Hinkley Point B - Planned Intervention
- Site: Hinkley Point B
- IR number: 16-047
- Date: June 2016
- LC numbers: 2, 10, 23, 24, 27, 28
Purpose of intervention
This was a planned inspection of EDF Energy Nuclear Generation Ltd's (NGL's) Hinkley Point B power station, undertaken as part of the planned intervention strategy for the Operating Facilities Programme (OFP) of the Office for Nuclear Regulation (ONR).
The work was carried out in-line with the planned inspection programme contained in the Hinkley Point B Integrated Intervention Strategy (IIS).
Interventions Carried Out by ONR
I (the nominated site inspector for Hinkley Point B) with support from ONR inspectors:
- Carried out a System Based Inspection on station control and instrumentation, specifically on the Data Processing and Control System, (DPCS) jointly with a NGL Independent Nuclear Assurance team.
- Carried out a licence condition 2 compliance inspection on marking of the site boundary.
- Attended the Site Stakeholder Group meeting.
- Discussed key matters with the site internal regulator.
- Held information exchange meetings with site personnel.
Explanation of Judgement if Safety System Not Judged to be Adequate
The Data Processing and Control System (station control and instrumentation) was judged to meet the requirements of the safety case and was adequate.
Key Findings, Inspector's Opinions and Reasons for Judgements Made
From the System Based Inspection on the DPCS we concluded that:
- LC 10 (Training) - We examined the role profiles and training records of personnel involved in the operation, maintenance and testing of the DPCS. We found that the personnel undertaking these maintenance and inspection activities were suitably qualified and experienced. We therefore assigned a rating of green (no formal action required) to this element of the inspection.
- LC 23 (Operating Rules) - The licensee's safety case and operating rules were contained within its Living Safety Case Document and Technical Specifications. We considered that both documents could be enhanced, but overall we concluded that for the DPCS they did support each other and were implemented as intended. We therefore assigned a rating of green (no formal action) to this element of the inspection.
- LC 24 (Operating Instructions) - We reviewed a number of operating instructions including station operating instructions, maintenance instructions, plant operating instructions and user guides for the DPCS. We considered then to be satisfactory and we therefore assigned a rating of green (no formal action required) to this element of the inspection.
- LC 27 (Safety Mechanisms, Devices and Circuits) - The DPCS was considered to be a safety related system as it provided information and alarms to the operators who acted on this information. It also had a number of control loops to enable the reactor to operate within its normal boundary. The evidence provided indicated that for both systems selected, adequate arrangements were in place and these were being followed. It was our judgement therefore, that a rating of green (no formal action required) was appropriate for this element of the inspection.
- LC 28 (Examination, Inspection, Maintenance and Testing) - We reviewed the maintenance schedule, work instructions, work orders and interviewed a Maintenance Engineer. The evidence provided during our site visit indicated that the LC28 arrangements for the inspection, maintenance and testing of DPCS were adequate and our judgement was that a rating of green (no formal action required) was appropriate for this element of the inspection.
- LC 34 (Leakage and Escape of Radioactive Material and Radioactive Waste) - We considered that this was not applicable to the DPCS system.
We carried out an inspection of DPCS plant and equipment and considered them to be in very good condition and well maintained. The housekeeping in the area was excellent.
After considering all of the evidence presented by NGL we concluded that the arrangements and their implementation, associated with the Data Processing and Control System met the requirements of the safety case and were adequate.
For LC2 (Marking of the Site Boundary) - We were satisfied that the site boundaries were adequately marked and that robust arrangements and facilities were in place to prevent unauthorised persons from inadvertently entering the site. We therefore assigned a rating of green (no formal action required) to this inspection.
I attended the Hinkley Point Site Stakeholder Group meeting. I was satisfied with the discussions and behaviours at the meeting which enabled me to interact with stakeholders and clarify ONR's regulatory activities.
I met with an INA evaluator on site to discuss a number of issues and promote effective working interactions. On this occasion we discussed the System Based Inspection that was carried out jointly by ONR and INA, staffing levels on the site and a number of safety initiatives that were being progressed.
Finally I held a number of information exchange meetings with station staff to gather information on the condition of the gas pressure relief valves, the recent manual shutdown of Reactor 4 due to voltage fluctuations on the turbine, the control of laptops on site and progress with arrangements for the next annual review of safety meeting.
The intervention was performed in line with ONR's guidance requirements (as described in our technical inspection guides) in the areas inspected.
Conclusion of Intervention
There were no findings from this inspection that could significantly undermine nuclear safety. At present, no additional regulatory action is needed over and above the planned interventions of Hinkley Point B power station as set out in the Integrated Intervention Strategy, which will continue as planned.