diff --git a/openmc/deplete/abc.py b/openmc/deplete/abc.py
index e3587f0527..3e2c37ece7 100644
--- a/openmc/deplete/abc.py
+++ b/openmc/deplete/abc.py
@@ -331,7 +331,7 @@ class NormalizationHelper(ABC):
             `fission_rates` for :meth:`update`.
         """
 
-    def update(self, fission_rates, mat_index=None):
+    def update(self, fission_rates):
         """Update the normalization based on fission rates (only used for
         energy-based normalization)
 
@@ -341,8 +341,6 @@ class NormalizationHelper(ABC):
             fission reaction rate for each isotope in the specified
             material. Should be ordered corresponding to initial
             ``rate_index`` used in :meth:`prepare`
-        mat_index : int
-            Material index
         """
 
     @property
diff --git a/openmc/deplete/helpers.py b/openmc/deplete/helpers.py
index 1e382576ee..3a7928a52d 100644
--- a/openmc/deplete/helpers.py
+++ b/openmc/deplete/helpers.py
@@ -426,7 +426,7 @@ class ChainFissionHelper(EnergyNormalizationHelper):
 
         self._fission_q_vector = fission_qs
 
-    def update(self, fission_rates, mat_index=None):
+    def update(self, fission_rates):
         """Update energy produced with fission rates in a material
 
         Parameters
@@ -435,8 +435,6 @@ class ChainFissionHelper(EnergyNormalizationHelper):
             fission reaction rate for each isotope in the specified
             material. Should be ordered corresponding to initial
             ``rate_index`` used in :meth:`prepare`
-        mat_index : int
-            Unused
         """
         self._energy += dot(fission_rates, self._fission_q_vector)
 
diff --git a/openmc/deplete/openmc_operator.py b/openmc/deplete/openmc_operator.py
index 6e6f8dd8d4..c340650782 100644
--- a/openmc/deplete/openmc_operator.py
+++ b/openmc/deplete/openmc_operator.py
@@ -528,13 +528,13 @@ class OpenMCOperator(TransportOperator):
             # Accumulate energy from fission
             if fission_ind is not None:
                 self._normalization_helper.update(
-                    tally_rates[:, fission_ind],
-                    mat_index=mat_index)
+                    tally_rates[:, fission_ind])
 
             # Divide by total number and store
             rates[i] = self._rate_helper.divide_by_adens(number)
 
         # Scale reaction rates to obtain units of reactions/sec
+        print(f"flux, power, or source rate: {self._normalization_helper.factor(source_rate)}")
         rates *= self._normalization_helper.factor(source_rate)
 
         # Store new fission yields on the chain