ML20041C963
| ML20041C963 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/25/1982 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-TM NUDOCS 8203020698 | |
| Download: ML20041C963 (3) | |
Text
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BALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 14 7 5 B A LTIM O R E. M A R YL A N D 21203 E[
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U.S. Nuclear Regulatory Commission Division of Licensing Washington, DC 20555 ATTENTION:
Robert A. Clark, Chief l
Operating Reactors Branch #3
SUBJECT:
NUREG-0737 Item I.A.1.1 Shift Technical Advisor (STA)
Calvert Cliffs Nuclear Power Plant Docket Nos. 50-317 & 50-318, Units 1 & 2
REFERENCES:
(a)
R. A. Clark letter of January 12, 1982, to A. E. Lundvall, Jr., Shift Technical Advisor (b)
A. E. Lundvall, Jr., letter of October 19, 1979, to D. G. Eisenhut, Follow-Up Actions Resulting from Tf11-2 (c)
A. E. Lundvall, Jr., letter of November 20, 1979, to D. G. Eisenhut, same subject (d)
A. E. Lundvall, Jr., letter of December 14, 1979, to D. G. Eisenhut, same subject (e)
D. G. Eisenhut letter of September 13, 1979, to All Operating Nuclear Power Plants, same subject (f)
R. W. Reid letter of April 7,1980, to A. E. Lundvall Jr., Staff Evaluation of Category A Requirements (g)
C. H. Poindexter letter of December 30, 1980, to D. G. Eisenhut, Response to NUREG-0737 Gentlemen:
As you requested in reference (a), the following is a description of the Shift Technical Advisor (STA) positions and associated training program. At Calvert Cliffs we have inplenented an STA program which separates two functions originally described in NUREG-0578. The positions are described in detail by references (b), (c), and (d).
A brief summary of these positions is as follows.
J lt 8203020698 820225 PDR ADOCK 05000317 P
R. A. Clark February 25, 1982 Accident Assessment Function The on-shift accident assessment function is performed by a Senior Reactor Operator (SRO).
During routine operations, this SR0 is either the Senior Control Room Operator who supervises control room activities, or the Shift Supervisor's Assistant who performs many of the administrative duties previously assigned to the Shift Supervisor.
However, during accidents or abnormal transients, this individual detaches himself from " hands-on" responsibilities and performs accident / transient assessment, advising the Shift Supervisor on matters which concern the safety of the plant.
The senior licensed operators who perform the accident assessment function are trained as described in reference (g). The senior licensed individuals trained for accident assessment in 1980 were administered college-level science and engineering courses on topics including the following:
Mathematics Classical Physics Atomic and fluclear Physics Reactor Physics Thermodynamics and Heat Transfer Fluid Mechanics Metal Properties fluclear Plant Heat Transfer and Thennal Hydraulics Water Chemistry and Chemistry Control Process Instrumentation and Control Additionally, they received extensive training in plant transient and accident analysis.
In addition to an in-depth study of the design basis accidents described in the Final Safety Analysis Report, the participants analyzed dozens of plant transients and accidents using the Broughton-Walsh technique.
Since they were all senior licensed operators, additional operations training was not necessary.
l Operating Assessment Function l
The Plant Operating Experience Assessment Committee (P0EAC) performs l
the operating assessment function. The members of this committee are plant staff members representing all major areas of plant operation and maintenance. The Committee regularly reviews the operating experience of Calvert Cliffs and other plants of similar design.
Its goal is to improve plant operational safety by dissemination of pertinent information to the appropriate plant personnel at Calvert Cliffs.
R. A. Clark February 25, 1982 Members are chosen based upon their technical knowledge and experience in the field of their expertise. The background of the present member-ship is as varied as the areas they represent. The comittee includes individuals with advanced engineering degrees and senior operator licenses.
It also has people with over ten years of nuclear-related maintenance experience. The objectives of the commitee are clearly stated in its governing instruction. Therefore, no additional training is necessary or administered.
In accordance with reference (e), the above approach to fulfilling the STA requirement was submitted to the Nuclear Regulatory Commission staff for their review and approval. Their acceptance was indicated in reference (f).
We strongly feel that the addition of a third senior licensed operator to each shift and the diverse membership of the Plant Operating Experience Assessment Comittee contributes more significantly to safe operations and proper accident response than the guidance set forth by NUREG-0578.
The basic functions of the "STA" are being satisfactorily performed at Calvert Cliffs.
During a recent inspection by the Performance Appraisal Section, the POEAC approach was singled out by the inspection team as being a particularly strong point of plant operations.
Should you have further questions regarding this matter, we would be pleased to discuss them with you.
Very truly yours, 0
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Vice President > Supply i
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J. A. Biddison, Esquire G. F. Trowbridge, Esqdire D. H. Jaffe, NRC R. E. Architzel, NRC 4
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