ML20002C868
| ML20002C868 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 01/08/1981 |
| From: | Randazza J Maine Yankee |
| To: | Clark R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20002C869 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-TM WMY-80-167, NUDOCS 8101120229 | |
| Download: ML20002C868 (4) | |
Text
.
A "VE MAIREMiHARHEE Atom /CP0l'KRCOMPARS*
AUGUSTA; MAINE 04336 wk (207) 623-3521 O
January 8, 1981 WMY 60-167 B3.2.1 M
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Uniteo States Nuclear Regulatory Commission hasningten, Er 20555
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- g; Attention
Office of Nuclear Reactor Regulation 12 g51 Robert A. Clark, Branch Chief c&'
g Cperating Reactor Branch No. 3 A
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(7) y a
Reference:
(a) License No. CPR 36 (Cocket No. 50-309)
(b) USNRC Letter, D.G. Eisennert to all Licensee of Operating Plants, cateo October 31, 1960 (c) NUREG 0737
Subject:
Shift Technical Aavisor
Dear Sir:
Reference (c) transmitted all TMI - related items approved for implementation oy the ccmmissicn as of Octcoer 31, 1980 as detailed in Reference (c).
l l
Item 1.A l.l. of Reference (c) requires that:
1.
Training tnat meets the lesscos-learnec requirements shall be completed by January 1, 1981 or by the time the fuel-loading license is issueo, whicnever is later.
2.
A cescription of the current training program and cemonstration of i
conformance with the October 30, 1979 letter shall be submitted.
3.
A description of the long-term STA program shall be submitted.
Maine Yankee has completed the training requireo under item (1) above. A cescription of this training and comparison with the October 30, 1979 letter is incluced as Enclosure (1).
A descripten of Maine Yankees 7.ong term STA Program inclucing requalification requirements is incluced in Enclosure (2).
l ihis Program is consistent with the intent of tne 1NPO guicelines.
l I
Maine Yankee currently has no plans for phasecut of the STA program.
We trust the informaticn containeo herein is adequate; however, if further j
clarification is necessary do not hesitate to contact us.
Very truly yours, Maine Yankee Atomic Power Ccmpany kcl:-
e, --
o 10 3 20M7 v a. B. Randazza Vice Presicent, Cperaticns
Enclosure (1)
Description of Present STA Program The October 30, 1979 letter from H. R. Denton to all operating nuclear power plants required that "Each licensee shall provide an on-shift technical advisor to the shift supervisor.
The shift technical advisor (STA) may serve more than one unit at a multiunit site if qualified to perform the advisor function for the various units.
The STA shall have a bachelor's degree or equivalent in a scientific or engineering discipline and have received specific training in the response and analysis of the plant for transients and accidents.
The STA shatl also receive training in plant design and layout, including the capabilities of instrumentation and controls in the control room.
The licensee shall assign normal duties to the STAS that pertain to the engineering aspects of assuring safe operations of the plant, including the review and evaluation of operating experience."
To meet this requirement Maine Yankee assigned personnel with a bachelor's degree in a scientific or engineering discipline to STA duties as described in Maine Yankee letter WMY 80-39 dated March 5,1980 on a rotating basis.
The Designated Shift Technical Advisor training program included lectures and training in the following areas:
A.
Specific plant systems training:
1.
Emergency Core Cooling System 2.
Emergency Cooling Water 3.
Emergency Electrical Power, AC & DC 4.
Chemical and Volume Control System 7.
Containment Spray System 8.
Residual Heat Removal System 9.
Primary and Secondary Component Cooling Systems
- 10. Excore and Incore Nuclear Instrumentation 11.
Compressed Air System 12.
Condensate System
- 13. Main Feedwater System 14.
Auxiliary Feedwater System
- 15. Steam Generator Water Level Control System
- 16. Main and Reheat Steam System 17.
Loose Parts Monitoring System
- 18. Containment Ventilation. System 19.
Auxiliary Building Ventilation System
- 20. Maine Turbine and Turbine Control System
- 21. Main Generator and Auxiliary Systems
- 22. Reactor Core
- 23. Pressurizer and Pressure Relief System 1
24.
Steam Generating System
- 25. Fire Protection Systems
- 26. Process Computer System 27.
Radiation Monitoring System 28.
Containment Hydrogen Monitoring and Control
- 29. Radioactive Waste Disposal B.
Applied Fundamentals and Plant Specific Topics 1.
Reactor Physics Theory 2.
Thermodynamics 3.
Heat Transfer 4.
Fluid Flow 5.
Thermal Hydraulics 6.
Reactor Chemistry 7.
Non-Nuclear Instrumentation 8.
Nuclear Radiation Protection and Health Physics 9.
Incore Analysis Program 10.
Fuel and System Design Limits
- 11. Reactor Protection and Engineered Safeguards
- 12. Plant Emergency Plan 13.
Technical Specifications 14.
Selected General Operating Procedures
- 15. Selected Emergency and Casualty Procedures 16.
Transient and Accident Analysis C.
Simulator Training:
The objectives of the' simulator training were -
1.
To reinforce previous training material, 2.
To demonstrate plant and operator response to a given condition or
- event, 3.
To describe the Shift Technical Advisor's role during an accident, 4.
To introduce the concept of " Safety Functions".
During the training, the following material was covered.
1.
Operation Board Orientation 2.
Reactor Coolant System instrumentation and operations demonstration 3.
Chemical and Volume Control System instrumentation and operation demonstration 4.
Manual reduction of reactor power from 100% to 85%
5.
Reduction of load 100MWe 6.
Stop and start one reactor coolant pump at approximately 70% reactor power 7.
Reduction of load to 40%
8.
Close and reopen one main steam isolation valve 9.
Plant startup to 20% reactor power l
10.
Accident Analysis Demonstration a.
Steam tube rupture b.
Large steam line break outside containment c.
Large steam line break inside containment d.
ATWS 2
j
- 11. Demonstration of actions resulting from engineered safety features actuation signals a.
Safety Injection Actuation Signal b.
Containment Spray Actuation Signal c.
Containment Isolation Signal d.
Containment Radiation Signal e.
Recirculation Actuation Signal f.
Steam Generator Isolation Signal g.
Loss of Coolant Incident Sequences h.
Shutdown Sequences 12.
Three Mile Island Duplication Attempt 13.
Natural Circulation Demonstration 14.
Accident Recovery 15.
Accident Identification Exercises 1
L a
3
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