WENRA Reactor Safety Reference Levels January 2007

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4.2 A qualification procedure shall be adopted to confirm that SSCs important to safety meetthroughout their design operational lives the demands for performing their function,taking into account environmental conditions 36 over the lifetime of the plant and whenrequired in anticipated operational occurrences and accident conditions.36 Environmental conditions include as appropriate vibration, temperature, pressure, jet impingement, electromagneticinterference, irradiation, humidity, and combinations thereof.20
Western European Nuclear Regulators’ AssociationREACTOR HARMONIZATION WORKING GROUPIssue H: Operational limits and conditionsDocument status: FinalSafety area: OperationReference levels1. Purpose1.1 OLCs shall be developed to ensure that plants are operated in accordance with designassumptions and intentions as documented in the SAR.1.2 The OLCs shall define the conditions that must be met to prevent situations that mightlead to accidents or to mitigate the consequences of accidents should they occur.2. Establishment and review of OLCs2.1 Each established OLC shall be justified based on plant design, safety analysis andcommissioning tests.2.2 OLCs shall be kept updated and reviewed in the light of experience, developments inscience and technology, and every time modifications in the plant or in the safety analysiswarrant it, and changed if necessary.2.3 The process for making modifications or temporary modifications of OLCs shall bedefined. Such modifications shall be adequately justified by safety analysis andindependent safety review.3. Use of OLCs3.1 The OLCs shall be readily accessible to control room personnel.3.2 Control room operators shall be highly knowledgeable of the OLCs and their technicalbasis. Relevant operational decision makers shall be aware of their significance for thesafety of the plant.4. Scope of OLCs4.1 OLCs shall cover all operational plant states including power operation, shutdown andrefuelling, any intermediate conditions between these states and temporary situationsarising due to maintenance & testing.5. Safety limits, safety systems settings and operational limits5.1 Adequate margins shall be ensured between operational limits and the established safetysystems settings, to avoid undesirably frequent actuation of safety systems.5.2 Safety limits shall be established using a conservative approach to take uncertainties inthe safety analyses into account.21
Page 4 and 5: 3. Sufficiency and competency of st
Page 6 and 7: implemented on site and that the se
Page 8 and 9: normal operation, anticipated opera
Page 10 and 11: in the plant states: normal operati
Page 12 and 13: 8.6 Any failure, occurring as a con
Page 14 and 15: 10.6 For times when the main contro
Page 16 and 17: - loss of off-site power- load drop
Page 18 and 19: to enable a timely assessment of th
Page 22 and 23: 6. Unavailability limits6.1 Limits
Page 24 and 25: Western European Nuclear Regulators
Page 28 and 29: e decided with due regard for the n
Page 30 and 31: 3.3 SAMGs shall be developed in a s
Page 32 and 33: 2.12 The SAR shall describe the on-
Page 34 and 35: 3.4 PSA shall be used to assess the
Page 40 and 41: 5. Training, drills and exercises5.
Page 42 and 43: - For all normal operating and shut

WENRA Reactor Safety Reference Levels January 2007

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