ML20079M299
| ML20079M299 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/24/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-TM NUDOCS 8401270254 | |
| Download: ML20079M299 (10) | |
Text
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DUKE POWER GOMPANY P.O. BOK 33189 CHARLOTTE. N.C. 28242 HAL B. TUCKER Tzternosz vum reeminear (704) 07N531 January 24, 1984
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Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission-Washington, D. C.~20555 Attention:
Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
Section 13.5.1.3 of the Catawba Safety Evaluation Report discusses License Condition 2, Shift Technical Advisor. As discussed in the attached revised Catawba FSAR pages, the on-shift staff at Catawba will include a Shif t Engineer (STA). This individual fulfills the recommendations of NUREG-0737, Item I.A.l.l.
Very truly yours, Hal B. Tucker ROS/php Attachment cc:
Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector Catauba Nuclear Station Mr.. Robert Guild, Esq.
Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance
'f 213515 Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 8401270254 840124 PDR ADOCK 05000413 E
v Table 1.9-1 (Page 1)
Response to TMI Concerns I. A.1.1 SHIFT TECHNICAL ADVISOR A Shift Technical Advisor is included'in the on-shift organization as discussed in Section 13.1 and the Technical Specifications.
I.A.1.2 SHIFT SUPERVISOR ADMINISTRATIVE DUTIES See Section 13.1 I.A.1.3 SHIFT MANNING The shift crew composition for operation of Catawba Unit 1 will be in accor-dance with Section 6.0 of the Technical Specifications.
Provisions governing the amount of overtime worked by licensed operators is addressed in an administrative procedure.
This procedure states that licensed operators shall (1) not work more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> straight, (2) not work more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, (3) not work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, and (4) not work more than 14 consecutive days without having 2 consecutive days off.
These limits on working time do not include shift turnover time.
Deviation from these limits on working time will be authorized anc Scumented by either the Superintendent of Operations or the Station Manager.
I.A.2.1 IMMEDIATE UPGRADING OF OPERATOR AND SENIOR OPERATOR TRAINING AND QUALIFICATION See Section 13.2 I.A.2.3 ADMINISTRATION OF TRAINING PROGRAMS FOR LICENSED OPERATORS See Section 13.2 I.A.3.1 REVISE SCOPE AND CRITERIA FOR LICENSING EXAMS See Section 13.2
- 1. B.1. 2 EVALUATION OF ORGANIZATION AND MANAGEMENT IMPROVEMENTS OF NEAR-TERM OPERATING LICENSE APPLICANTS See Sections 13.1 and 13.4 I. C.1 SHORT-TERM ACCIDENT ANALYSIS AND PROCEDURE REVISION Duke is in the process of developing new procedures and training guidelines for controlling and mitigating small break LOCAs, incidents of inadequate core cooling, and certain anticipated transients.
Duke's effort is in conjunction with analysis and research being performed by Westinghouse.
Rev. 9
v Table 1.9-1 (Page 5)
Response to TMI Concerns conditions at any' level of coolant activity.
The design of this system signi-ficantly reduces radiation exposures during sample collection under accident conditions.
In addition to the reactor coolant sample line, a containment atmosphere sample line will be routed to a new accident level sampling panel.
The containment atmosphere sample will be obtained from the hydrogen analyzer sample lines.
Sample line length is minimized and large radius bends are used to minimize plate out and provide an accurate effluent sample.
Procedures for collection and transport of reactor coolant, sump water, and con-tainment air samples under post-accident conditions have been revised to incor-porate actions to be taken to minimize radiation exposures.
These procedures specify the preplanning to be performed as well as modifications and approvals required prior to sample collection.
Samples can be collected within one hour in all instances where personnel exposure does not exceed 3 rem /qtr whole body and 18 3/4 rem /qtr to the extremities.
If the predicted personnel exposures exceed the above, samples can still be collected and analyzed but not within one hour.
The time required to install additional shielding and allow sample collection while minimizing personnel exposure will be dependent upon the nature of the event. The analytical procedures have been reviewed and deter-mined to be adequate for the expected sample activity levels.
II.B.4 T. RAINING FOR MITIGATING CORE DAMAGE Duke has modified the Catawba training program in order to place increased emphasis on the operation and significance of any Catawba systems or instru-mentation which could be used to monitor and control accidents in which the core may be severely damaged. This additional training identified the vital instrumentation which supplies the operator with needed information in a de-graded core situation.
The training also identifies alternate methods of ob-taining this information as well as specific instructicn in the interpretation of instrument readings in degraded core situations.
Operating personnel from the station manager through the operating chain (including the Shift Engineers (STA's) to the licensed operators will receive training for mitigating core damage.
II.D.1 RELIEF AND SAFETY VALVE TEST REQUIREMENTS EPRI PWR Safety and Relief Valve Test Program will be used by Duke to respond to NRC recommendations in NUREG-0737.
The Catawba valves covered by the EPRI program are pressurizer safety valves (Dresser type 6-31749A), pressurizer PORV (Control Components, Inc.), and PORV block valves (Rockwell Equiwedge gate valve).
Testing is complete for the three types of valves.
Duke has received complete Rev. 9
Table 1.9-1 (Page Sa)
Response to TMI Concerns EPRI reports covering the PORV's and block valves but has not received all test data for the safety valve tests.
Review of EPRI test data should be complete by March 15,-1983.
Plant specific information on the Catawba pressurizer safety valves, PORV's and PORV block valves was transmitted by H.R. Tucker's letter of October 26, 1983 to
- H. R. Denton.
l O
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b Rev. 9
CNS.
I _(s) Senior Station Quality Assurance Engineer The functions, responsibilities and authorities of the Senior Station Quality
~ Assurance Engineer are described in Topical Report, DUKE-1A.
13.1.2.3 Shift Crew Composition The operating shift crew consists of a Shift SLpervisor, an Assistant Shift
[ Supervisor for each unit, a shift engineer (STA), and appropriate licensed and unlicensed operators.
In addition, a health physics technician is on site at all times when there is fuel in a reactor and a rad / chem technician is onsite at all times when a unit is being operated in Modes 1-4.
13.l.3 QUALIFICATIONS OF STATION PERSONNEL The qualifications of personnel in the operating staff are in accordance with Section 4 of ANSI N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel", and are in accordance with Regulatory Guide 1.8 (Rev. 1) with the exception of those for the Radiation Protection Manager in Part C of Regulatory Guide 1.8.
The RPM (Station Health Physicist) shall have a bachelor's degree in a science or engineering subject or the equivalent in experience, including some formal training in radiation protection, and shall have at least five years of profes-sional experience in applied radiation protection of which three years shall be in applied radiation protection w~ork in one of Duke Power Company's nuclean, stations. A qualified individual who does not meet the above requirements, but who has demonstrated the required radiation protection management capabili-ties and has professional experience in applied radiation protection work at one of Duke Power Company's multi-unit nuclear stations, may be appointed to the position of Station Health Physicist by the station Manager, based on the recommendations of the System Health Physicist and as approved by the General Manager, Nuclear Stations.
An individual who temporarily replaces the RPM shall have a bachelor's degree in a science or engineering subject or the equivalent in experience and shall Q471*18 have at least two years experience, one of which shall be nuclear power plant experience.
Six months experience shall be on site.
Replacement personnel for positions at the station are fully trained and qualified.to fill their appointed positions.
13.1-6 Rev. 9
i
'p.
I CNS.,
.(n) Assistant Shift Supervisor An Assistant Shift Supervisor shall have the same qualifications as a Shift Supervisor.
1 (o) Shift Engineer A Shift Engineer (STA) shall have a bachelor's degree or~ equivalent in a scientific or engineering discipline and two years of responsible nuclear power plant experience accompanied by an overall knowledge of the plant.
l (p) Operators Operators to be licensed by the NRC shall have a high shcool diploma, or equiv-alent, and two years of nuclear or fossil station exoerience, of which a minimum of one year shall be nuclear station experience.
In order to be acceptable for
. full responsibility in a job, they shall hold a Reactor Operator license.
Operators, whether or not they are to be licensed by the liRC, should have a high_ school diploma, or equivalent, and should po sess a high degree of manual dexterity and mature judgment.
g (q) Technicians Technicians in responsible positions. (i.e., individuals who direct the activities of others and who are responsible for the activities they direct) shall have au minimum of two years of experience in their specialty.
These personnel should have a minimum of one year of related technical training in addition to their experience.
1 (r) Maintenance Personnel Maintenance personnel in responsible positions (i.e., individuals who direct the activities of others and who are responsible for the activities they direct) shall have a minimum of three years of experience in one or more crafts.
They should possess a high degree of manual dexterity and ability, and should be capable of learning and applying basic skills in maintenance operations.
13.1.3.2 Qualifications of Station Personnel Qualificatiens of station personnel are provided in Table 13.1.3-1 13.1-9 Rev. 9
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CNS,
(d) Operating Engineer The Operating Engineer has responsibility for directing the actual day-to-day operation of the unit to which he is assigned and may assume complete responsi-bility for station operation in the absence of the Superintendent of Operations.
(e) Shift Supervisor A Shift Supervisor is responsible for the actual operation of the station on his assigned shift.
He directs the activities of the operators on his shift and is cognizant of all maintenance activity being performed while he is on duty.
Tne Shift Supervisor on duty has both the authority and the obligation to shut down a unit if, in his opinion, conditions warrant this action.
(f)~ Assistant Sh'*t Supervisor An Assistant Shift Supervisor assists the Shift Supervisor in operation of the station on his assigned shift.
The Assistant Shift Supervisor on duty has both the authority and the obligation to shut down a unit if, in his opinion, conditions warrant this action.
1 (g) Shift Engineer
' A Shift Engineer (STA) provides evaluation and assessment of both normal and unanticipated transients.
s I (h) Reactor Operator A Reactor Operator is responsible for the actual operation of a unit on his assigned shift.
The Reactor Operator has both the authority and obligation to shut down a unit if, in his opinion, conditions warrant this action.
l (i) Nuclear Equipment Operator A Nuclear Equipment Operator is responsible for the operation of equipment outside of the Control Room.
l (j) Superintendent of Technical Services The Superintendent of Technical Services is responsible for directing the activities of the Technical Services Group, which includes performance, chemistry and health physics.
In the event of absence of the station Manager, the Superintendent of Technical Services, if so designated, assumes the res-ponsibilities and authority of the station Manager.
l (k) Performance Engineer The Performance Engineer directs data gathering and evaluation in the areas of equipment and station performance.
Specifically included in this are core physics and core performance, from both nuclear and thermal-hydraulic con-siderations.
He assists in setting up fuel shuffling patterns and partici-pates in other phases of fuel management.
13.1-4 Rev. 9
n CNS.
l _ (1) Station Health Physicist The Station Health Physicist has the responsibility for conducting the health physics program.
His duties include the training of personnel in use of equip-ment, control of radiation exposure of personnel, continuous determination of the_ radiological status of the station, surveillance of radioactive waste dis-posal operations,' conducting the radiological environmental monitoring program and maintaining all required records.
He has direct access to the station Manager in matters concerning any phase of radiological protection.
The Station Health Physicist also has direct support as required from the System Health Physicist and his staff.
1 (m) Station Chemist The Station Chemist is responsible for overall chemistry and radiochemistry requirements, with special emphasis on primary and secondary system water chemistry.
l (n)- Licensing and Projects Engineer The Licensing and Projects Engineer has responsibility for coordinating station modification activities and interfaces with regulatory agencies and for providing reviews of appropriate station technical matters.
l '(o) Superintendent of Maintenance i.
The Superintendent of Maintenance is responsible for directing the activities of the Maintenance Group, which includes mechanical and electrical mainten-ance and instrumentation and control.
In the event of absence of the station Manager, the Superintendent of Maintenance, if so designated, assumcs the res-ponsibilities and authority of the station Manager, j (p) Maintenance Engineer-(Mechanical)
The Maintenance Engineer (Mechanical) has responsiblity for maintenance of mechanical equipment.
i l (q) Maintenance Engineer (I&E)
The Maintenance Engineer (I&E) has responsibility for maintenance of electrical equipment, instrumentation, controls, and computers.
He also supervises computer maintenance.
l (r) Maintenance Engineer (Planning)
The Maintenance Engineer (Planning) has responsibility for planning and sched-uling of. all maintenance work as well as directing all material management activities.
.13.1-5 Rev. 9
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