diff --git a/docs/source/pythonapi/index.rst b/docs/source/pythonapi/index.rst
index 80da52998..1b13dfbfe 100644
--- a/docs/source/pythonapi/index.rst
+++ b/docs/source/pythonapi/index.rst
@@ -287,17 +287,11 @@ Multi-group Cross Sections
     openmc.mgxs.AbsorptionXS
     openmc.mgxs.CaptureXS
     openmc.mgxs.Chi
-    openmc.mgxs.ChiPrompt
     openmc.mgxs.FissionXS
     openmc.mgxs.InverseVelocity
     openmc.mgxs.KappaFissionXS
     openmc.mgxs.MultiplicityMatrixXS
-    openmc.mgxs.NuFissionXS
     openmc.mgxs.NuFissionMatrixXS
-    openmc.mgxs.NuScatterXS
-    openmc.mgxs.NuScatterMatrixXS
-    openmc.mgxs.PromptNuFissionXS
-    openmc.mgxs.PromptNuFissionMatrixXS
     openmc.mgxs.ScatterXS
     openmc.mgxs.ScatterMatrixXS
     openmc.mgxs.TotalXS
diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py
index 10e10738e..966550d8c 100644
--- a/openmc/mgxs/mgxs.py
+++ b/openmc/mgxs/mgxs.py
@@ -58,7 +58,7 @@ _DOMAINS = (openmc.Cell,
             openmc.Material,
             openmc.Mesh)
 
-# Supported ScatterMatrixXS and NuScatterMatrixXS angular distribution types
+# Supported ScatterMatrixXS angular distribution types
 MU_TREATMENTS = ('legendre', 'histogram')
 
 # Maximum Legendre order supported by OpenMC
diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py
index 8b3ffb3e9..c0e82c79f 100644
--- a/openmc/mgxs_library.py
+++ b/openmc/mgxs_library.py
@@ -1563,19 +1563,17 @@ class XSdata(object):
                                      temperature=294., nuclide='total',
                                      xs_type='macro', subdomain=None):
         """This method allows for either the direct use of only an
-        openmc.mgxs.MultiplicityMatrixXS OR
-        an openmc.mgxs.NuScatterMatrixXS and
+        openmc.mgxs.MultiplicityMatrixXS or an openmc.mgxs.ScatterMatrixXS and
         openmc.mgxs.ScatterMatrixXS to be used to set the scattering
-        multiplicity for this XSdata object. Multiplicity,
-        in OpenMC parlance, is a factor used to account for the production
-        of neutrons introduced by scattering multiplication reactions, i.e.,
-        (n,xn) events. In this sense, the multiplication matrix is simply
-        defined as the ratio of the nu-scatter and scatter matrices.
+        multiplicity for this XSdata object. Multiplicity, in OpenMC parlance,
+        is a factor used to account for the production of neutrons introduced by
+        scattering multiplication reactions, i.e., (n,xn) events. In this sense,
+        the multiplication matrix is simply defined as the ratio of the
+        nu-scatter and scatter matrices.
 
         Parameters
         ----------
-        nuscatter: {openmc.mgxs.NuScatterMatrixXS,
-                    openmc.mgxs.MultiplicityMatrixXS}
+        nuscatter: openmc.mgxs.ScatterMatrixXS or openmc.mgxs.MultiplicityMatrixXS
             MGXS Object containing the matrix cross section for the domain
             of interest.
         scatter: openmc.mgxs.ScatterMatrixXS