C734
| ML20063C734 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/27/1994 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-722, NUDOCS 9402070158 | |
| Download: ML20063C734 (4) | |
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3 VinoixxA Ex.ecTurc AND POWEH COMI%NY Ricnnoxts,Vinoix A 20261 January 27, 1994 U. S. Nuclear Regulatory Commission Serial No.93-722 Attention: Document Control Desk NAPS:JHUGSS Washington, D.C. 20555 Docket Nos.
50-338 50-339 License Nos. ' NPF NPF-7 l
Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS.1 AND 2 COMMENTS ON NRC IDENTIFIED WEAKNESSES FROM NRC EXAMINATION REPORT NOS. 50-338/93-301 AND 50-339/93-301 NRC Examination Report No. 50-338/93-301, dated November 12, 1993,-
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documented the results of NRC administered initial written and operating _
examinations to Reactor Operator (RO) and Senior Reactor Operator (SRO) candidates. During the administration of the examination, five weaknesses were identified by the NRC examiners. Although not required, we have elected to comment on several of the NRC-identified weaknesses because our view of -
the concerns differs from that of the NRC examiners. Corrective actions are being taken on the other NRC-identified weaknesses.
If you have any questions, please contact us.
Very truly yours,
\\Jt-6d W. L. Stewart Senior Vice President - Nuclear Attachment O O.h lj.
9402070158 940127 PDR ADDCit 0500o338
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U. S. Nuclear Regulatory Commission Region ll 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. T. A. Peebles, Chief Operations Branch Division of Reactor Safety 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 l
Mr. R. D. McWhorter l
NRC Senior Resident inspector l
North Ai.na Power Station l
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ATTACHMENT COMMENTS ON NRC IDENTIFIED WEAKNESSES FROM NRC EXAMINATION REPORT NO. 50-338/93-301 NRC Examination Report No. 50-338/93-301, dated November 12, 1993, documented the results of NRC administered initial written and operating examinations to Reactor Operator (RO) and Senior Reactor Operator (SRO) candidates. Five weaknesses were identified by the NRC examiners during the administration of the examination. Although not required, comments on three of the NRC-identified weaknesses are provided below:
NRC-IDEN11FIED WEAKNESS The candidates did not know that the Residual Heat Removal (RHR) system was unable to reject core decay heat untilapproximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> after shutdown if the core had a high power history.
COMMENTS A review of actual plant history has shown that the RHR system is capable of removing core decay heat in significantly less than 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. This was the basis for candidate responses. However, the candidates also realize that the RHR system cannot be placed in service to remove decay heat until Mode 4 is reached. Until then heat is removed with the use of the steam dumps.
1 NRC-IDENTIFIED WEAKNESS The candidates demonstrated a weakness in responding to questions in the administrative area.
Several were unfamiliar with temporary modifications, tagging and clearances, and radiation protection.
COMMENTS Discussions with the examiners revealed that the candidates answered the questions correctly but added "I would like to look that up".
Previous examiners have encouraged candidates to demonstrate proficiency in the use of reference materials. The change in philosophy of having a closed book walk-through may have caused some confusion.
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t NRC-IDENTIFIED WEAKNESS The candidates demonstrated a weakness in responding to questions in the area of emergency preparedness. Several could not show how to connect the Techn! cal Support Center (TSC)
Public Address (PA) system with the plant PA system. Also, several candidates were unfamiliar with the NRC notification form Information and the requirements to log certain requests from NRC Headquarters, responses from NRC Headquartera, and change of NRC Operation Officerorcommunicator.
COMMENTS Connecting the TSC PA system to the plant PA system is not performed at North Anna noris the function proceduralized. During emergency exercises, the TSC usually communicates with the Control Room to provide information to make announcements to the plant staff. However, announcements can -
also be made to the plant staff by TSC personnel with the use of the plant PA system.
Operator candidates were re-instructed on NRC communications and NRC notification form information prior to being placed on an operating shift.
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