TS 6.0 — Administrative Controls
6.1 — Responsibility
- The Plant Manager is responsible for overall facility operation
- The Senior Nuclear Shift Supervisor (or designee) is responsible for Control Room command function
- A management directive signed by the senior corporate nuclear officer is reissued annually to all station personnel (TS 6.1)
▶ Bases — 6.0 Administrative Controls
Bases — 6.0
Administrative controls establish the organizational structure, staffing requirements, procedural controls, and reporting requirements necessary to ensure safe plant operation. The safety limit violation actions ensure prompt shutdown, notification, and root cause analysis. The on-the-spot procedure change provisions balance operational flexibility with adequate oversight.
6.2 — Organization
Shift Staffing and Licensing Requirements
| Position | License Required | Source |
|---|---|---|
| Operations Manager or Asst. Ops Manager | SRO license | TS 6.3.2 |
| Senior Nuclear Shift Supervisor | SRO license | TS 6.3.2 |
| Nuclear Shift Supervisor | SRO license | TS 6.3.2 |
| Nuclear Control Operator | RO license | TS 6.3.2 |
| Shift Technical Advisor | No license (Bachelor’s degree or equivalent in science/engineering) | TS 6.2.3 |
The STA serves in an advisory capacity to the Senior Nuclear Shift Supervisor on engineering aspects of safe operation. (TS 6.2.3)
Exam -- 2023 Q94
Shift complement unexpected absence: per OP-AA-101-111, the shift complement may be one less than the minimum for up to 2 hours to accommodate an unexpected absence, provided immediate action is taken to restore. This provision does NOT permit any shift position to be unmanned upon shift change -- the on-duty member must remain until a relief is available. The preferred action is to hold the off-going shift personnel.
Exam — 2019 Q94
TS Table 6.2-1 STA staffing (SRO question): a licensed SRO who is also a qualified STA MAY fill the STA minimum staffing requirement on BOTH Unit 1 and Unit 2 concurrently. Additionally, that person MAY fill the STA minimum staffing requirement on Unit 2 while concurrently filling the SRO minimum staffing requirement on Unit 2. Trap: candidates may incorrectly believe the STA role must be dedicated to a single unit, or that an SRO cannot simultaneously fill the STA and SRO positions on the same unit.
6.6 — Reportable Event Action
For REPORTABLE EVENTS:
- Notify NRC and/or submit report per 10CFR50.73
- Each event reviewed by Station Operations Review Committee (SORC)
- Licensee Event Report submitted to Nuclear Review Board and senior corporate nuclear officer (TS 6.6)
6.7 — Safety Limit Violation
TS 6.7 — Safety Limit Violation Actions
a. Place unit in at least HOT STANDBY within one hourb. Notify NRC Operations Center by telephone as soon as possible, in all cases within one hour. Notify senior corporate nuclear officer and senior safety/QA management within 24 hours.
c. Prepare Safety Limit Violation Report (reviewed by SORC): (1) circumstances, (2) effects on components/systems/structures, (3) corrective action
d. Submit report to Commission, senior safety/QA management, and senior corporate nuclear officer within 14 days
6.8 — Procedures and Programs
6.8.1 Required Written Procedures
- Applicable procedures from Reg Guide 1.33, Rev 2
- Refueling operations
- Surveillance and test activities of safety-related equipment
- Security Plan implementation
- Emergency Plan implementation
- Fire Protection Program implementation
- PROCESS CONTROL PROGRAM implementation
- OFFSITE DOSE CALCULATION MANUAL implementation
- Quality Assurance Program for effluent and environmental monitoring (TS 6.8.1)
6.8.3 On-the-Spot Procedure Changes
Key Requirement
On-the-spot changes to procedures may be made provided:a. The intent of the original procedure is not altered
b. Approved by two members of plant management staff, at least one holding an SRO license on the affected unit
c. Documented and receives same level of review/approval as original within 14 days
6.8.4 Required Programs
| Program | Purpose | Source |
|---|---|---|
| Primary Coolant Sources Outside Containment | Reduce leakage from systems that could contain radioactive fluids during accident | TS 6.8.4.a |
| In-Plant Radiation Monitoring | Ensure capability to determine airborne iodine under accident conditions | TS 6.8.4.b |
| Secondary Water Chemistry | Monitor secondary chemistry to inhibit SG tube degradation | TS 6.8.4.c |
| Radioactive Effluent Controls Program | Control liquid and gaseous effluents per ODCM | TS 6.8.4 |
| Radiological Environmental Monitoring Program | Monitor environment around the plant | TS 6.8.4 |
| Steam Generator Program | SG tube inspection, plugging criteria, repair criteria | TS 6.8.4 |
| Containment Leakage Rate Testing Program | Type A, B, C testing per 10CFR50 Appendix J | TS 6.8.4 |
| Surveillance Frequency Control Program (SFCP) | Control surveillance frequencies; changes require NRC-approved methodology | TS 6.8.4 |
| Control Room Envelope Habitability Program | Maintain CRE habitability, limit DBA dose to <5 rem TEDE | TS 6.17 |
6.9 — Reporting Requirements
Routine Reports
| Report | Frequency | Due Date | Source |
|---|---|---|---|
| Annual Radiological Environmental Operating Report | Annual | Before May 1 | TS 6.9.1.7 |
| Annual Radioactive Effluent Release Report | Annual | Before May 1 | TS 6.9.1.8 |
| Core Operating Limits Report (COLR) | Each reload cycle | Per TS 6.9.1.9 | TS 6.9.1.9 |
| SG Tube Inspection Report | After each inspection | Within 180 days | TS 6.9.1.10 |
| Pressure and Temperature Limits Report (PTLR) | As needed | Per TS 6.9.1.11 | TS 6.9.1.11 |
| Specific Activity Report (if 3.4.9 exceeded) | Annual | In annual report | TS 6.9.1.5 |
Special Reports (6.9.2)
Submitted to NRC Document Control Desk with copy to Region I Administrator within the time specified for each report.
6.12 — High Radiation Area Controls
Dose Rates ≤1.0 rem/hr at 30 cm
- Barricaded and posted as high radiation area
- Access controlled by RWP or equivalent
- Individuals must possess continuous radiation monitoring device (dose rate display, integrating dosimeter with alarm, or remote-monitored device) (TS 6.12.1)
Dose Rates >1.0 rem/hr at 30 cm
- Locked access (in addition to above requirements)
- Keys controlled by Radiation Protection supervision
- Direct or remote continuous surveillance by qualified radiation protection personnel (TS 6.12.2)
6.13 — Process Control Program (PCP)
Approved by Commission. Changes require SORC review/acceptance and Plant Manager approval. (TS 6.13)
6.14 — Offsite Dose Calculation Manual (ODCM)
Approved by Commission. Changes require SORC review/acceptance and Plant Manager approval. Changes submitted with Annual Radioactive Effluent Release Report. (TS 6.14)
6.16 — TS Bases Control Program
Key Concept
Changes to the Bases can be made without prior NRC approval provided the changes do not require: (1) a change to the TS incorporated in the license, or (2) a change to the UFSAR/Bases requiring NRC approval per 10CFR50.59. Changes implemented without prior NRC approval are provided to the NRC per 10CFR50.71(e).
6.17 — Control Room Envelope Habitability Program
Ensures CRE occupants can control the reactor safely under normal conditions and maintain safe condition following a radiological event, hazardous chemical release, or smoke challenge. DBA dose limit: 5 rem TEDE for the duration of the accident. Includes CRE boundary definition, configuration control, unfiltered air inleakage testing per Reg Guide 1.197, and CRE pressure measurement. (TS 6.17)
View Tech Spec PDF (Section 6 in TS document)
Connections
- Related concepts: Radiation Monitoring
- Related systems: Containment
- Related exam questions: 2019 Q94, 2023 Q94
- Related JPMs: 2020 JPM SRO-A2
- Related exam: 2019 NRC Written Exam, 2020 NRC Operating Exam, 2023 NRC Written Exam