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Revising the RIA Regulatory Criteria Paul M. Clifford Sr. Reactor Engineer U. S. Nuclear Regulatory Commission March 7, 2006 RIC 2006 Session T1BC Fuels - Cladding Behavior for Regulatory Applications

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Revising the RIA Regulatory CriteriaPaul M. CliffordSr. Reactor EngineerU. S. Nuclear Regulatory CommissionMarch 7, 2006

RIC 2006Session T1BC

Fuels - Cladding Behavior for Regulatory Applications

2

Fuel Response to a Rapid Reactivity Insertion

Time

Pow

er /

Te

mpe

ratu

re Rod Power

Fuel Temperature

Clad Temperature

3

Current Regulatory PositionGeneral Design Criterion 28• Regulatory Guide 1.77• NUREG-0800 Standard Review Plan

4

RG 1.77 Acceptance Criteria1. Fuel radial average energy density

limited to 280 cal/g at any axial node.2. Maximum reactor pressure limited to the

value that will cause stresses to exceed Service Level C as defined in the ASME Boiler and Pressure Vessel code.

3. Offsite dose consequences limited to well within 10CFR Part 100.

5

NUREG-0800 Fuel Clad Failure1. Radial average fuel enthalpy greater

than 170 cal/g for BWRs at zero or low power.

2. Local heat flux exceeding fuel thermal design limits (e.g. DNBR and CPR) for all PWR events and at-power events in BWRs.

6

Empirical Database

7

RIL 0401 Operability Assessment

• Developed an empirically-based fuel clad failure threshold.

• Performed a best-estimate neutronics analysis over a range of LWR conditions.

• Concluded that operating reactors are unlikely to experience fuel cladding failure during a postulated RIA.

8

Revising the RIA Regulatory Criteria

9

Clad Failure Threshold

Oxide or Excess Hydrogen

Fuel

Ent

halp

y C

hang

e (c

al/g

)

SRP4.2 BWR Limit

Thermal Design Limit

10

Core Coolability Limit

Rod Burnup

Peak

Fue

l Ent

halp

y (c

al/g

)

Empirical

Fuel Melt

Clad Failure

RG 1.77 (1974)

MacDonald (1980)

11

Revised Source Term• Fission product inventory available for release

into the reactor coolant system:– Steady-state gap inventory– Transient-induced fission gas release from pellet

• Significant transient-induced fission gas release experienced during RIA and power-ramp tests.

• Basis of current radiological guidance being investigated to determine whether gap fractions remain conservative.

12

Conclusion• No immediate safety concerns related to

RIA fuel performance based on RIL 0401.• NRC will continue efforts to revise criteria

and update Regulatory Guides and SRP.– Technical basis of revised acceptance criteria

being developed. – Public meetings will be scheduled during the

revision process.